Published November 1993
| Version v1
Miscellaneous
A review of the history-based local parameter methodology for simulating CANDU reactor cores
Creators
- 1. Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations
Description
The history-based local-parameter methodology represents a fundamental refinement in the evaluation of nuclear lattice properties in core-tracing simulations for CANDU reactors. This paper reviews the basis, development, and advantages of the history-based methodology. The totally new feature of the method is that fuel tables are not calculated. Instead, a cell calculation is carried out for every single fuel bundle in core over the small irradiation increment associated with the specific bundle and the core-tracking time step simulated. 5 refs., 4 figs
Additional details
Publishing Information
- ISBN
- 0-919784-34-8
- Imprint Title
- INC93: international nuclear congress. Proceedings. V. 1,2,3
- Imprint Pagination
- [1500 p.].
- Journal Page Range
- (v.3) [8 p.].
- Report number
- INIS-mf--14809
Conference
- Title
- international nuclear congress.
- Acronym
- INC93
- Dates
- 3-6 Oct 1993.
- Place
- Toronto, ON (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 27056942
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; FISSION PRODUCTS; FUEL MANAGEMENT; P CODES; REACTOR CORES; REACTOR LATTICE PARAMETERS; REACTOR PHYSICS
- Descriptors DEC
- COMPUTER CODES; HEAVY WATER MODERATED REACTORS; ISOTOPES; MANAGEMENT; MATERIALS; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; PRESSURE TUBE REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS