JPRS ID: 9416 USSR REPORT ENERGY

• Document Type: CREST
• Collection: JPRS
• Document Number (FOIA) /ESDN (CREST): CIA-RDP82-00850R000300050036-4
• Release Decision: RIF
• Original Classification: U
• Document Page Count: 33
• Document Creation Date: November 1, 2016
• Sequence Number: 36
• Content Type: REPORTS

APPROVE~ FOR RELEASE: 2007/02/08: CIA-R~P82-00850R000300050036-4

'~`3-~" ~~#'~~~'~~i'i- ~ '3 ~ '~=a'~' ~'~:~'3 i ~
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2047102/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY
JPRS L/9416
28 November 1980
~JSSR Re ort
p
ENERGY
(F~ UO 24/80)
Fg~$ FC�REIGN BROADCAST INFORMATION SERVICE
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2047102/08: CIA-RDP82-00850R000300050036-4
NOTE
JPRS publications contain information primarily from foreign
- newspapers, periodi:als and books, but also from news agency
~ransmissions an2i broadcasts. Materials froa foreign-language
sources are translated; those from English-language sources
_ are transcribed or reprinted, with the original phrasing and
_ other characteristics retained.
- Headlines, editorial reports, and matQrial enclosed in brackets
- are supplied by JPRS. Processing indicators such as [Text]
or [Excerpt] in che first line of each item, or following the
last line of a brief, indicate how the original information was
processed. Where no processi.ng indicatar is given, the infor-
mation was summarized or extracted.
Unfami?iar nacnes rendered phcneticaily or transliterated are
enclosed in paren~heses. Words or names preceded by a ques-
_ tion mark and enclosed in parentheses were not ~lear in the
original but have been supplied as a~,propriate in context.
_ Other unattributed parenthetical notes with in the body of an
item originate with the source. Ti.mes within items are as
given by source.
The contents of this publication in no way represent the poli-
cies, views or attitudes of the U.S. Government.
COPYRIGHT LAWS AND REGULATIONS GOVERNING OWNERSHIP OF
MAT.ERIALS REPRODliCE~ HEREIN REQUIRE THAT DISSEMINATION
OF THIS PUBLZCATION BE RESTRICTED FOR OFFICIAL USE O~~TLY.
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2047102/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY
JPRS L/9416
28 November 1980
USSR REPORT
ENERGY
(FOUO 24/80)
- CONTENTS
ELECTRIC POWER
MEI Nuclear Power Research
(N.G. Rassokhin.; TEPLOEN~tGETIRA, C~t 80) 1
Standard WER-1000 AES Safety Systems
(V.P. Tatarnikov; TEPLOENERGETIRA, Oct 80) b
Armenian AES Seismic Stability
(R.S. Galechyan, et al; TEPLOENERGETIKA, Oct 80) 13
~~,c
Pet�.roleum-Bearing Prospects of South Caspian Basin
(M.M. Grachevskiy, et al; IZVESTIYA AKADII~III NAUK SSSR:
SERIYA GEOLOGICHESRAYA, Aug 80) 19
- a - [III - USSR - 37 FOUO]
FCIiP nFFTf'iAT T1~F (1NT.t~
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02148: CIA-RDP82-44850R000300054436-4
FOR OFFI~IAL USE ONLY
_ ELECTRIC POWER
UDC 621.311.25:621.039.001
~IEI NUCLEAR FOWER RESEARCH
Moscow TEPLOENERGETIKA in Russian No 10, Oct 80 pp 2-4
[Article by Doctor of Technical Sciences N. G. Rassokhin: "Basic Directions of Sci-
entific Research by the Nuclear Power Plant Department at Moscow Power Engineering
Institute"]
- [TextJ The services of the MEI (Moscow Order of Lenin Power Engineering Institute)
in training cadres are highly valued: in 1980, the MEI was awarded the Order of the
~ October Revolution. The academic work of the institute is inseparably linked to its
scientific research. This applies in full as well to the activities of the depart-
ment of nuclear power plants at MEI.
Following MEI tradition, tk~e AES department has from the first days of its existence
dor.e active scientific research connected with solving problems of raising technical-
economic indicators, reliability and safety at nuclear power plants. Work has been
- done to study thermal-physical and physical-chemical processes as applicable to re-
actor shape and steam circuitry at both two-loop and one-loop AES's with water-
cooled reactoss.
It is quite obvious that achieving anything substantial along these lines by engin-
eering science is possible at present only given quite exter.sive experimental re-
search on further theoretical processing of the results obtained. Therefore, the
primary attention of the collective has been focused on creating a modern experi- '
mental base for research in bcth thermal physics and physicochemical processes us-
- ing the parameters and characteristics of actual installations. This has led to the
. creation. of original heat-exchange/corrosion and hydrodynamic test stands using ra-
dio-isotope radioscopy. The experimental base consisted of atmospheric pressure in-
stallations, static test stands (no heat carrier circulation) with t,igh and super-
critical parameters, dynamic test stands (with heat carrier circulation) for iso-
thermic testing of structural materials and to study hydrodynamics, and dynamic test
_ stands with experimental fuel [heat-generating] sections. Several test stands were
equipped with radioscopic devices, but a neutron illumination method developed by the
department has recently been introduced.
Circulation loops have been designed, installed and put into operation in combination
with experimental reactors (one being the experimental reactor at Budapest Technical
University), as have several dynamic circulation loops for experimental research both
under isothermic conditions and with heat exchange given reactor radiation of vary-
ing intensity and with varying neutron spectra.
1
I
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPR~VED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY
~
The installations currently in operation were created and began operating in the
~970's, and their improvement continues to this day.
The department is also conducting experiments at industrial installations at the
Beloyarskaya, Novovoronezhskaya, Leningrad, Chernobyl'skaya and Shevchenkovskaya
nuclear power plants, the Kostromskaya GRES, the MEI TETs and other industrial en-
- terprises. Modern research laboratories have been created to research various ma-
terials of models r.ested on test stands, to determine the characteristics of the
heat carrier, develop experimental materials for both physicochemical and thermal-
physics experiments, as well as to research mathematical models. Among them are the
optical and electron microscopy laboratory, the %-ray structure laboratory, the elec-
trochemical and chemical-analytical analysis laboratory, and a reactor kinetics la-
boratory equipped with simulating analog and digital computers. Finally, creation
of a computer center consisting of a unified-series model 1022 computer will be com-
plete by the 25th anniversary of the department, and we subsequently propose to link
it to the institute's main computer center.
Development of the experimental laboratory base was determined by the dynamics of
scientific research development. In the initial years, in spite of limited material-
technical opportunities, the department collective did original research devoted to
studying the corrosion resistance of austenite stainless steei. One feature of that
research was experiments using parameters characteristic of the opPrating conditions
for. parts made of these steels, as well as the combining of static (autoclave) ex-
periments with resource testing in circulation circuits. The results obtained made
- a definite contribution to our understanding of the mechanism of corrosion spalla-
ticn and enabled us to off er recommendations on the reliability of the structural
fc~rmation of certain steam-generation installation elements. It was precisely this
work that laid the foundation for the new scien~ific direction of studying the inter-
' action of structural mate~ials in the heat-transfer agent. In this area, research
has been done on the corrosion-erosion stability of nuclear puwer installation ele-
ments under the most diverse conditions. Among the completed work, we should note
research on the efficiency of heat-transmitting surfaces made of zircon macerial
given surface rimming and high heat flows. Analogous research was done on other
' materials, including stainless steels. It revealed new factors determining the re-
liability and economy of operation of nuclear gower installations. Thus, research
results for the corrosion resistance of austenite stainless steels showed the neces-
sity of replacing it with other heat-transfer agents less demanding as to quality,
more efficient, and, particularly importantly, relatively inexpensive. The initia-
tor of work on replacing austenite stainless steel with perlitic steels was Doctor
of Technical Sciences T. Kh. Margulova. In working c,n the problem, primary atten-
tion was focused on creating methods of passivating carbon steel. The MEI method
- was based on creating strong protective films when working carbon profiles using
complexones. One important feature of this research is that it studied behavior _
patterns given thermic and radiation influence by both the complexones themselves
and the iron complexes formed by them. This research enabled us to br~aden substan-
tially opportunities for using complexones, including the possibility of preventing
and washing off incrustations and of decontaminating AES equipment. For their work
in the area of using complexones in ordinary and nuclear power engineering, doctors
of technical sciences T. Kh. Margulova and N. G. hassokhin and Candidate of Techni-
cal Sciences A. S. Monakhav were awarded the USSR State Prize in 1978. .
The. AES department carries out a broad range of research connected with studying the
patterns of incrustation in the cooling system, with working out steps to prevent it
2
' FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007102/08: CIA-RDP82-00850ROOQ3QOQ5Q036-4
FOR OFFICIAL USE ONLY
_ and effective methods of removing it. This research is also done in a comprehensive
manner, using various experimental installations and reac~or loops, and the results
~ are subsequently checked at industrial installations. The MEI method of washing off
incrustations has already successfully undergone industrial testing and has been ex-
tensively introduced into practice.
In close connection with these research efforts is work to develop an optimum water
system fcr reactors, steam generators and AES's as a whole. The results of water
system research confirm most graphically the effectiveness of the principle adopted
- by the AES department of closely combining comprehensive laboratory experiments with
industrial testing. Typical of the AES department's water system research has been
the far_t that the bulk of the industrial research has been done at a GRES with super-
~ critical parameters, since the condensate and feed water quality there is practically
identical with that at an AES. Setting up scientific research this way has import-
ant features ordinary thermal power engineering gains from the introduction of
progressive new water systems, and transferring them to nuclear power engineering is
more reliable after a long check-out period at a GRES. Thus, resolutions connected
with optimizing 100-percent condensate purification were initially t~ested and intro-
duced by the AES department at the Kostromskaya GRES and were then transferred to a _
similarly shaped AES with an RBMK-1000. A similar situation developed with chemical
purification technologies prestart-up, operational and "running." Treatment me-
thods developed in AES department laboratories were introduced at ordinary TES's and
were then tr.ansferred successfully to A~S conditions. Research in the water-system -
area which is done directiy on large AES reactors is of great scientific and practi-
cal interest. First, we must note research on the behavior of hydrogen peroxide in
the reactor loop. We proved for the firat time under actual conditions the existence
of hydrogen peroxide in reactor water even at full capacity and revealed the positive
_ role o� hydrogen peroxide in reducing corrosion in steels. fihis work enabled us to
transfer the nuclear power experiment to thermal power generation. Thus, blocks with
doses of different oxidizers, hydrogen peroxide and gaseous oxygen, were researched
under comparable conditions for the first time at the Kostromskaya GRES. In combi-
nation with laboratory experiments in this area, the AES department proved the fa~-
lacy of views held by FRG power engineers to the effect that doses of hydrogen per-
oxide were only a"convenient method of introducing oxygen."
In this water system work, we should also mention theoretical (thermodynamic) re-
search done on the behavic~r of iron hydroxides as a function of condensate tempera-
ture and alkalinity. This research explained the observed preferential sorbtion of
iron on anionite, rather than cationite, which is important in loading condensate -
purification filteY�s efficiently; such filters are a mandatory element both at TES's
with supercritical parameters and at single-loop AES's.
_ In connection with the fact that the reliability and econo:ny of nuclear power plants
; is closely linked to thermophysical processes, hydrodynamics and heat exchange prob-
lems occupy an important place in scientific research at the AES department. At the
same time, these processea are intimatEly associated with physicochemical ones, and
in particular, with those examined above. The department's earliest work in the area
of thermophysics was devoted to researching the hydrodynamics of bubbling two-phase
streams. The data obtained in it on transition region height and its connection with _
calculated phase speeds and bubbler diameter, as well as data on steam phase capture
in down sectors, found a place in the development both of steam generator and boil-
ing-water reactor separation systems and of calculations of the reliability of the
3
~nv n~~TrTAr rTC~ n*nv -
,
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007102/08: CIA-RDP82-00850ROOQ3QOQ5Q036-4
FOR OFFICIAL USE ONLY
circulation in them. This work was subsequently transferred to the field of the hy-
drodynamics of single-phase, abruptly-boiling and two-phase streams under a variety
of conditions as are possible in individual reactor loop elements.
The AES depart~nent is one of the first scientific organizations to have initiated re-
search in this area. Along with concrete data need~d for planning and designing hy-
drodynamic syatems, this work has provided rich scientific methods material, in par- _
ticular concerning methods of y-illuminating two-phase streams.
As is known, a precise knowledge of hydrodynamic conditions when fuel assemblies are
washed over by a heat carrier is very important in reactor engineering. The AES de-
partment has done a great deal of re~earch to determine the true steam content ~ as
applicable to conditions in the acti~e zor.es of boiling-water and water-cooled reac-
tors given surface boiling. Especially important in this research is the dPVelop-
ment of a precise method of determining local value In this area, much work has
been done to improve Y-illumination methods so as to create a special, original neu-
tron illumination method. Extensive experimental data on the dependence of ~ on
the various operating conditions an3 flow parameters have found broad application in
various branches of engineering which use heat-exchange equipment. Heat-exchange
work was initially done in t~e AES department to meet our "own needs." In the 1960's,
there were no experimental data or calculatiun recummendations on determining thermal ~
_ conditions for testing materials in accepted experimental sector designs. We there- i
fore had to conduct a series of original research on heat exch.ange in circular pas-
sages, both for the usual turbulent water flow and for surface and thorough, hard
boiling.
- As a consequence, research was done on the heat-exchange patterns and critical heat
flows in circular passages for which the presence of deposits, including iron oxides,
in the heat-generating pipes was an original feature. The results of this research -
provide an accurate representation of the reliability of heat-f ixing surfaces giv~en
the presence of deposits with various characteristics on them. Data were also ob-
tained on the patterns of deposit formation, their thickness and effective heat con-
ductivity as a function of the thermal, hydrodynamic and physicochemical conditions
in the loop.
Work begun more than 10 years ago to study WER [water-cooled power reactor] AES -
_ emergencies led to the creation of a promising research line, studying the transient
hydrodynamics of a two-phase flow. The applied work of the initial stage included _
research on the following problems:
hydrodynamics of single- and two-phase flows in complex systems if the main cir-
culation pumps are dead;
transient hydrodynamics if the main circulation pipeline is cut off from the
_ first AES loop.
The tasks set early in this work were to create calculation models and, based on
them, programs which would satisfy developers of promising new AES units (WER-440,
VVER-1000). However, experience showed that this task would require a great deal of
experimental work in the area of transient hydrodynamics of a cwo-phase flow, since
there were practically no experimental data, or were clearly inadequate data, on the
following problems:
escape of a two-phase flow through openingr and pipes under transient conditions;
wave procesaes given a meta-stable state of water incompletely heated to satura-
- tion temperature;
4
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02148: CIA-RDP82-44850R000300054436-4
FOR OFFICIAL USE ONLY
the physics of water and steam dissociation if pressure drops.
~ao experimental installations were developed and created to study these phenomena.
The second of them is unique in its potential, since it is equipped with a y-illumi-
nation system which enables us to study the structure of a two-phase flow under dy-
namic conditions.
The experimental data obtained on it have permitted a substantial improvement in the
level of calculation methods and have yielded impartant practical recommendations
for developers of AES safety systems.
Original research has been done on heat-exchange pa*_terns for repeated wetting of
heating surfaces as applicable to water heat-carrier reactor cooling conditions.
This research has been oriented towards obtaining calculation patterns, primarily for
creating reliable, effective water heat-carrier reactor emergency cooling systems.
Moreover, the experimental data obtained are necessary for studying the complex heat
exchange ~nechanism represented by repeated wetting of heating surfaces, for which
- there is very little data at present. It should be noted that stud}.~ing heat ex-
change in emergency cooling has led to the development of a comprehensive approach
to studying the effectiveness of emergency cooling systems, one based on determin:tng
their functional and structural reliability. Such an approach enables us to find ef-
fective ways of optimizing such important AES protection features as the emergency
_ cooling systems for reactors with a water heat-carrier.
COPYRIGHT: Izdatsl'stvo "Energiya", "Teploenergetika", 1980
11052
CSO: 1822
5
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 20Q7/02148: CIA-RDP82-00850R04Q34Q05Q036-4
I
_ FOR OFFICIAL USE ONLY
ELECTRIC POWER
UDC 621.039.58 _
STANDARD VVER-1000 AES SAFETY SYSTEMS
Moscow TEPLO~NERGEiIKA in Rus~ian No 10, Oct 80 pp 5-8 -
[Article by Candidate of Technical Sciences V. P. Tatarnikov, "Teploelektroproyekt"
All-Union State Planning Institute: "Safety Systems for AES's With A Standard VVER-
1000 Reactor"J -
[Text] One of the main types of reactors planned for use in USSR AES's is the VVER
- [water-cooled power reactor]. Available experience in operating power units with ~
this type of reactor testif ies to the fact that all those operating in the USSR or ~
built with USSR assistance abroad are operating stably, that planned indicators are
beix~g sustained. Th e installed capacity use factor has reached 80 percent. As �n
example, one could c ite the AES built with USSR technical assistance in Finland.
The high reliabi.lity of operation of this AES is indicated by the fact that during
the period of its commercial operation, the drop in electric power output due to un-
_ planned equipment down time in the machinery hall has been only about 5,000 mW-hr.
~ In warranty tests, specific heat expenditure was 11,098 kJ/(kW-hr), with a planned
expenditure of 11,94 6 kJ/(kW-hr), and the maximum power (net) was 445.7 MW, as
against a planned power of 420 MW, that is the thermal efficiency of the unit was
7.1 percent above that plan~ed and its (net) power w~s 8.0 percent higher than
planned.
Tests run after 22 months of commercial operation revealed practically no deteriora-
tion in AES thermal effici~ncy. During power unit operation, no thinning of the fuel
elements was observed and the appearance of fi.ssion products in the main circulation
loop was determined to be simply a result of fuel element surface contamination.
The USSR'manufactures equipment and builds AES's with WER reactors with an electric
power output of 440 ~nd 1000 MW.
The 440-MW power units have been installed at the Armenian, Kol'skaya, Novovoronezh-
skaya and Rovenskaya AES's. Such power units have been and are being built in the
- GDR, Hungary, Bulgaria, Poland, Czechoslovakia and Finland. The geographic, clima-
tic, geologic a:~d other conditions in areas where WER-440 AES's are being built dif-
fer substantially, so we had to restrict ourselves to standardizing the basic plan-
ning reaolutions, rather than creating a standard AES plan. At the same time, exper-
- ience shows that ~~::n the use of standard plans which are altered not more than once _
every 7-10 years enables us to bi~ild power units in acceptable periods (5-6 years),
to ensure that they are provided wi.th sets of equipment at the proper time, and to
5
- FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007102/08: CIA-RDP82-00850ROOQ3QOQ5Q036-4
FOR OFFICIAL USE ONLY ~
organize a well-planned construction industry. Given stability of the power system
in the European portion of the country, power units up to 2,000 MW and larger can be
- installed in it. The geographic conditions in the central regions of the European
USSR are similar, which creates good conditions fc~ the extensive ~:onstruction of
standard AES's with WER-1000's.
In 1980, thQ fifth unit at Novovoronezhskaya AES, with tts 1,000-MW WER lead reac-
- tor, began operating. The work done showed that the planned indicators of the power
- unit urill be achieved. Based on power unit development and construction in the USSR,
a plan has been drawn up for a series-produced 1,000-MW power unit.
The main specifications for the standard power unit are as foZlows:
Gross electric power 1,000 MW
_ Overall efficiency 33.3 percent
Annual electric power output 5,960,000 kW-hr
Electric power expenditure to meet own needs 5.2 percent
Steam presaure beyond the generator 6.0 MPa
Steam parameters after industrial heating 1.16 MPa (250�C)
First-loop heat-carrier temperature 322/289�C
First-loop heat-carrier pressure 16 MPa
Coolant expQnditure (fou�r loops) 57,000 t/hr
Pressure in turbine condenser 0.004 MPa -
- Steam generator productivity 1,470 t/hr
Pipeline capacity 1,000 MW
The nuclear fuel is uranium dioxide enriched with 4.4 or 3.3 percent U-235. -
I.ncreasing the unit capacity of power units for WER AES's forces us to be more de-
manding as to their safe operation. AES safety is regulated by norms and rules, the
_ foremost being "General Provisions on Ensuring Nuclear Power Plant Safety During
Planning, Construction and Operation," "Nuclear Safety Regulations," "Temporary
Norms for Planning Nuclear Electric Power Installations for S eismic Regions" and
so on.
