Published September 1990 | Version v1
Journal article

A theoty of fast search for feul loading pattern in lWRs

Creators

  • 1. Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy

Description

In order to fast search for fuel loading pattern without trial and error, a theory for predicting in-core reactivity distribution, according to power necessity and available assemblies, has been developed on basis of the fast computing nodal method and two group diffusion theory. In that, the fast group flux distribution can be predicted from power necessity and the approximation of fast group constants to be independent of nodes. Then, the thermal group fluxes are expressed by both known powers and predicted fast fluxes. After replacing thermal flux, the thermal diffusion equations turn into some equations that have only unknown group constants. The unknown constants are expressed approximately by making use of some expansions of infinite multiplication factors of available assemblies. In such a way, the non-linear reactivity equations are developed and then solved, where node reactivities are the only unknown physical quantities, Finally, the loading pattern is obtained by setting some of available assemblies at each node location where corresponds to a closest reactivity of between laid assembly and node. A computer code LOADMP based on the theory has been made. The theory has been tested numerically on IAEA benchmark problem, and gives an accurate prediction of reactivity distribution and loading pattern. The CPU-time for making a loading pattern search is saved very much, about one second on the CYPER-825/170 machine

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
10
Journal Issue
3
Series
Chin. J. Nucl. Sci. Eng.
Journal Page Range
201-209
ISSN
0258-0918
CODEN
HYGOD

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
22073248
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ERRORS; FUEL MANAGEMENT; L CODES; NEUTRON FLUX; NUMERICAL SOLUTION; PROGRAMMING; REACTOR CORES; REACTOR FUELING
Descriptors DEC
COMPUTER CODES; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; RADIATION FLUX; REACTOR COMPONENTS