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A method for calculating plutonium source LMFBR accidents

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T.A.E.C. Ç E K M E C E N U C L E A R R E S E A R C H A N D TRAINING C E N T E R

I

s t a n b u l

-

t u r k e y Ç N A E M - R -151 A M E T H O D F O R C A L C U L A T I N G P L U T O N I U M S O U R C E L M F B R ACCIDENTS By M. Kırbıyık

P. K. 1, Hava Alanı, İstanbul, Turkey

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Mehmet K ı rbıyık

Çekmece Nuclear Research and Training Center

In liquid-metal fast breeder reactors (LMFBR*s)

the

more abundant uranium-238 isotope is converted to

plutonium,

which can be utilized as a fissionable nuclear fue l ,

The fuel

in L M F B R ■s is a mixture of about 20$ plutonium

and

80$

urani­

um-2 38. Current generation L M F B R ’s use U Og—PuOg

fuel,

A m ajor concern in LMFBR safety analysis is the

re­

lease of biologically hazardous plutonium aerosols to the environment in the event of a large accident. The plutonium- vapor source term determines the initial conditions of plu­

tonium transport as particulate aerosols. These plutonium aerosols could result from condensation of plutonium

vapor

that has b e e n vaporized during the accident. The rate

of

aerosol production will be directly related to the

rate of

vaporization. Experimental and analytical results show that sizes for condensed plutonium particles before

agglomeration

1

2

and coagulation are less than 1pm. ’ . These

submicron-size

particles are the primary radiological source

available for

leakage to the environment.

The objective of this work was to estimate

upper

limits for the generation of vaporized plutonium

during dis­

assembly and during subsequent expansion of the fuel

in

a large core-disruptive accident. Fuel-vapor generation

during

disassembly was calculated u s i n g the VEKUS-II

code^. The

ex­ pansion after disassembly was assumed to be isentropie,

The

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îuel was allowed to expand to low pressure; and in this process further fuel vapor was formed. Heat transfer and mixing prior to expansion might reduce fuel-vapor source while at the same time generating sodium vapor.

In VENUS-II the fuel density in each mesh cell is calculated during disassembly. By u s i n g the fuel properties, described in R e f e r e n c e ( 4 ) , the quality and, hence, the mass of fuel vapor in each cell during disassembly were calculated. Fuel-vapor generation d' ring isentropic expansion was calcu­ lated from the initial conditions of the fuel at the end of disassembly and the final conditions at the end of an expansion to a specified final pressure. The amount of plutonium vapor­ ized in eaoh mesh cell is the product of the plutonium atom fraction in the fuel(<w20^) and the total mixed-oxide fuel vaporized. It was assumed that PuC>2 acts like UOş. Then

plutonium-vapor inventory for the whole core is equal to the sum of the plutonium vaporized in each mesh cell.

The analytical method was applied to the test case calculation of Jackson and Ficholson^, which was a core-dis­ ruptive accident with sodium present, based on Fast Flux Test Facility geometry. Cases were also calculated with sodium removed or partially removed from the core, but the reduction in the doppler constant from -0.0040 to -0.0025 where sodium was completely removed. The results are given in Table 1,

Little vapor generation was calculated for the sodium present case but a sizable fraction of the fuel vaporized in the sodium removed cases. Vaporized plutonium-time histories are shown in Fig. 1.

These results represent one step in the estimation of the plutonium source term. 0n l3r a small fraction of these results, after condensation, can escape from the primary system to the containment building.

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-TABLE 1

Percentages of the Total Plutonium Vaporized

End of

Isentropic Expansion to Pressure P

Case Disassembly p-100 atm.

p=30 atm. ~o=10 atm.

p-1

atm,

1 ( s o d i u m -in) 1 1 o H icT* H O 1 0.004 0.4 2 (partially voided)

0.1

1.2 3.7 6.0 8.9 3 (sodium- out ) * o 2.9 6.4 8.7 1 1 . 6

Total Plutonium Mass * * 6 8 9 Kg.

ACKNOWLEDGMENT

The assistance of

A.L.

Reynolds

is gratefully acknow­

ledged» This

work was performed under the

auspices of the

U.S.Atomic Energy Commission. REFERENCES

1. AfV.Castleman Jr., F.L.Horn, and G.C. Lindauer, "On the Behavior of Aerosols Under Fast Reactor Accident Condi­

tions", Brookhaven National Laboratory, B N L - 1 4 0 7 0 ( 1 9 6 9 ). 2. R.L.Koontz, R.S.Hubner, and M.A.Greenfield,

"The Effect

of Aerosols Agglomeration on the Reduction of

the Radio­

logical Source

Term

for the LMFBR Design Basis

Accident",

Atomic International, AI-A E C - 1 2 Ö 3 7 (1969)•

3» J.F.Jackson and R.B.Nicholson, "VETTUS-II: An LMFBR Disassembly Program",Argonne National Labo r a t o r y ,ANL-7951(1972).

4. M. Kırbıyık, "Fuel-Vapor Generation in LMFBR Core-Disruptive Accidents", Ph.D, Thesis, University of Virginia,

May,1975»

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3-M A S S OF P LU TO N IU M V A P O R / M A S S OF PLUTON IUM

Fig .1 Relative m ass of plutonium vapor produced during disassem bly. 0.0

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