The exacting requirements of these norm~ a.id regulations determine the necessity of
planning AES's for such natural occurrenres as earth tremors, hurricanes, floods,
landslides, and so forth, if they are likely to occur at least once every 10,000
yeara. AES's are also designed for conditions associated with human activity. It
is necessary to take into account the coincidence of these effects in planning �or
maximum depressurization of the reactor circulation loop. Consideration is also gi- '
ven to the possible coincidence of four emergencies accident in a system operat-
ing normally, undiscovered and lon~.-standin~ defect in a normally operating system,
failure of the safety system and fa~:~ire of the accident containment system. In
= this regard, multiple failures caused by a single occurrence are viewed as a single
- emergency. For example, fire in the power plant might cause numerous failures.
All possible fires are examined, including one in the power unit control panel which ~
causes it not only to lose all functions, but to issue incorrect commands to the
control system.
In this connection, the power units include a back-up control panel which can stop
the power unit and make it safe.
7
L'fID (1L'L'T/+TAT TTCL' f~~TT V
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02148: CIA-RDP82-44850R000300054436-4
FOR OFFICIAL USE QNLY
In orc.er to prevent false commands from reaching the AES safetyLeferenceliscaivenf to
fire or operator error, wt?en there is an emergency at an AES, p g
commands from the automatic systems. After those commands have been issued, the
safety systems are au tomaticaliy ~aken out of the hands of the operators (or of com-
mands opening or clos ing control circuits in the case o~ fire), or the operators may
be permitted to intervene when the technologieal parameters permit giving such per-
mission. A structural diagram of a saf ety system for an AES with a W~R-1000 is
given in Figure 1.
Figure 1. Structural Diagram of AES Safety Systems
~ 1 ~ Psc,rmnp v ~{upKyn~yaonNait ncmnu
(2) ~3~ 6~
/J~YNtlKU Ncmay~u,r~r IIC/170YNOKU /1C/!)OYNlIK!! HcmovHUKU ~C/IIOVNUA'Q
~O~OCN06AYCHflR ANC/JLOCNQB.IY~N(/1I DOdOCNOQ.IYINtlJ? .lXCpLOCMG6AICNU/1 BDgOCMF6MONtl~I lNSpdOCNQ6AYLh'fIA
G!/C/JICMD/ N~1 CQC/JI~Mb! Ns1 cucmeNSi N=Z C!lCB7CM6/ Np? cucmeNe~ Nsd cucmeNSi Na3
~8~ ~9 1Q
TCXHO/10t!lYCCA'UO TOXMU/lCdl'YOCA'(!C TOXNOADtUYCCA'U6
MCXCM!lJ.~(b/ NCXQA4~JNi/ M6XdAQfJMb/
ClICd7CMb/ lY"1 cucmcNa N~Y OKCJJJOMN Npd
- ~11 ~1 ~1
AB/AONO/J!!/YGCK!/!T ~Op~vUpOBdH!!0 ADR)OMQIII!lVCCK!!!I ~opNrtpaBaHUt ABmoNamaqac,rut7 $OpN!/p00GN!/C .
aanycK .fOMQNd Jd/JSIC~f .fOMGHd JC/l~/CA' A'ONONO
mexNO~azuvecKUx aCmoMOmuvecxoao mexN~~oauvecKUx QamoNamut~ecKaao mexNOnoauvecKUX aBmoN~rmuvec~'aen
NCXOH!lJMOB aanyc,r� MCXGNUJMOD sanyc~'a MCXGH(/JNOB aanqcKa
CflC/l7CM6! N�/ C!!C/I7CM6/ Np7 CflC/I7CMN N~2 cucmeNei NpZ cucmeMai Npd crrcmere~ N+3
1 2 3� 1 Z d
Ilecm ynpaeneHUa Nsl /Incm ynpa q~eHUA Ng2
(17.) cucmener Ngl-d(6!Q_v) ~ 18 ) cucmeNe~ N 1 d(PlL(9J ~
Key:
1. Reactor and circulation loops
2. System 1 water supply
3. System 1 power supply
4. System 2 water supply
5. System 2 power supply
6. System 3 water supply
7. System 3 power supply
_ 8. System 1 technological mechanisms
9. System 2 technological mechanisms
10. System 3 technological mechanisms
11. System 1 t~chnological mechanism automatic start
12. System 1 automatic start command initiated
13. System 2 technological mechanism automatic start
14. System 2 automatic start command initiated
15. System 3 technological mechanism automatic start
16. System 3 automatic start command initiated
17. No 1 control post for systems 1-3 (power unit control panel)
18. No 2 control post for systems 1-3 (reactor control panel)
8
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02108: CIA-RDP82-00850R000300050036-4
~
FOR OFFICIAL USE ONLY
The high demands made on reliability of the AES sa:ety systems have led to the neces-
sity of heavy redundancy of these systens. Thus, the basic systems participating in
emergency cooling of the reactor active zone have a 200-percent reserve, that is,
three systems, each of which can overcome emergency situations. The same app?ies not
" only to the technological portion of these systems, but also to other parts (diesel
units, feed and control panels, cables, and so forth). 'I'he systems are completely
independent of one another, both technologically and physically.
Where these systems cannot be dispersed spatially, the structures separating them
are inten3ed to be f ire-resis:ant for a minimum of 1.5 hours. A safety systems f low
~ine diagram is shown in Figure 2[following page].
In case of an accident involving loss of coolant from the circulation loop, the re-
actor active zone is cooled with water which can be supplied b,y high or low pressure
pumps from reservoirs under nitrogen pressure. When coolant is lost, the high-pres-
- sure pumps are switched on at slow speed. In the case of serious depressurization,
up tc and including comolete, instantaneous failure of the main circulation loop -
pipeline, water is initially fed f rom a reservoir and then the high-pressure pumps
ar.e switched on; if they are inadequate to maintain pressure in the loop, the low-
pressure pumps are switched on. Initial~y, after an accident, the pumps take water `
from tanks, but then they are switched over to areaways and the water begins circulat-
ing in a closed loop: areaway - heat exchanger - Fump - reactor - areaway. Steam
generated when coolant escapes from a loop into the premises is condensed using the
sprinkler systems.
Zn case of an accident involving loss of feed water to the steam generators, three
emergency feed pumps ar2 planned for the AES.
The main AES buildings are also laid out with consideration of safety requirements.
Practically all the systems associated with AES safety except for the diesel units
and coolant water pumping are laid out on a single foundation slab. Utility lines
are laid underground between the reactor building and the diesel and coolant pumping .
tireas. Such an arrangement has advantages over one in which the systems are located
in different buildings. A compact placement of systems simplified servicing and eli-
minates the passibility that personnel not directly connected with safety system ser-
vicing wiil have access to them. Utility line length is reduced to a minimum. Hav-
Inp, a single faundation slab simplifies solving AES seismic stability problems.
Locating safety systems in a building built around the reactor pressurization chanber
enables us to avoid planning that building for aircraft impact, since a minimum of
" one of the three systems will always remain in the "shadow" of the pressurization
- chamber, which is built to withstand aircraft impact.
Construction and operation experience has demonstrated the appropriateness of build-
ing AES's in the form of separate power units with minimum technological links to
one another and with almost no structural links. When this is done, we can change
_ over to construction using a flow-line method (when several identical power units
are located at one AES), ensure a broad worl.t front, and avoid operation of one unit
while another -Is being built. All this speeds up construction and lowers its cost.
The operation of individual units is also simplif ied, inasmuch as it becomes pos-
sible to totally exclude interference associated with the construction of some power
units and the operation of others. In view of what has been said here, we plan to
9
T/~n I~TY~T/'IT1r t~!'~T I~ATT~I
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007102/08: CIA-RDP82-00850ROOQ3QOQ5Q036-4
FOR OFFZCIAL USE ONLY
~ Figure Safety Systems Flow Line Diagram
~ ) e 3Nroee-
Q,~ b cucmt~p r
0
~
~a~r~o~~~,~d,~
Id !d = 13 > 1,~ naM~u~tNUe
- - ~`-i -
_ _ _ - . - - - = 5 S
4 _ _ - - - . p e am.?a- - - ~ ~
r _ - _ ~m~oy (c) O 5
- ~ 12
- . 9 6 ~
- d I
~ S
r~ ~
z ~ ~o
7 8 S -
. _ h I _
Q
a h S
w. , ( -
- ~ ~ S
~ ~
~.8 ~ z~ 2~ z~ I
~ - - - S =
Is? /S /6 !~i 15 16 14 i5 /6 I -
O
- ' !f - - - ' /7 ~ " ~j IB ZB ~ T8 S
~ ~ 19 Ib 1B I
~ ~ ~ ~ ! ~ + I ~ ~ ~ ~ A' aGapuJN~i~ nampy6~'a~ 5
19 20 I9 10 ' I 19 10 ~ I (d~ ~aPaeeMCpamapa~ ~
I L _ Z) L _ ZI I L _ ZT ~
_ I -r~
' I I
j ~ zz ~ ~ ZZ ~ ~ zz
I ~py0-o.?AaOumael ' e~lpyd-orno0umcn~ ~~e~py0-a.~nodum:~ S
- - - I -
- _ _ _ _ _ - v = - = S
~ f~ A'M/l, ~GU{uin0, o0rrainypQ ( f)~'yn, avufvm?, OpNOinypQ ~ f~ A'N/I, ~au~uma, apMamypa I -
~ ~v ~g~NGGOCd/ S
~ (gy/atocn~ 'L . yacoce~
. I
Z~ ~ f ~ ,`24 Z3 ~ ~ ~ ~ 1J ~ ~ ~ ~
_ z6 5 S S z6 S S S . z6 S
TS 15 ?s ~t' nomp~6umcnsr I
r C06GmeCMNb/X N!//Y(~
~i(lGTCM? NS~ ~i~CucmtNQ NQZ ~acmt~a Hod
[I.ey on following pageJ
build VVER-1000 AES's pri.marily in the form of individual powEr units in the forth-
~ coming five-year plan. A line drawing of a WER-1000 AES layout is given in Figure
3 [second page following].
