JPRS ID: 10630 WORLDWIDE REPORT NUCLEAR DEVELOPMENT AND PROLIFERATION

• Document Type: CREST
• Collection: JPRS
• Document Number (FOIA) /ESDN (CREST): CIA-RDP82-00850R000500080004-4
• Release Decision: RIF
• Original Classification: U
• Document Page Count: 22
• Document Creation Date: November 1, 2016
• Sequence Number: 4
• Content Type: REPORTS

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JPRS ~'10630
2 J u~�r 1982
Worldwid~ Re ort .
~
- NU~CLEAR DEV~LOPMENT AND PROLIFERATION
CF4U0 7/82?
FBIS FOREIGN BROADC~4ST INFORMATION SERVICE
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JPRS L~10630
2 July 1982
WORLDWIDE REPORT
_ NUCLEAR DEVELOPMENT AND PROLIFER~4TION
(~OUO 7/82~
CONTENTS
EAST EUROPE ~
CZECHOSLOVAKIA
Chemical Effects in Fast Breeder Reactora Viewed
(Boleslav Eremiae, Miroslav Fresl; JA~ERN~~ ENERGIE, No 3,
_ 1982) 1
Deposite G~ntrol in V-1 Plant During First Shutdown
(Rudolf Burcl, et al.; JADERNA ENEKGIE, No 3, 1982) 7
LATIN AMERICA
ARGENTINA
Survey Concludes Nation Near Nuclear Weapon Capability
I
(Christopher Mosey; Tf~ TIMES, 27 Maq 82) 14
~ "
WEST EUROPE
~ INTERNATIONAL AFFAIRS
Ansaldo To Deliver Magnet for French Tokamak
- (ATOMO E INDUSTRIA, 1- 15 Apr 82) 16
ITALY
' Iteform of Nuclear Agenay ripproved
(ATOMO E INDUSq'RIA, 1- 15 Apr 82) 17
I Nuclear Power Plant To Be Deactivated
~
(ATOMO E INDUSTRIA, 1- 15 Mar 82) 19
~
~
~I
- - a - [III - WW - 141 FOUO]
~
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i CZECHOSLOVAKIA
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' CHEMICAL EFFECTS IN FAST BREEDER REACTORS VIEWED
~ Prague JADERNA ENERGIE in Czech No 3, 1982 pp 88-90
[Article by Boleslav Eremias and Miroslav Fresl, the G. V. A1?.imov Stats Research
Institute for the Protection of Materials, Prague: "Influence of the Chemical Com-
Fa~sition ~f Materials on Their Corrosion Resistance and Mass Transport Behavior in
So~iium. ~ircuits of Fas~r R~actors"]
[Text] The article summarizes and evaluates the investiga-
t~ons to date into the corrosion resistance and mass trans-
=i port behavier in liqsid sodlum of a~ exten~ive series of ma-
` terials ~n a wide range of chemical composition:?.
1. Chemical Comg4sition of Materials and Their Corrosion
The quantity of information available on corrosiqn and mass tranu~port in liquid so-
- dium, wh~ch could be of immediate use in designing fast reactors, is limited. How-
ever, many organizations have investigated the factors that ~nfluence the behavior
of materials in a sodium environment.
i Generally speaking, so far as hot spots (temperatures higher than 500�C) in sodium
circuits are concerned, the corrosion behavior of the investigated materials--aus-
tenitic steels and ~lloys, and also chromium-molybdenum steels--in circulating so-
dium tends to follow the trend of the so-called incubation pericd. Which meaas
- that in the initial stages of exposure to sodium there develop on the surface of
the materials fi~~s of reaction products with sadium, respectively with the impur-
ities contained in it; with continuing exposure these films tend to disanpear, and
the material goes over into the region of mass defects that are functions of time
[1J�
Studies undertaken in a number of laboratories [2, 3] establish~d that the time ne-
cessary for_ the removal of the oxide film of reaction products with sodium signifi~
cantly depen3s on the mechanical stability of this film in flowing aodium, and the
conclusions state that different rates of corrosion were observea in ~he process
of the film's removal. Other works in this f ield also pointed out that different
types of surface finish could produce films with differeat degrees of inechanical
stability in sodium [4]. Under isothermal conditions and at a stationary concentra-
tion of oxygen, the formation of oxide film of reaction products with sodium is lim-
= ited to the surface of the ^aterials, but it also has been demonstrated [5] that,
under certain conditions, this fitm may form in the regions of grain boundaries as
1 .
