ORIG. RUSSIAN: RADIOISOTOPE FUELED THERMOELECTRIC GENERATORS

• Document Type: CREST
• Collection: General CIA Records
• Document Number (FOIA) /ESDN (CREST): CIA-RDP88-00904R000100100019-0
• Release Decision: RIPPUB
• Original Classification: U
• Document Page Count: 21
• Document Creation Date: December 22, 2016
• Document Release Date: August 12, 2009
• Sequence Number: 19
• Publication Date: May 1, 1964
• Content Type: STUDY

 Approved For Release 2009/08/17: CIA-RDP88-00904R000100100019-0
00,
Third United Nations
International Conference
on the Peaceful Uses
of Atomic Energy
Confidential until official release during Conference
A/CONK'. 23/P/313
USSR
May 1964
Original: RUSSIAN
RADIOISOTOPE FUELED THERMOELECTRIC GENERATORS
Voronin A.N. , Gverdsiteli I.G.,
Orinberg R.S. , Gubanov Ju.D. , Zharkov V.A. ,
Zhukov V.F. , Kovirsin V.K. , Kodjukov V.M. ,
Korotkov N.P. , Kucherov R.Ja. , Lalikin
S.P. , Ragosinski A .I . , Fradkin G.M. ,
Shind e r ov B. L. , Erman S. Ja.
During the recent years a great attention has been paid
to the design of low power self-contained sources utilizing
the decay energy of radioisotopes . Since these power sour-
ces are extremely reliable and have a longer service life
not requiring an additional charge they may be used to supply
power to remote maintenance-free devices.
This report describes two radioisotope fueled thermoelect-
ric generators designed in the USSR. The first power source
utilizes Po-210 as a fuel, while the second one - Ce144
I. Radioisotope power source using Po2'10
For recent years many papezz have been published descri-
bing various radioisotope fueled thermoelectric generators
delivering from 1 to 100 W. Lead selenides and tellurides
are used as a thermoelectric material because of their
higher figure of merit as compared with the well known ma-
terials. The figure of merit however is not the only factor
indicative of thermoelectric material suitability. Appli-
cation of high temperature alloys (although with the less
figure of merit) allowed to increase the emitter tempera-
tare and so to save the weight of the device the efficiency
being the same due to the greater temperature difference
between hot and cold junctions.
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A number Of t..:.:'",;u-.?iectric generators were designed
wi.;.h tae initial power up to 10 W , they had similar thermo-
electric conversion systems and differend only in a radiator
and in the way the thermopiles are pressed to the hot sur-
face. These instruments were used to determine equipment
capacity, electrical parameters and temperature distribu-
tion through the blocks by means of a radioisotope heat
source simulator.
Principle parameters. The preliminary investigation of
the device versions have showed that a design where a flat
capsule is snuggly fitted between hot surfaces of two
thermopiles the cold junctions of which are attached to the
radiator is a simplest one; this device has sufficiently low
heat loss.
The capsule has the shape of rectangular parallelepiped
of 60x60x13 mm. Manufacture technique and operating c onditi
limit to some extent possible values of its pa.ralleters. lez
example to make a capsule reliable at high pressure (up to
200 atmospheres) caused, by helium produced in the decay its
surface temperature should not exceed 85000. Temperature-resis-
tant rubber used for sealing the device limits the tempe-
rature of the radiator , which should not be more than 250?C.
A semiconductor section of the thermoelectric elements
was chosen 3 cm long; if the length welb less the power would
fall off due to the higher commutation resistance in the
total thermal. battery resistance and the insulation plate
resistance fraction in the thermopile resistance. On the
other hand , if the length 1 is more than 3 cm the weight of
the device builds up but its elecic characteristics are
improved slightly. Silicon-germanium alloy used in this
device has nn average figure of merit Z = 4.10-4 1 /?C and
a thermal conductivity factor x = 1.5.10-2 cal/cm. sec.0C.
The results calculations made it possible to choose
the principle parameters, temperature characteristics and
efficiency of the device . The results are listed in
Table I.