10
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007102/08: CIA-RDP82-00850ROOQ3QOQ5Q036-4
FOR OFFICIAL USE ONLY
Key [to Figure 2, preceding pageJ:
a. Pressurized area
b. To the power system
c. To the atmosphere
- d. To the steam generator emergency branch pipes
e. Cooling pond
f. Control and measuring instruments, shield, reinforcement
Pumps
h. System 1
i. System 2
j. System 3
k. To own-needs customers
, 1. Reactor
2. Steam generator
3. Main circulation pump
_ 4. Volume compensator
5. Turbine
6. Condensator
7. Condensate pump
8. Low--pressure heater group
9. Deaerator
- 10. Feed pump
- 11. High-pressure heater group
12. Generator
_ 13. Water storage tank
14. Hydrazine-hydrate reserve tank
- 15. Emergency boron solution tank
16. Boron concentrate reserve tank
17. Heat exchanger
18. High-presaure pump
19. Sprinkler pump
Z0. Low-pressure pump
21. Coolant water consumers
22. Coolant water pump
23. Power supply busbars of. Category I reliability
24. Diesel generator
25. Power supply busbars of Category ZI reliability
26. Storage battery
27. Desalinated water reserve tank ~
28. E~:ergency feed pump
~
11
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2047102108: CIA-RDP82-0085QRQOQ3QOQ50036-4
FOR OFFICIAI, USE ONLY
- Figure 3. Layout of the Main Structure of a WER-1000 AES
- ~ a 6~~5
, 3
- ~ - ~
yu. Ba - - - - - - ~f
i i i i s .
29, y0
~ ~ 6 Z~ 60
~ 18,00
~iS,00 - /J 00
.
0, 00 � 0,00 ~
S
4,10
~ . . .
~ + F c~
i I - .
I � - ~-r-
'
p .
~ l _ _
R ~ 4
~ ~ . ro
. . ~ . � b
f� i. i
_ S
~ ~ ~
~ z ~ _
� _ _ 1Z0000 _ 1500 66000 ~
Key:
1. Turbine department
2. Reactor building
3. Crane
- 4. Reactor
5. Main circulation pump
6. Auxiliary premises
COPYRIGHT: Izdatel'stvo "Energiya", "Teploenergetika", 1980
11052
CSO: 1822
12
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02148: CIA-RDP82-44850R000300054436-4
FOR OFFICIAL USE ONLY
ELECTRIC POWER
w
UDC 621.311.25:621.039(479.25)
ARMENIAN AES SEISMIC STABILITY
Mosco*.~ TEPLOENFRGETIKA in Russian No 10, Oct 80 pp 21-24
- [Article by Engineers R. S. Galechyan and E. S. Saakov and Candidate of Physico-
mathematical Sciences K. A. Gazarqan (Armenian AES): "Main Fea~ures of Seismic
Stability of the Armenian Nuclear Power Plant"]
[Text] The Armenian AES was the first nuclear power plant built in the USSR in
a region of high seismic activity. Nuclear power plants in seismic zones require
an extremely responsible approach to ensure safety and cannot be planned follow-
ing general construction norms and regulations.
The planning asaignment for the first line was devo,.oped in 1968 b,y the nuclear po-
_ wer engineering department at "Teploelektroproyek`t" Institute based on the plan for
- the third power unit at Novovoronezhskaya AES, wit}~ its series-produced WER-440
units. Lack of experience in building AES's in aeismic regions prevented the plan-
- ning assignment for the Armenian AES from refle~~ting sufficiently fully the techni-
cal resolution on ensuring seismic stability.
The planning organization (the Gor'kiy depzrtment of "Teploelektroproyekt" Institute)
developed "Measures to Ensure Seismic Stability at the Armenian AES Using Series-
Produced WER-440 Units" in 1971 with consideration of the reco~endations of con-
struction, design and scientific research organizations; these measures were used
for guidance in the actual planning.
In order to ensure that operator personnel and the population at large are protected
against radiation, as well as to avoid possible econ~mic loss as a result of tremors,
- all systems and components are subdivided into three categories, with different de-
mands as to maintaining operability: Category I-- systems and components which en-
_ sure AES safety during and after an earthquake, that is, shutting down the reactor
- and keeping it shut down, reactor cooling, localizing any damage (to the reactor,
- control and safety rods, concrete shield, first-loop equipment and pipelines, box
pressurization loop, boron assembly and emergency replenishmen+~ equipment, emergency
replenishment localization syste.m, damage localization system, diesel generator sta-
tion); Category II systems and components ensuring AES operability without signi-
ficant interruption, protection of expensive equipment and radioactivity containment
if the radiation might lead to overexposure of personnel but which does not threaten
the population at large (the special water ~~reatment installation and the first-loop
auxiliary equipment, deaerators, secure feed systems equipment, construction compo-
nents of the main structure, turbine generator foundation); Category III all other
AES systems and components.
13
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2047102/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY
Main Features of the Armenian AES
Based on an analysis of geologic-physical and engineering-seismological research on
~ the AES site and also on data on strong earth tremors previously observed in this re-
gion, the Institute of Geophysics and Engineering Seismology (IGIS) of the Armenian
SSR Academy of Sciences issued parameters and a schedule of earthquake recurrence.
It follows from these data that the Armenian AES would be built or. a site where the
maximum earthquake expected would be 8.0, so the calculated earth tremor used in the
plannin~ was 10.
A cross-section of the main AES structure is given in Figure 1. All building parts
are based on industrial facility seismic-stability construcrion norms with a safety
' factor of four for the reactor department and of two for other installations of the
main structure.
Figure 1. Cross~Secti~n o� the Main Structure of the Armenian AES
3> >
A'pap Q-TSO d0 r
Z~2 ~1~
Z ~pQN[ Q=lIS170 r ~ ~
18,5 ~pQy Q 90 S r IB, S ~8.0
- (1 ~ 16.1
_ 14,7 I4�~ !T 1
17,! J0,5 I1,935 IOJ
9, 6 9 6 9.75 ~ ? B.9
5,4 S.J 7,� Q 5.67 5,67 ~ 6B 0~ S.f
' . 4'S ~ 39 3.B
- � ~ O 7.7 2.7
0,0 0,0 ~B 0,0 01 '0~ 0.0
-7,1 3 ~0 2 2 ~ 29
~ -41 -3,0 -3,.~
-6,5 ' ~
6 B t
-10,8 .
1Cey:
1. Crane(s)
The reactor, the first-loop equipment, the steam generators and the main circulation
pump were designed for seismic events with a safety factor of three.
A series-produced reactor was modernized to increase its seismic stability; the ves-
sel flange has an upper support ring to stabilize it in a concrete shaft against de-
- stabilizing moment; to eliminate stresses on subassemblies connecting the ARK [pro-
bably: nuclear reactor vessel] jacket pipes with the spherical cover connectors,
spacer grates were installed at three heights on the upper block and the ARK jackets
were separated by wedges; the crate was secured at two different heights; the
14
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPR~VED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY
reactor support beam is an embedded eqrthquake-resistant metal structure built ri-
gidly into the reactor shaft.
In order to dampen seismic swaying of equipment in the main circulation structure,
which has no rigid attachment to structural components due to its thermal displace-
ments, 20-, 100- and 170-ton hydraulic shock absorbers (Figure 2[following page])
were used to relieve the stress on the main circulation pipelines, Dy 500 mm. They -
do not prevent thermal expansion but are rigid supports in the event of seismic dis-
turbances.
Research on the dynamic characteristics of this three-dimensioaal system and stresses
in it was done using models on a vibration platform.
Based on these experiments, in order to increase reliability, each steam generator
is separated using eight hydraulic shock absorbers, each main circulation pump by
three and each GZZ [not further identified] by two.
The seismic stability of the common industrial fittings used in Category I systems
was calculated and the ability of the fittings to hold under vibration was deter-
mined on vibration test stands.
Utility lines at the AES site (diesel fuel pipelines, oil lines, acetylene, oxygen
and water pipelines) were made to conform to special specifications for laying pipe-
lines in seismic regions.
Control and measuring devices, automatic control apparatus, electrical devices and
equipment used to control, monitor and feed Category I technological equipment are
also included in Category I.
Using a specially developed program, equipment and apparatus was tested at manufac-
turing plants and on vibration test stands of the IGIS, Armenian AES and All-Union
Scientific Research Institute of Hydraulic Engineering imeni B. Ye. Vedneyev for the
predicted parameters of possible earthquakes (speed, frequency, amplitude).
On the basis of an analysis of this rese~rch, control and safety rod boards and pa-
nels and electrical equipment were separated to increase AES safety; all electrical
equipment and damper assemblies were placed on lower levels, where they would ex-
perience less earthquake effects; emergency shut-down cooling control and monitoring
are concentrated at a separate control board.
In order to ensure a reliable supply of cooling water to Category I consumers, two
earthquate-resistant pipelines were run for industrial water from the pump station
- to the boron subassembly of each blocr and the diesel generator station.
If a seismic disturbance disrupts operation of the feed water stan4ard system, chemi-
cally desalinated water is supplied through pipelines connected to eacli s~team gene-
rator to maintain the water level in the steam generators.
Water is supplied by two additional emergency seismic pumps (ASN) install~ad in earth-
quake-resistent premises and using two earthquake-resistant tanks of resf:rve chemi-
cally desalinated water. In this regard, steam is discharged into the atmosphere
through a contactless relay from the steam generators. After 5-8 hours of operation
15
r.nn /~TL+T/~T AT ttcr. nwrr v
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPR~VED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY -
~ ~ -
~
ir~
\
~
.a
v ,
3 '
~ �
~ o
~ .
O - ~
~ .
C
~ . ~ .
I
cd
~ O � -
M �
- ~
~--I ~ ' h
~i ~
~ ~ i
1.~
H ~ GJ
?
