Development of a multicell methodology to account for heterogeneous core effects in the core-analysis diffusion code
Creators
- 1. Atomic Energy of Canada Limited, 2251 Speakman Drive, Mississauga, Ont. L5K 1B2 (Canada)
Description
In CANDU R reactor calculations, the lattice-cell cross sections are calculated with WIMS-AECL, and the three-dimensional core neutron-flux and power distributions are calculated with RFSP-IST. The lattice-cell cross sections employed in RFSP-IST and in many other commercial core-analysis diffusion codes are usually based on the use of single-lattice-cell calculations, without considering the effects of the environment. This approximation is not sufficiently accurate for heterogeneous core configurations in the ACR-1000TM. A multicell correction method is therefore developed in RFSP-IST to account for heterogeneous core effects in the design and analysis of ACR-1000. The calculation results show that the multicell methodology developed in RFSP-IST is effective, generic, and it works well for ACR core analysis. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 10 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43130086
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- APPROXIMATIONS; ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; COMPUTER CODES; CORRECTIONS; CROSS SECTIONS; DESIGN; HETEROGENEOUS REACTOR CORES; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; POWER DISTRIBUTION; REACTOR LATTICES; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CALCULATION METHODS; CANADIAN ORGANIZATIONS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; HEAVY WATER MODERATED REACTORS; NATIONAL ORGANIZATIONS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR CORES; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 9 refs.