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Conversion device. The silicon-germanium alloy was
used as a thermoelectric material of the conversion device
because of the following factors: a) high operation tem-
perature (above 10000C) ; b) low vapor pressure at T=1000 0C;
c) high strength; d) resistivity against radiation; e) low
specific gravity. Each battery of thermogenerator comprises
16 thermoelements connected in series (8 thermoelements are
of 'p'-type and the other eight of 'n'-type) , they are
screwed between two metal plates. The hot surface plate is
made of carbon steel and the fixing screws are of molyb-
denum. The cold surface plate and its fixing screws are
made of copper. Thermoelements screwed between steel and
copper plates are coupled by molybdenum wire contact
welded with the nickel foil 0.02 mm thick.
Both batteries are connected in series. In the instal-
lation 5 this connection is provided by a copper contact
insulated with ceramics; in installations 6 and 7 the housing
is used as a connecting conductor.
Installation housing. The housing of the installation 5
is of duraluminium and is cylindrical in shape, its bottom is
provided with a flange to form sealing with a copper top of
the housing. Two metal electrodes with ceramic insulation
are welded into the copper top. The shape of the copper top
flange is so chosen that the bottom can move 2-3 mm with
respect to the flange due to the top deformation. Gas-tight
coupling between the top and the housing is provided by
a sealing ring of temperature-resistant rubber.
Since the housing of installations 6 and 7 are of duralu--
minium throughout, they are more rigid and lighter, the
thermopiles are closer pressed to the radioisotope heat
source capsule. The thermobatteries of the installation 5 are
pressed to the radioisoliope heat source capsule by means
of a disk steel springs fitted on bolts coupling two parts
of the housing. To provide good thermal contact between the
elements of the installation 7 the both parts of the hou-
sing are coupled by a clamp secured to the flanges. The
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low section of the housing has stiffening ribs. The construc-
tion of the top section permits bending of the bottom with
respect to the cylinder flange at a distance of 2 mm. The
holes are provided in the housing to remove air from the
interior and to fill it with the thermoinsulating material
"Perlit". To increase blackness factor the housing is
c oated with a thin layer of hot proved paint with f =0.85.
Fig.I shows general view of the installation 7.
Electrical Simulator Used for Capacity Tests of Gene-
rator. The electrical simulator of the radioisotope heat sour-
ce is a graphite unit (size: 60 x 60 x 13 mm) with a molyb-
denum hairspring. Heater power was determined by connecting
a a.c. wattmeter into the heater circuit. The performances
of these systems were shown to be stabl.j during 1000 hour:..
operation. The results are listed in Table 2. The efficiency
and electric power of thermogenerator 6 with the nuclide heat
source simulator were also determined under various tempe-
rature conditions, Figs2 shows the test results.
Radioisotope Heat Source. Radioisotope heat source is a
rectangular parallelepiped; it is made of stainless steel.
Capsules containing Po210 are inserted in five cells.
The nickel capsule containing 1000-2000 curies of Po210 is
mounted within two stainless steel tubes for strength. Tubes
are provided with screw stoppers, welded during assembling.
Fig-3 shows a general view of the radioisotope heat source
and its components. The source thermal power was deter-
mined call orimetrical ly.
Tests of Thermoelectric Generator with Radioisotope
Heat Source . Generator 7 has undergone tests. The thermo-
generator with a nuclide heat source containing Po210 the
original thermal power of which equaled 24+4 W was. set up
for 50 minutes, then it was connected to the meters. Accor-
ding to the bench test of generator 7, the following para-
meters wer continuously controlled: the voltage produced
by the thermogenerator across the load 0.34 ohm; the hot
skin temperature (two points) ; the radiating housing tempe-
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rature (two points); the gamma-radiation dose-rate at a
distance of 0.3 m from the source. The test results
are 1 isted in Table 3.
Fig.4. presents volt-ampere characteristics taken perio-
dically (in five-seven days).
II. Electric Power Generating System Containing Ce144
At present time the human life is hardly possible
without reliable and serviceable weather stations situated
both in inhabited regions and in remote almost inaccessible
ones, where there are no constant electric power sources.