}.i ~ r-I
~ . ~
~ . .
t~A ` O
~ / 1~.~
A
,,e o
u ~ ~
o ~ ~
~ > a
.r ' N a
r-, ' ' 6
~ . ~ i~ U
cd O 6 ~
x . ~ ~n a ~o
y .n ~ ~
" .~e a~i a~i ~ x a
� ~ .c�a~i�
~ ~ ~ ~ ~ ~ .C ~ ~ b0 u
N
t~C R: ri 7 6 Yi 01 'C~ Q i~ Q
MI c0 ~ 41 1~ O'O C ti Cl ~
A ~ 1~~+ ~ cU0 .~L Q 'r'~ ~ ~ ~ ~0 `
~-i 'C7 ~-t a~ m O ~ 'G ~n R ~
rl rl iJ ctl 1-i 7, O'LS O a~
~�i o;xo~c~w~ad~~
a,
~ N c*'f ~T u'1 ~G I~ 00 C+ O�1
pp .-r
~ ~
w x
16
~
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02/48: CIA-RDP82-44850R000300054436-4
FOR OFFICIAL USE ONLY
under these conditions, until the pressure in the steam generators reaches 0.5 MPa,
the steam is fed into two emergency condensers C) cooled by industrial water. From
the Ait's, the condensate is returnEd to the steam generators using two emergency con-
densate pumps (AKN}, that is, the cooling is done in a closed circuit.
An emergency industrial antiseismic protection system (SIAZ) consieting of three sets
of seismometers scattered around the AES site has been installed. The SIAZ system
switches on first-order emergency protection when an earthquake of 6 or more strikes.
Using a remote-controlled armature, it ::uts Category I systems which are not earth-
quake resistant off from ttee first and second loops, cuts nonpriority consumers off
from the own needs system, puts certain systems participating in power plant emergency
operating conditions on stand-by.
Planning the systems and equipment caused serious difficulties due to the complexity
of determining the seismic load and calculation schemes, as well as tc the inadequacy
of experimental data on the behavior of the installation and equipment during earth-
quakes. In order to record accelerations and shifts during seismic events in spe-
cified main-structure building subassemblies and first-loop turbine and equipment
- foundations, a 21st seismometric post was installed as part of the engineering-
seismometry station (ISS) system.
The seismometry laboratory services ISS equipment and the SIAZ system and analyzes
data received from these systems. Moreover, with the help of displacement sensors
installed in the hydraulic shock absorbers and several matn-structure sectors, la-
boratory associatesmake observations of displacements in them during loop warm-up
and cool-down.
Armenian AES Operating Experience. Scientific and Technical Problems.
The Armenian AES first power unit was star*_ed up in three stages.
During the first stage, in an emergency shut-down with loss of the primary sources
of electric power, residual heat releases were eliminated by switching over to na-
tural water circulation in the first loop, and the permissible power did not exceed
35 percent of nominal. The power unit was oPerated at this capacity for 44.5 effec-
tive days. Considerable time was required for second-stage operation, so opportuni-
ties for increasing power unit capacity were sought out. Calculations showed that
for operation at 46.5 percent of capacity at reduced first-loop parameters and
sliding second-loop parameters, reactor operating safety was not below nominal pa-
rameters and 35 percent of capacity. The power unit was operated for 48 effective
days under these conditions.
During the second stage, in an emergency shut-down with loss of the primary sources
of electric power for AES use, residual heat releases were eliminated during the
first 60 seconds using four (two, for worst--case) GTsN-310 main circulation pumps
fed from diesel generators operating continuously, with subsequent transfer to na-
tural circulation. Permissible capacity was 90 percent; these operating conditions
were mastered on 13 May 1978.
Uuring the third and concluding stage, residual heat releases were eliminated by
running out a GTsN-317 inertial main circulating pump, which experiments showed took
- more than three minutes. These operating conditions were mastered on 6 October 1979.
17
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02/48: CIA-RDP82-44850R000300054436-4
FOR OFFICIr~L USE ONLY
~ The results of tests of the new earthquake-resistant equipment, experiments conducted
during the course of mastering 100 percent of capacity and experience in operating
at nominal capacity pernitted the conclusion that the planning resolutions selected
~ere correct and that the equipment operated reliably. All decisions made on in-
cre8sing the seismic stability of equipment for the first power unit were implemented
in the second unit, which was switched ~nto the network on 29 December 1979 and run
at nominat capacity on 31 May 1980.
While the first power unit was operating (December 1976) ~here were seven earthquakes
of 3-S points at the Armenian AES site. Some of these earthquakes (7 March 1978, 5
points at the epicenter and 4 points in the Armenian AES region; 26 May 1978, 7 and
4 points, respectively; 15 August 1978, 5 and 3 points) were recorded by the Armenian
AES engineering-seismometry station and the response of the buildings and equipment
was also recorded. The earthquakes had no effect whatsoever on equipment operation.
In view of the positive experience already available in predicting the place, force
and time of earthquakes, it seems appropriate ta create an experimental-methods
testing ground in the region in which the Armenian AES is situated. Clearly an ac-
curate earthquake prediction will enable.us to take prompt steps to increase AES op-
erating reliability.
Several technical problems requiring solution were revealed during operation of tlie
AES's first and second power units. Several of them have already been solved, and
others require detailed study and development, with the involvement of various or-
ganizations. The latter include:
1. Possible substitution of a water cooling system for the GTsN-317 oil cooling
system;
2. Improving the seal water supply.
According to the plan diagram, seal water for the GTsN-317 is supplied by piston-type
Tr 6/160 pumps. They have a limited operating life and high pressure pulsation (1
MPa), which leads to vibration of the pipelines and equipment. They should be re-
" placed by low-feed centrifuge pumps in continuous operation.
3. Improving hydraulic shock absorber operation. The gasket rings on hydraulic
shock absorbers located in the box are made of a special type of rubber; they mal-
function, harden, and hydraulic fluid leaks appear. Connecting pipe welds are very
weak and the connection system is complicated.
_ ExperiencP in operating the Armenian AES testifies to the fact that the available
systems ensure AES operating safety under seismic conditions.
COPYRIGHT: Izdatel'stvo "Energiya", "Teploenergetika", 1980
11052
CSO: 1822
18
;
,
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPR~VED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY
FUELS
UDC 5~2.578.2.+552.578.1(575.4)
PETROLEUM-BEARING PROSPECTS OF SOUTH CASPIAN BASIN
Moscow IZVESTIYA AKADEMJI NAUK SSSR: SERIYA GEOLOGICHESKAYA in Russian
No 8, Aug 80 pp 133 -141
[Article by M. M. Grachevskiy, Ye. V. Kucheruk, I. A. Skvortsov, and A. K.
Zyubko: "The Reef Slope of the South Caspian Basin and Its Petroleum and
Gas Prospects (Southwestern Turlanenistan)"]
_ [Text] Many petroleum and gas deposits identified both in the USSR and
abroad are associated with buried reefs. A significant share of world
reserves of carbohydrates enclosed in reefs are in the barrier reefs, which
in most cases form independent zones of petroleum and gas accumulation
(Grachevskiy et al., 1977). There is no doubt that many petroleum and gas
deposits which will be found in the near future are associated with barrier
reefs, which are widespread in numerous known and promising petroleum-gas
regions of the USSR. Reef formations are also an important reserve for
increasing petroleum and gas extraction and enlarging the reserves of these
minerals in both n ew and oId petroleum-gas regions. Prospecting for buried
barrier reefs is very timely in our country. Scientif ically substantiated -
prediction of barr ier reef zones can often be accomplished by comparative
analysis of f eatures of the geological structure and history of develop-
ment of petroleum-gas basins (Grachevskiy, 1961, 1974). The discovery of
buried barrier reef s makes it possible to reorient prospecting and explora-
tion for petroleum and gas and in most cases sharply increases their ef-
fectiveness.
The assumption that there is a Neocomian barrier reef slope scarp in South-
western Turlaaenistan was f irst made on the basis of results of reinterpre- ~
tation of data from regional KMPV (correlation refracted wave technique)
work and a comparative paleogeomorphological analysis of three basins with
similar structure: the South Caspian, the Gulf of Mexico, and the Caspian _
(Grachevskiy, Kucheruk, 1978). Additional analysis of geological-
geophysical findings done by the authors of the present article confirms
this assumption and indicates a coincidence in plan of a barrier reef scarp
of Neocomian age with the Pribalk3~anskaya petroleum-gas zone and with the
zone of the so-called Shordzh-Gekchinskiy fault (see Figure 1) It is over-
lain by an argillaceous diapiric ridge and in the Pribalkizanskaya uplift
zone controls the processes of diapirism, structure formation, and petroleum-
- gas accumulation. The faults here are also caused by the argillaceous
19
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPR~VED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIA'L USE ONLY
asAQvodsk . . . � . .
~ . ~ . ~ . � � . .
t ~ . - , ~
~ ~ a .'4 - ~1a3t~ - ~
, . a . .
, . . , 7. '8 - ~ .
. e
- . ~ ' ~ ~ - ~o
Caspian
S~a ~ , ~
S~ol.s. - ~ , ~z - � ; ' : . .
~r=~~~ ~ is . ~,,r^'~'
_ ; ~ ` . . : . � ~ . ~,.r . - i
~ . ` .~.1 ~ ~ ~ ,
0' ' . " - . . . - , y' '
~ : y ~ ~a' j ~ -
~ l . U � ~
. � . � ~X,~.'l'~ . 16. . . .
Figure 1. Map of the Distribution of the Potential
Petroleum-Gas Bearing Barrier Reef in Southwestern
Turlanenistan .
Key to Symbols: (1) ~Jeocomian Barrier Reef (Arrow Point Indicates Its
Steep Basin Slope);
. (2) Basin Slope of Upper Jurassic Barrier Reef;
(3) Local Uplifts in Zone of Neocomian Barrier Reef [See key to
locations below];
(4) Assumed Combined Traps in Barrier Reef;
(5) Gas Deposits in Carbonate Neocomian;
(6) Mi.ning Structures;
(7) Location of Seismogeological Cross-Section of Barrier Reefs in
Monzhukly Region (See Figure 2b below);
(8) Recommended Parametric Wells.
Key Co Locations Along Reef Line:
- (1) Cheleken; (9) Danata;
(2) Kotur-Tepe; (10) Western Zirik;
(3) Barsa-Gel'mes; (11) Western Ala-Dag;
(4) Burun - Nebit-Dag; (12) Northern Rustam-Kala;
(5) Monzhukly, Urundzhuk; (13) Southern Rustam-Kala;
(6) 'Kum-Dag; (14) Gechka;
- (7) Kobek; (15) Togolok;
(8) Syrtlany; (16) Ki.zyl'Tepkh.
20 -
- FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPR~VED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4
I
FOR OFFICIAL US~ ONLY
diapirs above the reef and disappear beneath the red bed stratum. Finds of
organogenic cavernous 1 imestones with fauna of Mesozoic age (Tithonian - -
Barremian) containing selvages of petroleum, and Domanik-type depression
facies in the breccia of the mud volcano Aligul in Cheleken permit the assump-
tion that the source of petroleum in the Pliocene beds of the Pribalkhanskaya
producing zone are formations of Mesozoic depression facies and that the prin-
' cipal reserves are contained in the Neocomian barrier reef. In a similar way,
at the Mexican Samaria deposit petroleum was first taken only from terrigenous
Miocene formations, whereas the principal reserves proved to be associated -
with the underlying car bonate barri~er reef complex of the Reforma trend (1.4
billion tons) lying at a depth of 4,000 meters and also having a Lower
Cretaceous age. The d iscovery of this highly productive barrier reef trend
has enabled Mexico not only to full.y satisfy its own domestic petroleum
needs but also to begin exporting to other countries. As a result of bringing ~
the reef deposits of t he Reforma trend inta production, petroleum extraction
- in the country has incr eased 300 percent in the last five years. According
to estimates by experts, in 1988 Mexico will export as much petroleum as
Iran exports today. Predicted petroleum reserves are steadily increasing in _
. that country. At the b eginning of 1977 they were equal to the reserves of
the northern slope of Alaska; by the beginning of 1978 they had reached the
magnitude of the reserves of Kuwait, and by September 1978 were being com-
pared with the reserves of Saudi Arabia (Metz, 1978).
The paleogeomorphologi~ alsimilarity of the South Caspian petroleum-gas basin
_ and the Gulf of Mexico basin lies in the fact that both basins are framed by
carbonate formations of a lagoon-type paleoshelf bounded on the basin side by
barrier reef scarps. These scarps have been studied thoroughly in the Gulf
of Mexico basin, where their maximum height is about 5,000 meters (J3 KlPl~� ~
On the southern flank of the Bol'shoy Balkhan the thickness of the carbonate
Neocomian alone is 450-500 meters and together with the primarily carbonate
_ Upper Jurassic it approaches 1,200 meters. The Danata well (800 meters) has
_ penetrated the carbonat e shelf Malm-Neocomian in the foothills of the Western
Kopetdag. According to the findings of P. I. Kalugin, the thickness of the
reefogenic Goterivian is 400 meters. In the deep Kizyl-Tepekh-2 well drilled
on the Gorgan coastal p lane in Northern Iran, hydrocarbon gas has been ob- -
tained from the Neocomian carbonate stratum that is a component of the Tehran
suite. This stratum is composed of porous oolitic limestones (185 meters
thick) and evidently, j udging from the fact that it contains the deep-water
fauna hannoconus, is a facies of the foot of the reef. The thick layer of
- Valangian-Goterivian 1,500 meters) underlying it, unlike formations of the
same age expressed by continental beds that have developed in regions further
east, is also a deep-water formation, to ~udge by the presence of Tintinnadae
fauna in it (Jaafari, Chadimi, 1972). This is evidence of the existence of
a deep-sea regime in t he South Caspian Basin during the Mesozoic. The geo-
morphological expression of the South Caspian Basin in Barremian is con-
firmed by the fact that the Urgonian rudistid coral reef facies is confined
entirely to its periphery (Bol'shoy and Malyy Balkhan) and the absence of
this facies over the vast area of the anhydrite-carbonate lagoon-type paleo -
shelf within the southern slopes of the Turanian platform plate, where only
Bryazoan biostromes ar e known, as for example at the Modar deposit
(Bliskavka et al., 1969).
- 21
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02/48: CIA-RDP82-00850R000300054436-4
rvn vr r i~ieu. u~c: vivL1
The paleogeomorphological comparison of the Reforma petroleum-gas zone in _
Mexico and the Priba?.khanskaya zone of Southwestern Turkmenistar. shown in -
Figure 2 below confirms that they are similar in significant ways. 'Itao
zones of barrier reefs and two corresponding zones of lagoons can be traced,
deep outer zones and shallow inner zones with anhydrites and gypsums. The _
nuter reefs are correspondin~ly 3ouble-sloped while the inner reefs are vir-
tually single-sloped. There is a one-to-one ratio between the vertical and
horizontal scales on the profiles. The Cretaceous reefs of the Pribalkhanskaya
scarp of Southwestern Turl~enistan are not completely synchronous; the inner _
barr ier formed somewhat later than the outer and is shifted transgressively
in relation to the Upper Jurassic barrier that controls its location. The
outer Neocomian barrier is controlled by the ],ip of a terrigenous argilla-
cenu s terrace and develoged initially as a single-sloped barrier somewhat
further east, in the Kobek region; with the disappearance of this wedge-
shaped terrace these barriers are converging and becoming transgressively
situated (see Figure 1 above). Under the conditions of Sitio Grande and
Sabancuy the Lower Cretaceous inner barrier, judging by the profile, is also
controlled by a wedge-shaped Jurassic terrace, evidently of reef origin.
Judg ing by the latest publication on the deposits of Agave, Oxicaca, Artes,
Sunap, and Copano, this inner barrier reef is Upper Jurassic-Lower Cretaceous
in age and iCs productive part reaches a thiclcness of up to 1,500 meters
(Dias Serrano, 1978) . '
The assumptions of Mexican geologists that the outer and inner reef barriers
spread completely around the Yucatan Peninsula and that it is a mega-atoll
have not been rigorously proven, even though such a double Lower Cretaceous -
barrier has been outlined for the Belize region (hava Garcia, 1978).
Under these conditions, as in Southwestern Turlanenistan as wpll, there may
possibly be both regressive displacement and also overlapping or even trans-
gressive displacement on the plane of different-aged reefs, in particular the _
Cretaceous and Upper Jurassic (under the conditions of the Yucatan Peninsula
the Lower Cretaceous and Paleocene). The Paleocene age of the producing
horizflns of the Chac and other off shore deposits has recently been denied,
without solid grounds, by various Mexican investigators even though the dis-
tribution of the Paleocene carbonate facies in Yucatan and adjacent r?gions "
was demonstrated in earlier works (Judoley;, Furrezola-Bermudes, 1971). At
the same time, the existence of an independent petroleum bearing Paleocene
barrier reef zone here is entirely natural a:~d was essentially predicted by
us before it o;as discovered (Grachevskiy et al., 1977). The presence of
- Paleocene reefs is also possible in the slope zone of the South Caspian
Basin. _
In the inner parts of the South Caspian and Mexican basins the thickness of
the sedimentary mantle increases to 20 kilometers and the granite crust thins ~
out substantially or even disappears completely with the development of a
mantle diapir. Corresponding to the ocean type of crust here is the ocean
type of paleobasin with bathya? petroleum-source formations of the Domanik
(euxinic) type in the phase of lack of compensation for the depression cycle
of sedimentation. Such formations are reliably known from drilling data in _
the Mexican and Caspian and, judging by presence in the breccia of the mud
volcano Aligul, may with full substantiation be assumed in the Malm-Neocomian
22
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02/48: CIA-RDP82-00850R000300054436-4
FOR OFFICIAL USE ONL~
a~ i
o
~a~~
~ ,v ~ ~ Ma ~e� � � . . ' . . O ~ ~ ~ ~ .
~
. ~ � ' ' �O , ~ : , ~ ' u wv G
o N~ a `o c~ o
i�~ ~ ..~V , 1 1 , � ~ ~ a . ~ . ~
. .Q . ~a ' . ~ I 1 N~.~ w ..ww
_ ~ v~ , � w N 1-+ Cl Gl Cl Cl
a~ V~ b , I C 'I ~O. y.a F~+ cd ~ N ~ R~ ~
,yF ~e d ic.. ;
~ b V ' . . ' ' � ~I . ~ ( ~ ~ c~d w ~ N ,~~1 r~i
u ~Z~ ~ ' I ~ N ~ ~ N GNl cN0 ~ ~
~ ~ , . . .C O tA pf, ~r~l CS cd R1
O ~ ~ , ~ � `I ~J N CJ U i P~i fA
t/~ E Q ' . ' , Cl ia F+
a4 ~ � . , 4a cC O N 4~-~ ~ 4+ H
~ C~ O . ' O a.1 r-I ~r1 ~ N~+ G~+l
' ~ C l ~:r L+ H I G'+ C+
v p~~ i~~ ~ , 1 ~ t` , ~ U~ C
A H J H H
~
e i Ho..~ � cd a~i o u ~v w o o �
C ~ t ' � � . " ~ d ~�a oo vi ~ N aki a) ~
LC Q ~ � . ' ' .1 . .C ~ cU 4a Gl r-I ~ G)
i1 ' ' � ~ . ~ ^ W ~ 3~-I ti H ~ .C O O ~
i~ , O{~ O 00 tn U U tA
o u s~ w p
1
v N ~v. ~ :,1 aNi ~ d a � "g~ ~
~ C ` . � . I~ , o CU1 ~ ~ p G 'L1 w
v~~
N tn ~
. . . ~ � � I I�` I O 'Ly H FI ~ ^
' � ~ ~ O O iy ~ q ct1 ~~rl U
p ~ ` , O . tn V O 1-1 ~ .L' .n
� nO I I GJ O~ N q H 0~0 ~
~ & 0 � ' . ~ � ~ . ~ I a~i ri ~ cud ~ a ,'S,' C
T ~ qw ~ i . . 4-i cd N~ 'L7 N~ r~l C+ ~
I �"da~~ ai ~';~�o�o
N - ~ ~i � ~ ' q a1 H a1 00 00
' V ~ ~ , o ~ a~ ~ 00 �~I I c0 R1
. ~ . - . ' � ~t � m d q a .~G u ~l ~7
C0a ~ � � ' ' . 0 3 c~�~~
~ N~r-~7 ~ A ~M a~i a~i
. ~ b ' , . � ' C . , ~ . ~ a~i ~ w u v p iC a.+ ~ -
. ~ ~ ~ `�:T
~ ~ , ' ~ ~1 i`~ ~ � U R1 GI ~ i-. ~ i~.l A ~ ~ H
~ y , Pa ~ C ~ cC -
. r-I O O c0 ~ i~+ ~ r.
, . ~C cd 'b N �ri ~..i � ~ !C u'1 c6 C1 Gl
rl ~C . U G) 1J N fA d!~ v v~ ~
~ ~ r-1 ~1 ~ ~ 1' �rl v~l cE U�rl d e-1
H a~ � oo w~ a~ u a.
~ r� ~ o i~ w o~,-~~ in
, ~ ~ . . . . ' ~ o'~ uNi~ ~ v ~3~
t'~ . LL ~ w' O~ cn w cn v
~pt q.~ - \ o~~v~ �'fld a~i o 00
~ �1 ` '
~E ~ � ~~Ct'r~ a�~ u ~'~ca a~'i ~ N ~ ~ ~
~ ' ` � ova~c"n v~~o~
~ ~ � ~ . ' ~ . r-~i A ~ 3 w "ioo ~ o
- ~ ~ ' ~ o ~ , ~ a M v~ o a ~ ~ ~ o"a
~ . ~ a~ao -
c~i � m co c' ~n
N c0 f-~ I~ '-1 N c~1 ~1' ~D
- Lj ' U C,9 .-1 ~vvvv
. Q O O p; p Gl cE A
, p f~+ O U O
v
~ a b o~.o a~i d
' w ~ ~ ~ a ~
23
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2047102108: CIA-RDP82-00850R000300050036-4
FGR OFFICIAL US~' ONLY
coraplex of the South Caspian basin and, in part, in the Upper Cretaceous
and Paleocene-Eocene. According to the findings of I. Shteklin (1979), the
South Caspian basin is a relict of the Paleozoic Tethya or at least of the
pre-Lower Jurassic Tethys, judging by data from the Kizyl-Tepekh-2 well,
which revealed Lower Jurassic beds in the assumed zone of distribution of
oceanic crust .
The leveling o~it of the South Caspian ba.sin was accomplished on the eastern
slope by the argiliaceous diapir-forming strata of the Aptian-Cenomanian
while in the inner part of the basin it was done by a Paleogene-Miocene-
Pontian stratum; today they form the outer and inner diapir zones respec-
tively. The productive red bed stratum and the overlying Ak,chagyl-
Apsheronian form a complex of compensatior synclines with a total thickness
of up to 10 kilometers. Locally these synclines force the argillaceuiis
beda of the underlying complex out of the cross-section before the reef into
adjacent 3iap irs two kilometers high.
The Pribalkhanskiy scarp is traced by KMPV seismic exploration data in the
beds underlying the red beds along a high-speed horizon (5,000-5,600 meters
a second) that corresponds to the surface of the carbonate Neocomian. This
scarp is bounded on the south by the so-called Kel'k.orskiy trough. gently
sloping monocline that together with the south-tilting sCarp forms the
Pribalkhanskaya scarp corresponds to this trough on this seismic horizon.
In a similar way, the submeridional Shor3zha-Gekchinskiy high-amplitude
scarp forms the boundary on the South Caspian basin side for the Aladag-
Messerianskaya scarp, which is composed of a Malm-Neocomian carbonace com-
plex and an Aptian-Cenomanian terrigenous complex.
The wedge-shaped f~rmation of layera in a subparallel system can be clearly
traced ir~ the Mesozoic beds of the ICI~V regional profiles done by Yu. N.
Godin, which are transverse to the scarps and crosa Nebit-Dag and Gechka.
According to a reinterpretation don e with an OGT (common depth point tech-
nique) profile and KMPV , the subhorizontal occurrence of the layers in the
space of both scarps can be traced some~ahere at the level of the foot of the
Neocomian, at a depth of about 6-8 kilometers. In Yu. N. Godin's regional
geological-gecphysical profile through Erdekli - Nebit-Dag the foot of the
Mesozoic (in fact the foot of the Neocomian), which is subhorizontally bedded,
even has a slight dip to the north in the scarp zone, toward the Bol'shoy
Balkhan, unlike the boundary of the Mesozoic and Cenozoic (Beskrovnyy et al. ,
1963). This is incompatible with traditional noti~~ns of the deep faulted
nature of the scarp. The diapiric character of thF: ridges and faults that
control the p etroleum an~ gas presence of the reu bed stratum is confirmed
by the great er thickness of the argillaceous strata and by the development
of AVE~D (anomalnusly high layer pressures) and mud volcanism associated with
weakly mineralized hydrocarbonate-sodic waters that are forced out of the
argillaceous minerals and introduced into overlying strata. But no well
there has disclosed the full thickness of the argillaceous beds beneath the
red beds, wliich exceed 1,200-1,500 meters. On the Pribalkhanskaya scarp be-
yond the lim ita of the marginal dia~ iric rid.ge the argillaceous atratum under
the red beds petars out almost entirely.
- 24
4~0~t `4FF~I~I~A~. U$E 4~NL~'
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4
~OR OPFICZAL USE ONLY
_ The carbonate composition of the lower half of the seismic wedge identified
here on OGT profiles is indicated by the linear poaitivs gravimetric anomaly
(gravimetric scarp) confined to it, despite the development of the diapiric _
ridge here. Nonethelesa, all the diapirs of the Gogran'dag-Okaremskiy
_ region which have developed in the fore-reef (depression) zone of the South
Caspian basin where the thickness of the beds synchronous to the barrier reef
is sharply reduced are distinguished by negative gravimetric anomalies and
- lowered thermal anomalies. Unlike the red bed stratum and the agrillaceous
strata beneath the red beds the Neocomian carbonate complex has higher
density and heat conductivity tGrachevskiy et al, 1979). On Yu. N. Godin`s
geological-geophysical profile through Erdekali-Nebit-Dag the Meaozoic beds
with a density of 2.65 grams per cubic centimeter in the region of the
Pribalkhanskaya scarp occurring at a depth of about 3.5 kilometers with a
- thickness of several thousand kilometers (2,000-3,000 kilometers) are
- abruptly wedged out to the south by a lowering of the roof. A density of 2.65
grams per cubic centimeter corresponds to carbonate rocks. A density of 2.4
grams per cubic centimeter is accepted for the overlying Cenozoic terrigenous
strata. The fact that the dip angle of the roof of the wedge-shaped carbon-
ate complex in the scarp zone is 30 degrees, which is greater than the criti-
cal angle of reef formation (six degrees) indicates that the scarp has a
reef origin, in the particular case a barrier reef (Grachevskiy, 1976).
It is important to observe that the curve of local ~g in the same prof ile
by Yu. N. Godin shows a gravitational maximum not only on the Pribalkhanskaya
scarp (Vyshka), but also to the north, in the region of the Malm reef scarp. -
Bcth maximums, which are caused by the anomalous densitiea of the barrier
reef complexes within the sedimentary stratum, the southern Neocomian and
northern Neocomi.an-Upper Juraesic, complicate the major asymmetric regional
minimum of the force of gravity in Bouguer reduction which corresponds to
the Predbalkhanskiy trough in the structure of the crystalline foundation
formed at the point of subduction of ocean crust underneath continental
crust (Benioff zone). The latter is conf irmed, in the first place, by the
abruptly asymmetr ic character of the minimum of the curve of ~g with the
location of the maximum conjugate with the Predbalkhanskiy minimum in the
Bol'shcy Balkhan region and a gravity scarp directly south of this maximum;
in the second place, by the existence of a f~cal earthquake surface at the
level of the roof of the basalt layer that dips under the Bol'shoy Balkhan
(Andreyev, 1953); in the third place, by outcrops of ultrabasic rock in
the zone of the deep Krasnovodsk-Balkhan fault (Kuba-Dag), which is associ-
ated with the centers of deep-~ocus earthquakes (100 kilometers).1
Very weak "shallow-focus" earthquakes with focus depths of about 10 kilom-
eters are associated with the Pribalkhanskaya scarp are not caused by deep
faulte (Beskrovnyy et al, 1963), but rather by isostatic extrusion of the
argillaceous strata below the red beds from the fore-reef zone of petroleur
1
Considering t he position of the focal surface of earthquakes, it is perhaps
more correct to speak of gravitaCional slippage of the granite layer from the
mantle diapir into the seam zone of the Bol'shoy Balkhan as the interior con-
tinental "micro-ocean" opens up in place of the split meridian mass. The
rifting of the granit~ slabs in the South Caspian basis is broader and, pos-
sibly earlier than in the Kura basin. -
25
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2047102/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY
an~ gas formation into the diapiric ridges, above all into the productive
ridge above the barrier (Banka LAM-Cheleken - Kumdag) and their replacement
in the cross-section by terrigenous red bed and sub-red strata that comprise
the, compensation syncline complex. In an analogous manner the lateral barrier
re~f scarp of the Caspian basin formed above the diapiric salt ridge when
Kungur salt was forced out of the fore-reef zone by the weight of the Permian-
Triassic red bed complex that had accumulated therE (in the compensation
syncline). In the Antonio Bermudes g.roup of deposits in Mexico (the Reforma
Mesozoic barrier reef trend), the presence of anomalously high layer pres-
sures appears also associated with the formation of a diapiric ridge 1,000
meters thick in the Eocen e argillaceous beds above the barrier at the same
time as layer pressure below, in the reefogenic limestones at a depth of
4,000 meters, corresponds to hydrostatic pressure (Mayerkhoff, 1978). Such
a distribution of layer pressures appears to indicate that a diapiric wedge
separates the la[eral migraticanal stream of petroleum-gas bearing fluid from
the continental depression facies of the nearby fore-reef zone into two
streams: above and below the diapir. The diapiric wedge itself is the cause
- of the anomolously high layer pressures, while its argillaceous variation is
also the source of fresh hydrocarbonate-sodic thermal waters and mud
volcanism, whose roots are found (in the ca~~~ of Southwestern Turkme~ istan)
in the fore-reef depression and pediment zone of the Neocomian barrier reef
- at a depth of 6-8 kilometers under the theimal screen of the compensation
synclines under conditions of geostatic pressure. The latter, with an aver-
age density of 2.4 grams per cubic centimeter for overlying rocks, should
reach 1,500-2,000 atmospheres in this case.
With this model of petroleum-gas accumulation mud volcanism does not create,
but rather destroys deposits that were formed with nearby lateral migra-
tion from the fore-reef generation zone. This mod~l can containscnotdonly
with the fact that the breccia of the mud volcano Aligul
its own reef cavernous limestones but also the black siliceous-bituminous
beds of depression facies which we discovered there in 1978. They are the
st=atigraphic analogs of the Neocomian reef complex. The faults, which are
traced around the axial part of the structural Pribalkhanskaya zone in the
form of a graben, represent a system of axial grabens thst complicate the
diapiric ridge and, naturally, taper out in the argillaceous beds below the
red beds. Incidentally, similar grabens above diapirs are familiar from
the salt domes of Emba (Dossor, Makat, and others).
The local structures of the Pribalkahanskays diapiric ridge represent a
combination of it and transf er submeridional structures, which is empha-
sized by the paired local gravimetric maximums located south of the chain
of local structures (Monzhukly, Nebit-Dag, and others) within the compensa-
tion syncline and reflecting the position of submeridional structural
protuberances. The combined character of the Monzhukly structure, which is
intersected by a structural meridional protuberance, is also confirmed by
the existence of the North Monzln�kly structure and the transverse Bol'shoy
Balkhan uplift with an amplitude of o^~ meters in the region of the city
of Nebit-Dag. Combined traps have been identif ied in the Neocomian barrier
reef at the following sites: Banka, LAM, Cheleken, Kotur-Tepe, Barsa-
Gel'mes, Nebit-Dag, Monzhukly, ICum-Dag, Syrtlanli, Western Zirik, Kobek,
Western Alad~g, Northern and Southern Rustam-Kala, Gechka, and Togolok.
26
F0~ OF~'~'~IA~ ~lS~ ONL~f
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4
FOR OFFICIAL USE ONLY
The depth of the reef crest is 3,000-4,500 meters. Ir. the aubmeridional sec-
_ tor of the barrier reef trend the combined traps are formed where the trend
is crossed by the sublatitudinal anticlinal zones of spurs of the Southwestern
Kopetdag and coincide with structures mapped at the foot of the red bed
stratum and located along the Shordzha-Gekchinskiy scarp. The traps are also
of the combined type within the entire Neocomian barrier reef. The depth of
the Neocomian reef crest at the Monzhukly sitE is about 3,000 meters with a
width of about five kilometers, while the height of the reef scarp is 1,500
metera and the height of the reverse slope is about 300 meters. The length
of the Monzhukly structure is 12 kilometers. The existence of a high- _
amplitude barrier reef scarp at the Monzhukly site is additionally confirmed
by the coincidence here between the gravimetric maximum and the electrical
ma~cimum (based on data from vertical electrical sounding) in the cross-
section at 3,600 meters. The maximum has a resistance up to 90 ohms and
is extended linearly along the strike of the structure maps according to a
provisional seismic horizon near the roof of the red bed stratum. Such
, high electrical resistances and the thermal anomaly appear to reflect not
just the carbonate composition and reef character of the collector, bur also
that it is saturated with petroleum. The Neocomian barrier reef here, as is
true along the entire Pribalkhanskaya scarp, occurs on the lip of an
argillaceous regressive terrace presumed to be of Valangian age that grew
ontu the shelf from the Malm barrier reef scarp to the south during the prin-
cipal phase of folding in the Bol'shoy Balkhan at the dividing point of the
Jurassic and Cretaceous (see Figure 2 above).
The paleogeomorphological situation in the South Caspian petroleum-gas basin
permits the hypothesis that the slope barrier reef ensemble can be found
under the water of the sea and in the Kuza basin as well as in Southwestern
- Turlanenistan. It would appear that the Eocene slope reef established from
seismic exploration data in the region of the Muradkhanly deposit in
Azarbai~an is related to this reef formation around the basin (Gadzhiyev,
Kul'chavin, 1977). The analogy we have drawn between this vast petroleum-
gas basin and tfie basin of the Gulf nf Mexico offers a new picture of its
development and petroleum-gas promise, replacing the idea of the South
_ Caspian median mass by the development of a mantle diapir and oceanic basin
here in the Mesozaic. In the Turkmen part of the South Caspian basin the
principal prospects for petroleum and gas are associated with its Neocomian
barrier reef slope scarp. In an analogous paleogeomorphological situation
a Mesozoic petroleum and gas bearing barrier reef scarp is predicted along
the outer margin af the northwestern shelf of the Black Sea.
BIBLIOGRAPHY
1. Andreyev, S. V., "Deep Structure and Seismicity of Southwestern Turkmeni-
stan," AVTOREF. KAND. DIS. AN SSSR, 1953.
2. Beskrovnyy, N. S., Gemp, S. D., and Shvarts, T. V., "Deep Faults of
Western Turkmenistan and Their Role in the Formation of Petroleum Pools,"
TR. VNIGRI., Vyp 210, Leningrad, 1963.
3. Bliskavka, L. T., and Ruban, V. N., "Signs of the Existence of Reef
Massifs on the Southern Slope of the Turkmen Platform Plate," GEOL.
NEFTI I GAZA, No 8, 19b9.
27
L'(1D I1L~t+Tr'T AT TTCF l~~TT V ~
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02/48: CIA-RDP82-44850R000300054436-4
FOR OFFICIAL USE ONLY
;
~
4. Tadzhiyev, A. N., and Kul'chavin, L. D., "Reefogenic Formations in _
the Kura Basin Based onSeismic Exploration Studies," NEFTEGAZ. GEOL.
I GEOFIZ., No 6, 1977.
S. Grachevakiy, M. M., "Possible Reefs of Permian Age in the Slope Part
of the Northern Caspian Region, News of Petroleum Engineering," GEOLOGIYA
No 11, 1961.
6. Grachevskiy, M. M., "Paleogeomorfologicheskiye Predposylki
Rasprostraneniya Nefti i Gaza" [Paleogeomorphological Prerequisites of
Petroleum and Gas Distribution], Nedra, Moscow, 1974.
7. Grachevskiy, M. M., "Buried Barrier Reefs and Prospecting for Petroleum
and Gas Deposits Within Them," TR. VNIGNI, Vyp 194, Moscow, 1976.
8. Grachevskiy, M. M., Kucheruk, Ye. V., and Skvortsov, I. A., "Petroleum
and Gas Content of Reef Complexes and Characteristics of Prospecting
for Petroleum and Gas Pools in Them in Foreign Countries, Survey of
Foreign Literature," "Neftegazovaya Geologiya i Geofizika" [Petreleum-
Gas Geology and Geophysics], Moscow, VNIIOENG, 1977.
9. Grachevskiy, M. M., Kucheruk, Ye. V., and Skvortsov, I. A., "Petroleum
and Gas Deposits Associated with Buried Barrier Reefs," "Geologiya,
Metody Poiskov i Ra.zvedki Mestorozhdeniy Nefti i Gaza" [Geology and
Methoda of Prosnecting for and Exploring Petroleum and Gas Deposits],
VIEMS, 1977.
- 10. Grachevskiy, M. M., and Kucheruk, Ye. V., "The Highly Pro~ising Barrier
Reef Scarp of the Turkmen Part of the South Caspian Petroleum-Gas
Basin," VINITI, Moscow, 1978, Dep. Manuscript No 2625-78. _
11. Grachevskiy, M. M., Rucheruk, Ye. V., and Skvortsov, I. A., "Potential
of Heat Surveying in Prospecting for Reefs with Petroleum and Gas Prom-
ise," VINITI, Moscow, 1979, Dep. Ma.nuscript No 4302-79.
12. Mayerkhoff, A. A., "The Geology of the Huge Deposits of the La Refo~a
Zone, Southern Mexico," GEOL. NEFTI I GAZA, No 8, 1978.
13. Shteklin, I., "The Ancient Continental Ma.rgin in Iran," "Geol.
Kontinent. Okrain" [GEOlogy of the Continental Margins], Vol 3, Moscow, ~
1979.
14. Dias Serrano, J., "Hidrocarburos: abundancia y cautela," PETROL.
INTERNAC., Vol 36, No 7, 1978.
15. Flores Vargas, A., "Paleosedimentologia en la Zona de Sitio Grande-
- Sabancuy," PETROL. INTERNAC., Vol 36, No 11, 1978.
16. Jaafari, A., and Chadimi, M., "Forage et geologie du puits de plus
profond et le plus chaud du Nord de 1'Iran (plaine du Gorgan)," C. r.
4-ene Colloq. ARTER, Rueil-Mal~aison,"1971, Paris, 1972.
17. Judoley, C. M., and Furrazola-Bermudes, G., "Geologia del area del
Caribe y de la coata del Golfa de Mexico," Havana, 1971.
28
FOR OFFICIAL USE ONL�~C
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4

APPROVED FOR RELEASE: 2007/02148: CIA-RDP82-44850R000300054436-4
~t pE~IC~.~ USE ~,Y
D
e
18. Metz, W. D., "Mexico: The Premier Oil Discovery in the Western Hemi-
sphere," SCI.?CE, Vol 202, No 4374, 1978.
; 19. Nava Garcia, M., "Registros geofisicos en Tabasco-Chiapas y Campeche-
- Yucatan," PETROL. INTERNAC., Vol 36, No 11, 1978.
~
20. Niering, F. E., "A New Force in World Oil," PETROLEUM ECONOMIST,
Vol 46, No 3, 1979.
21. Stewart-Gordon, T. J., "Mexico's Oil: Myth, Fact and Future," WORLD
� OIL, Vol 188, No 2, 1919
~ COPYRIGHT: Izdatel'stvo "Nauka," "Izvestiya AN SSSR, seriya geologicheskaya",
1980 ~
l1,i76
CSO: 1822
END
~
29
FOR OFFICIAL USE ONLY
APPROVED FOR RELEASE: 2007/02/08: CIA-RDP82-00850R000300050036-4