Published October 2002 | Version v1
Conference paper

The use of WIMS for gas-cooled reactor calculations

  • 1. Serco Assurance, Winfrith Technology Centre, Dorchester, Dorset DT2 8ZE (United Kingdom)

Description

The Advanced Gas Cooled Reactors(AGR) operated in the UK are a design that has features that test the capability of reactor codes. The WIMS code is a general neutronics package that has the capability to model this type of reactor. This paper outlines some recent developments to the hybrid Monte Carlo package called MAX within WIMS. These improvements were designed to improve the speed and accuracy of calculations that mainly involve perturbations due to temperature or irradiation. The method adopted is outlined in the paper, in particular the linkage to the deterministic code CACTUS and the treatment of sequences of perturbations are described. The paper also outlines the developments to the WIMSBUILDER package that significantly eases the generation of input for WIMS calculations involving a sequence of perturbations to temperature and then cycles through a set of depletion steps. Finally the paper outlines a number of validation results that test the performance of this new package. Results are presented that show the package accurately predicts 3D effects, temperature coefficients, poison worth and irradiation effects. The resultant code is also shown to be ∼ 2 orders of magnitude faster than both the older version of the code and conventional Monte Carlo calculations. Thus the paper concludes that this new method is capable of being used to accurately model complex situations and can be used in conjunction with the code PANTHER to apply these results to whole core situations. (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
10 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
55004481
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DISTURBANCES; GAS COOLED REACTORS; MONTE CARLO METHOD; PERTURBATION THEORY; TEMPERATURE COEFFICIENT; VALIDATION
Descriptors DEC
CALCULATION METHODS; REACTIVITY COEFFICIENTS; REACTORS; TESTING

Optional Information

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