Thermohydraulic justification for the installation of block-containers with uranium-bearing material into experimental channel of WWR-c reactor

UDC: 
УДК 621.039

Issue of journal:

Abstract: 

This paper presents the feasibility of blockcontainers with uraniumbearing
fissionable material being installed into the experimental channels of the WWRc
reactor. Two versions of the blockcontainer structure were examined, namely, those
with regular and enhanced loading of the fissionable material. The arrangement of
the cooling system for the experimental channels of the nuclear reactor was
examined in detail, including the geometry of bench marks disposition where the
basic equipment is located. Designbasis justification was performed using the
ANSYS CFX 10.0 code. Designbasis justification for the cooling loop of the
experimental channel was performed based on the solution of the Bernoulli
equation. The following is shown: 1) the circulation loop with two experimental
channels equipped with circulation pumps ensuring the head of ≈ 2 atm and the
coolant flow of 3 m3/h does not require modernization for standard heat removal
from irradiated blockcontainers at all reactor power levels (up to 15 MW); 2) the
coolant heating in the cooling loop for experimental channels placed in series or
in parallel (consisting of 4 blockcontainers) amounts to ≈ 4 °C; 3) the maximum
temperature of the blockcontainer walls significantly varies on the side of the main
flow and on the side of the stagnant zone. In the most loaded blockcontainers (the
thirdfromthebottom of four) the maximum temperature of the wall on the side
of the main flow is no more than 70 °C, and on the side of the stagnant zone the
wall temperature exceeds saturated water temperature where coolant subboiling
is possible; 4) the pressure inside the gas cavity of the most loaded blockcontainer
does not exceed ≈ 1.5 atm which is the subtolerance value. It can be concluded that
practically at all reactor power levels (up to and including 15 MW) bubble boiling occurs
in the inner cavity of the blockcontainer and has a beneficial effect on the heat transfer
in general. The key results of the present paper are as follows: 1) the cooling loop of
the experimental channels does not require modernization; 2) three or four block
containers can be installed into the reactor without affecting the safe operation of the
nuclear facility.

References: 
1. ANSYS. Avaiable at http:// www.ansys.com
2. Lojcanskij L.G. Mehanika zhidkosti i gaza [Mechanics of Fluid and Gas] 6nd edition. Moscow, Nauka Publ., 1987, 840 p. (in Russian)
3. Forrest B.B., Booth T.E. et al. «MCNPA General Monte Carlo NParticle Transport Code, Version 5, Overview and Theory, Volume I», LAUR031987, LANL (2003).
4. Kirillov P.L., Bobkov V.P., Zhukov A.V., Jur’evJu.S., Spravochnik po teplogidravlicheskim raschetam v yadernoj energetike [Thermalhydraulic Calculations in Nuclear Power. Handbook]. Moscow, Izdat Publ., 2010, v. 1, 770 p. (in Russian).
5. Petuhov B.S., Genin L.G., Kovalev S.A., Solov’ev S.L. Teploobmen v yadernyh energeticheskih ustanovkah [Heat Transfer in Nuclear Power Plants]. Moscow, MEI Publ., 2003, 548 p. (in Russian).

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