Published June 13, 1997
| Version v1
Journal article
Development of CANDU reactor physics calculation system based on WIMS code
- 1. Institute for Nuclear Research, Pitesti (Romania)
Description
A comparison of global reactor parameters obtained by two different methodologies is considered in this paper. The classical CANDU methodology (experimental adjusted) and an alternative calculation system are used. The last is based on WIMS code, PIJXYZ - a 3D integral transport code and DIREN - a 3D diffusion code. Both these codes are PC versions that provide good portability, an easier path to develop new versions. PIJXYZ and DIREN have been developed for CANDU reactor type analysis. The results show fair agreement between CANDU benchmark predictions and our codes system estimations. (author)
Additional details
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 24
- Journal Issue
- 14
- Journal Page Range
- p. 1105-1125.
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 28057339
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CALCULATION METHODS; CANDU TYPE REACTORS; D CODES; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; P CODES; REACTOR KINETICS; THREE-DIMENSIONAL CALCULATIONS; W CODES
- Descriptors DEC
- COMPUTER CODES; HEAVY WATER MODERATED REACTORS; KINETICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; TRANSPORT THEORY