The available power sources have definite limitations ham-
pering their usage and can not operate reliably and c ontius-
ly.
Electric power nuclide sources based on the thermo-
electric principle of converting the thermal power into
electricity are more reliable and have suffi;,iently high elect.
rical parameters,
The generator considered is a prototype of an electric
power source for automatic meteorological stations. The
possibilities of generators utilizing short lived beta-emit-
ting nuclides were determined by a test model with a heat
source containing 144 during controllable period (constant
output power) and uncontrollable one (output power falls off).
Performances. By the beginning of an uncontrollable pe-
riod the nuclide fueled generator contained 17500 curies of
Ce,1144 . Fig.5 presents the
generator general view.
During an uncontrollable operation electric output is
5.0-5.6 W; voltage - 3.5 V ; overall efficiency 3.5 - 4%.
A thermopile based on solid d solutions of Bi: Bi2Te3+Bi2Se3
('n4-type conductivity) and B12Te3 + Sb2Te3 ('p'-type con-
ductivity) are used to convert the heat into electricity.
A special automatic device provides a predetermined power
level. The electric power is oonsumed by a storage battery
with a capacity of 12 A/hours, this battery supplies power
to a weather station, working in pulsed operation with 26 V
and 6 A. 318
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Radiation shielding consists of operating and shipping
containers. The operating container shielding was designed
to provide dose rate not more than 1.0 r/hr at a distance
of one meter from the generator surface. While the operating
container inserted into the shipping one the dose rate re-
duces to the value not exceeding 10 mr/hr at a distance of
one meter from the shipping container surface. The operating
container has removable stiffening ribs, and the shipping
one - fixed stiffening ribs. The generator may be used in-
serted into the operating container and into shipping one
Tungsten and lead are used as shielding material. The total
weight of the generator with the operating container is
400 kg, the shipping container weight is 1200-1400 kg.
Main Parameters and Engineering Design . A necessary
electric power of the generator is calculated assuming that the
diurnal values of consumed energy and the delivered one are
equal. The values of a necessary thermal power and an elect-
ric power for one disintegration assuming the gamma-absorp-
tion in the fuel, capsule and heat unit determine the radio-
isotope activity.
While constructing the device a particular attention
has been payed to ensure a required radiation shielding,
a minimum temperature drop between a cold junction and
an ambient air, a lighter weight and smaller overall dimen-
sions. Several designs were considered having various tungsten
heat block-to-lead shielding thickness ratio. The construc-
tions differed in the way the thermopiles are replaced, in
the thermal regulation (radiation, thermal shunt, insulation
thermal conductivity) ; in the shape and material of the
radiation shielding (spherical and cylindrical geometry) ;
lead, tungsten and depleted uranium were considered as
shielding materials,
The generator comprises: a) a heat and a radioisotope
blocks; b) a thermopile; c) a thermal power controller;
d) an arrangement for substitution of the thermopile;
e) housing; f) a biological shielding.
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radioisotope
A block is fitted within a tungsten cylindrical heat
block with a diameter of 100 mm, its sides are 20 mm and
bottom is 40 mm thick. The cylinder is closed with a hemi-
spherical top fixed to the cylinder with a covering ring.
A isotope block is a double capsule made of stainless
steel XI09T-type. It consi%s of two coaxial cylinders
within which a vessel is inserted filled with a melted cerium
molybdate. Each cylinder is closed with a top, argon-arc
welded and is checked for air-tight sealing. The heat block
is mounted on the thermopile consisting of 97 thermoelements.
The thermopile is fixed in a special case and attached to the
bottom made of cylindrical copper plug. In order to maintain
nominal temperature conditions the generator is provided with
thermal control means including special thermal shields and
a control actuator with a reducing gear. A constant heat
flux through the thermopile (when isotope block power falls
off) is assured by reducing a radiating surface of the heat
block by moving the thermal shield. Fig.6 presents the ther-
mal power vs time. The spring thermal control actuator is
driven electrically. A thermal block, a thermopile and an
arrangement for substitution this thermopile are inserted
into a cylindrical housing with welded branches to mount a
case with a thermopile. A cap with a lead filler closes the
top end of the housing. Operation and shipping containers
provide a radiation shielding. Stiffening ribs of aluminium
alloy are used as a heat-removing system . This system
consists of 64 rectangular ribs fixed with a coupling bolt
on the operating container; these ribs provide a required
temperature drop between an ambient air and a thermopile
base. The conjugate surfaces of the dismountable elements
are highly finished and a sufficient specific pressure is
ensured at the point of contact.
