Calculational and experimental investigations of void effect -- A simple theoretical model for space-dependent leakage treatment of heterogeneous assemblies

Journal Article · Thu Dec 01 04:00:00 EST 1994 · Nuclear Science and Engineering; (United States)

OSTI ID:6630676

Benoist, P; Petrovic, I ^[1]; Mondot, J ^[2]

---

1. Commissariat a' l'Energie Atomique, Gif-sur-Yvette (France)
2. Commissariat a l'Energie Atomique, Saint Paul lez Durance (France)

This method, which takes into account the influence of assembly heterogeneity on neutron leakage, is based on the heterogeneous B[sub 1] formalism, which assumes the existence of a fundamental mode in an infinite and regular lattice of heterogeneous assemblies. A simplified formalism, TIBERE, is presented that allows one to define directional space-dependent leakage coefficients. This method, introduced for two-dimensional x-y geometry in the APOLLO-2 multigroup transport code, uses classical and directional first-flight collision probabilities. One can now define leakage cross sections as additional absorption cross sections that have space and energy dependence, as well as all other cross sections. Hence, one obtains perfectly consistent reaction and leakage rates used in an equivalence procedure, determining cell-homogenized parameters for a whole core calculation. The study of this refined heterogeneous leakage treatment was undertaken because of the insufficiency of the homogeneous leakage model, especially in cases when an assembly contain voided zones or almost voided zones, i.e., zones with a long mean free path, so that the streaming effect may become important. The fission rate comparison between the EPICURE reactor experimental results and the results of the corresponding whole reactor calculations were accomplished, with leakages calculated by the homogeneous and the TIBERE procedures of the APOLLO-2 code.

• OSTI ID: 6630676
• Journal Information: Nuclear Science and Engineering; (United States), Journal Name: Nuclear Science and Engineering; (United States) Vol. 118:4; ISSN NSENAO; ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
A CODES
COMPUTER CODES
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
HETEROGENEOUS EFFECTS
KINETICS
MATHEMATICAL MODELS
NEUTRON LEAKAGE
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY COEFFICIENTS
REACTOR KINETICS
REACTORS
SPACE DEPENDENCE
T CODES
THERMAL REACTORS
VOID COEFFICIENT
WATER COOLED REACTORS
WATER MODERATED REACTORS