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well. So far it has not been determined whether such formations can weaken the grain
boundaries and become the precursors of intercrystalline corrosion attack. If under
the conditions of operation this type of intercrqstalline attack appears significant
in the case of alloys of the Incoloy 800 type and chox~aium-m~lybdeaum steels of the
9Cr1Mo type, then the state of the materia3.'s surface and the distiibution of oxi-
dizable elements (Cr, Mo, A1 and Ti) in the matrix of the alloy will be critical f~c- ~
tora in determining the nature and exteat of the attack. TherefQre a comparison of
the corrosion behavior of the mentioned two alloys with otk~er p~tential.materials far
- steam generators in installations with fast reaetors--such as materials of the AISI
304 or 316 typ~, or ferriti~ ateels of the 21~4er7.M~, 21/4Cr1MoNb or 21/4Cr1MoNiNb
' type--showed [6] that the effect of chemical compasition on the resistance to cor-
rosion and mass transfer in liquid sodium depends significFntly on the parameters of
the sodium circuits (the t~mperature and flow �~eloeity of the sodium, and ita oxygen
content).
In tests at high temperatures (for example, at 65~�C) and high sodium �low veYoci-
ties (greater that 3.7 m/sec), with different contents of oxygen, Incoloq 800 and
9Cr1Mo are insignificantly less sensitive to changes of the oxygen level of the so-
~ dium than is AISI 304 or 316, and significantly ~.ess sensitive than 21/~sCr1Mo,
21/4Cr1MoNb or 21/4Cr1MoNiNb. At low oxygen levels (less than 30 ppm) t.he corrosion
rates rank as follows: I-R00 > 304 > 316 > 9Cr1Mo > 21/4CF1Mo >~l/4Cr1MoNb >
> 21/4Cr1MoNiNb; at higher oxygen levels (over 30 ppm) the rates of corrosion rank
as follows: 21/4Cr1MoNb (21j4Cr1MoNiNb)> 9Cr1Mo >~16 > 304 ' I-800, In tests at low
~ temperaturES (for example, at 550�C) and verq Low sodium flow velocities (convective
~ sodiuTa lo~ps) anc? different oxygen levels, the difference betwee~ the corrosion
rates of austenitic anr] le~~a-all4y ferritic steels is especially significant; and
when b~th types of materials are tested together and the oxygen content is not high,
the corrosion rate is influenced more by the f`low vel~city and period of exposure
than by the oxygen content of the s~dium [7]. Although many organizations have made
preliminary studies of the corrosion behavior of materials for ~.he sodium ~ircuits
of fast rea~tors, none of these studies is sufficientlq detailed to provide an over-
all picti~.re of t'ne corrosion behavior ~f all the considered types of materials, espe-
cially when two or more types axe testpd together. The information available from
publishec? data on corrosion teats in sodium loops, which ch~rac*erizea the data
mentioned above~ ia summarized in Tables 1 and 2.
Table 1. Effect. of Chemical Composition on the Corrosion Resistance of Materials
for the Sodium Circuits of Fast Reactor~, at High Temperatures and Sodium
Flow Velocities
.
~l~~Zi" r~~ r~
' i '
tcplnta ~ c~�ci~luKl nb.:~l~ korniui
>G~t~~ri~il sodiku ~ xodfku I~>-ylikii ~ r>�chloHt
[�C1 f~~~lyl ~ IDP~~~I ~fu~~~'~�c~1~1
1 �~t~4crIJluNI, r,;,n I s
'9Crlvio r,:;;) ~3 3.r,.~
:1TST ;D11i ti:;i) S) :i ~i.~l
1-ifll~ li.ill I ll `~.89
I-;jnll li.i(1 I ~ ~i(1 I i~
:~ISI31(i u:;~~ y :~u ~>u:c
- ~c~riMo ~;:~o ~ _~.~~3
_'1'~Cr1M