Thermophysical Calculations. Cylindrical heat source
temperatures were calculated from a thermal conductivity
differential equation. Heat flux distribution over genera-
tor blocks were also determined. This distribution depenus
upon the thermopile operating conditions i.e. free running,
rated e d operation, and short circuit.
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The results are listed in Table 4.
4. Heat Generation Calculation
The heat generation in the unit, containing Ce144 is
determined by beta particles of Ce144 + Pr144 and gamma-rays
absorbed in both isotope and heat blocks.
Space distribution of the specific heat generation due
to beta-emission may be considered uniform throughout the
capsule interior. Heat leakage due to bremsstrahlung are neg-
lected since a bremsstrahlung transfered energy equals
1-2 per cent of the total energy; the most portion of this
energy is absorbed in isotope and heat blocks. Space distri-
bution of the specific heat generation due to gamma-radia-
tion (it is of particular importance for nuclides of the
Ce137 type) is defined by the following expression:
for gamma-radiation absorbed by the capsule material
kc , E t(E)pQ. (E)
V
-~ I )z ga (E) I z _*c Pt
( t C
Here Q r (r ) - heat generation per a volume unit close
to the point with coordinate r (W/cm2) ; k = 1.b .'10-13 W. sec /Mev ;
q - material specific activity, curies/cm3 ; n(E) - number
of gamma-rays per one disintegration; V - capsule core
volume; E - gamma-ray energy;)! (E) and_Ao- (E) - gamma-ray
attenuation coefficient and energy-absorption coefficient
in the fuel respectively; Ba[ (E) / r - 'r' /3
accummulated absorbed energy factor for gamma-radiation in
the fuel.
Similar relations exist for gamma-rays absorbed by the
(r') ,
capsule walls Q t2 (r) and by the heat block Q r,3
The total heat generation is calculated by integrating
the expressions for Q (r) Q (r") and ;Qj (r )
over drug, capsule and heat block volumes respectively. The
heat generation during rated operation (controllable period
end) was 135 W (17500 curies),
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Thermal power of the isotope block was measured by a
special calorimeter, the obtained data agreed with the cal-
culated ones.
Radiation Shielding Design. A multigroup method was
used to design shielding, partial gamma-ray constants (the
dose-rate given by the separate gamma line of the unshielded
isotope) corresponding to gamma lines of Ce144 +Pr144 was
first determined. Bremsstrahlung was taken into account
by replacing a continuous spectrum with a discrete one for
each line of which a corresponding gamma-constant was deter-
mined. A series of partial gamma constants obtained was
treated according to "competing lines" method that resulted
in time saving.
The necessary heterogeneous shielding thickness was cal-
culated from
---~P~---- = q Ykri L i Bi ,
k
(I)
where P - permissible dose rate; k - assumed safety factor ;
q - drug specific activity ; k - partial gamma-c onstant;
T, - radiation function of the cylindrical source behind
the shielding allowing for geometric factor, self-absorption
in the source and attenuation in the shielding disregarding
the scattered radiation (radiation function was calculated
by an electronic computer) ; Bi - dose buildup factor
allowing for multiple scattering of gamma-radiation within
both the drug and capsule substance and the shielding.
The following expression was used for a dose buildup
factor in a heterogeneous medium
N n-4
Lkdk)-~, ah, (i Pi.k d
k-4 )
(2)
where N - number of heterogenous shielding layers; '[K
attenuation coefficient of K-layer; dk - K-layer thickness.
Expressions (I) and (2) were used to determine a dose
rate on the shielding surface. I is necessary to notice
that thicknesses calculated by this way agree with thick-
ness values estimated according to Monte-Carlo method.
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Table 5 lists calculated values of two different shielding.
Thermoelectric generator and Voltage Transformer. A ther-
moelectric conversion device consists of 97 thermoelements
(5 mm x 5 mm) , 20 mm high. The thermoelements are made up of
solid solutions based on triple alloys Sb2Te3+Bi2Te3
and B12Te3 + B12Se3. A solder provides commutation allowing
to pperate in the temperature range of 300?C. To prevent the
thermoelements from oxidation at high temperatures hot Jun-
ction are coated with a thin layer of a special enamel. The
total heat losses of the generator were calculated allo-
wing for the heat losses across the thermopile insulation
and the other blocks. The generator tests carried out by
means of an electrical simulator of the heat source under
normal operation conditions showed good agreement between
calculated and experimental data. Fig-7 presents generator
load characteristics obtained at controllable operation,
fug.8 - the same ones during the uncontrollable period after
50 days of operation under these conditions.
To recieve a d.c. voltage of 26 V this system com-
prises a transistorized dc-dc transformer. Energy storage
is accomplished by silver-zincum accumulators. The transformer
supplies current to the storage battery depending on the
operating conditions of the meteostation. The transformer
efficiency is 75 per cent; the accumulator efficiency is
75-430 per cent. The higher overall efficiency of 98 per cent
achieved with accumulators connected in series ,
Operation. The above generator with accumulators and a
voltage transformer is used as a power source at an automatic
weather station located in the middle part of the Soviet
Union. To minimuze a dose rate around the generator it is
slightly buried into the ground. The generator operation
was controlled by the output instruments which indicated
the principle parameters: voltages electromotive force, current
All output parameters of the dc-dc transformer and accumu-
lators were automatically recorded.The operation recured
in every two hours. The output power at the end of control-
lable period was 5.4 W , voltage was 3.6 V.
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Fig.9 shows variations of the dc-dc transformer input
voltage (9-a), of the accumulator battery output voltage
(9-b) and of the transformer efficiency for the whole cycle
of operation . During an uncontrollable operation after two
meteo
month period of 2 hr cycle the station was transffered to
3 hr cycle. Climatic conditions were controlled during this
experimental operation. The heat removal depended on these
conditions. At present the system is in operation and if
the power falls off the intervals between the operation should
be made longer.
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List of References
1. Barnat M. et al. Nucleonics, 17, No.5, 166 (1959).
2. Harvey D.G. , Horse I.G., Nucleonics, 19, No.4, 62 (1961).
3. Harvey D.G. , Carpenter R.T., IAS Paper , No.61, 18(1962).
4. 14O NS L. 1lonynpoBoAHHxoBNe TepuoaneMeHTba. MBA.AH CCCP9
1956,
AzenenoB B.C., IIeKep JI.I{. CBeubi pacnaAa paAxoaxTraBHbX
RAep, MBA-BO AH CCCP, I958*
b. OpaAim r.y., Kynxm L.E. NCTOIIHMHX o. j6 , / H HeMTpOHHNx
x3AygeHx#, rocaTouHaAaT, 1961 .
Geiger I.S. et all Nuclear Physics, 28, 387-406 (1961).
8. K.K.ArniHue!, B.M.KOAIKOB, M.JIHaJiaB, X1.B.CxBMHI;eB.
HpxxnaAHag AoafMeTpIR, rocaTOMH3AaT, 1962 .
9? KyTaTexaA3e C.C. OCHOBH TeopWR TenJtootaexa, Morn,
1962 .
10. EypuTe I.H A,N. OII3i ecxxe ocxoBbI pacgeT noJlynpOBOAHHxoBHx
TepRO3J1exTpw ecIwx yCTPOYICTB, )H3MaTPH3, 19629
11. PorHncx1# B.k . 3IIexTpOnHTaHxe pa1i ioyCTpo 4CTB, CBR3bM3-
AaT, 1963,
12. Collin W., Physics Letters, 5, 329 (1963).
13o rycem H.r . , $OBH11 eB I.E. M AP-, 3au Ta OT ianyqeHxR
fIPOTFIMeHHbXX MCTOgHHKOB, rocyAapCTBeHHOe H3AaTeJILCTBO
xxTepaTypBa B o6BaCTH aTOMHOM Hay= I TexH]dxx, 196I.
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 Table I
-
Insulation thermal resistance, -_C_sec_
12
cal
2. Heat flow through insulation, W
49
3. Initial heat power of the capsule. W
320
4. Radiator surface , cm2
900
5. Number of thermoelements (allowing
for the external load voltage of 1.8 V)
32
6. Thermopile cross section, cm2
0.8
7. Hot junction temperature , ?C
760-775
8. Cold junction temperature, ?C
300-330
9. Thermoelectric generator efficiency, %
3.5-3.9
10. Overall efficiency, %
3-3.3
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? 3 ? 4 ? 5
9. Radiator maximum
temperature when
Q = 320 W, 00
241
250
240
10. Maximum temperature
of the thermoelement
hot plate when
Q = 205 W, 00
670
650
633
11. Radiator maximum
temperature when
Q = 205 W , OC
190
196
195
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Table III
Nos. Parameters
Operation period, hours
48
1000
1400
2000
I Thermal power of the
radioisotope heat
source, W.
244
200
185
163
2 Electromotive force, V
2.85
2.3
2.09
1.88
3 Load voltage 0.34 ohms, V
1.4
1.14
1.04
0.92
4 . Power output, W
5.8
3.79
3.24
2.52
5 Installation effi-
ciency, %
2.36
1.91
1.75
1.55
6 Thermoelectric generator
hot plates temperature
when operating at the
load of 0.34 ohms,
759
633
600
545
o0
746
542
503
440
7 Radiator housing tempe-
230
202
192
163
rature, 0C
216
190
178
157
8 Activity of the radioiso-
to a heat source using
Po310, curies
7700
6300
5320
5140
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Table IV
Operating Thermopile Heat flux Heat flux Thermal
conditions temperature via ther- via the efficien-
drop mopile, other cy
w blocks,
W
------------- ------------------------- ------------------------
Free
running
225
112.5
22-5
83.4
Rated
operation
190
119
16
88
Short
circuit
170
121
14
89.6
Note: Cold junction temperature assumed to be O?C, the ambi-
ent temperature - +20?C. Electric power of the
thermopile is of 5.2 watts.
Table V
Direction Ver- Container type
Sion - ---------------------------------------
0 Shipping
: Shipping
Axial
I P b - 12 cm Pb - 9!8 c m
2 W-1 cm + Pb-10.I cm Pb - 9.9 cm
---------------------------------- -------------------
Radial
1 Pb - 11.8 cm Pb - 9.8 cm
2 W-2 cm + Pb - 8.2 cm Pb-9.9 cm
Note : Ce144 total activity of the source is
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30000 curies; a dose rate is I 12/h and 10 mr/h
at a distance of 1 meter from the operating
container and the. shipping one respectively.
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Fig.1. General view of the generator, containing po2'10
Fig.2. Electric power and efficiency of the installation
under various thermal conditions
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Fig.3. Heat source capsule
and its components
Fig.5. Generator general view
using Ce144
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Fig.4. Volt-ampere characteristics
Fig.6. Thermal (Q) and
output electric (P) power v. s.
operation time
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7. Generator load characteristic Fig.8 Generator load
under controllable conditions characteristic under
I - ambient air temperature uncontrollable conditions
+10?C
2 - ambient air temperature
+600C
4 Pa$oma cmaW14uu Z t7aaj060d vac05 1 Qo*ma cmo tIw
a) ;
b o0
- h b
CU
8)0,7,s1?
0 /0 20 d0 40 30 50 70 00 90 100 110 120
3 8ptHRCI'~#j
Fig.9. The pattern of change of DO-DC transformer
input voltage (a ), accumulator battery output
voltage(b) and transformer efficiency (c) for
one operating cycle of the weather station
318 1 - station operation; 2 clock winding up
- 20 - 3 time (min)
Approved For Release 2009/08/17: CIA-RDP88-00904R000100100019-0