Recent improvements in PSU-LEOPARD/MCRAC code package
Creators
- 1. Institut Rudjer Boskovic, Zagreb (Yugoslavia)
- 2. Faculty of Electrical Engineering, Zagreb (Yugoslavia)
Description
The PSU-LEOPARD/MCRAC code package was benchmarked against operational data of the first three cycles of the Yugoslav NPP Krsko reactor and used to determine the loading pattern for cycle 4. As the NPP Krsko switched to low leakage cores, modifications were made in the PSU-LEOPARD code to model classical burnable absorbers as well as integral fuel burnable absorbers. Changes were also made in the MCRAC code: to provide a fast and convenient fuel assembly interchange for loading pattern search; to calculate local power peaking factors; to print out core map with all the relevant data in a self-explanatory form; to automatise mesh definition; to convert the code to FORTRAN 77 standard. Further development, now in progress, will enable: following quarter-assembly burnups: more accurate local peaking factor determination; thermal hydraulic feedback modeling; conversion of the code package for PC. The described improvements will make this code package a reliable tool in loading pattern determination. (author). 13 refs, 6 figs
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. 32-39.
- Report number
- IAEA-TECDOC--567
Conference
- Title
- Technical committee meeting and workshop on improvements of in-core fuel management codes.
- Dates
- 12-15 Jul 1988.
- Place
- Madrid (Spain).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22023353
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNABLE POISONS; BURNUP; FUEL MANAGEMENT; FUEL RODS; KRSKO REACTOR; MODIFICATIONS; P CODES; POWER DISTRIBUTION; REACTOR CORES; VERIFICATION
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MANAGEMENT; MATERIALS; NEUTRON ABSORBERS; NUCLEAR MATERIALS MANAGEMENT; NUCLEAR POISONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS