Published October 2002 | Version v1
Conference paper

Analysis of Control Rod Ejection Accident in MOX and MOX/UOX Cores with Time-Dependent Multigroup Pin-by-Pin SP3 Methods

Description

Multigroup, pin-by-pin transport methods based on the SP3 approximation have been implemented in the U.S. NRC neutronics code PARCS and applied to analysis of a control rod ejection transient for MOX/UOX and UOX fueled cores. The purpose of this paper is twofold. First, comparisons are made of rod ejection transient results for the MOX/UOX and UOX cores in order to assess the impact of MOX on core transient performance. Results here indicate that the MOX/UOX core shows an earlier and smaller power peak compared to the UOX core. Point kinetics parameters were generated from the spatial kinetics results in order to help explain the observed behavior. The second purpose of this paper is to assess the importance of multigroup transient transport calculations for highly heterogeneous problems. A comparison of the 8-group pin-by-pin SP3 with the conventional two group nodal diffusion methods indicates that the difference of the predicted control rod worth is a large source of the discrepancy between the higher and lower order results. (author)

Part of:
Proceedings of the PHYSOR 2002 International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
Imprint Pagination
9 p.

Conference

Title
International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing
Acronym
Physor 2002
Dates
7-10 Oct 2002
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
55004304
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTROL ELEMENTS; CONTROL ROD WORTHS; ROD EJECTION ACCIDENTS; TIME DEPENDENCE; TRANSIENTS
Descriptors DEC
ACCIDENTS; REACTIVITY-INITIATED ACCIDENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS

Optional Information

Notes
6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)