Published November 1990
| Version v1
Report
PWR core fuel management code package
Description
In this paper a multi-dimensional multi-cycle PWR core fuel management code package is described. It can simulate and follow PWR nuclear power plant multi-cycle depletion behavior, and search for the optimal fuel loading pattern by means of optimization. We use the code package to predict first cycle core burnup behavior for a preliminarily designed PWR. Besides, with the package the burnup calculation of first and second cycle for Qinshan nuclear power plant has been performed. The result is in good agreement with that obtained by other code used in PWR design. (author). 3 refs, 4 figs, 2 tabs
Additional details
Publishing Information
- Imprint Title
- In-core fuel management practices. Proceedings of two technical committee meetings and workshops held in Madrid, 12-15 July 1988, and Vienna, 4-7 December 1989
- Imprint Pagination
- 438 p.
- Journal Page Range
- p. 175-181.
- Report number
- IAEA-TECDOC--567
Conference
- Title
- Technical committee meeting and workshop on in-core fuel management.
- Dates
- 4-7 Dec 1989.
- Place
- Vienna (Austria).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22023365
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FUEL ASSEMBLIES; FUEL MANAGEMENT; M CODES; NEUTRON FLUX; OPTIMIZATION; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CORES
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS