Published October 2003
| Version v1
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Preparation and testing ORIGEN-ARP library for VVER fuel design
- 1. State Scientific and Technical Centre on Nuclear and Radiation Safety, Kyiv (Ukraine)
Description
The main results of neutron-physical constant libraries preparing and testing for assessment VVER reactors spent fuel isotope composition with the SCALE control module ORIGEN-ARP are presented in this report. The libraries were tested on the basis of the comparison between the calculation results with the experimental data, and with the calculation benchmarks. It should be mentioned that the particular attention was paid to important in the view of criticality analysis isotopes that are contained in the spent nuclear fuel. (author)
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Additional details
Publishing Information
- Imprint Title
- ICNC2003: Proceedings of the seventh international conference on nuclear criticality safety. Challenges in the pursuit of global nuclear criticality safety
- Imprint Pagination
- 486 p.
- Journal Page Range
- p. 721-726
- Report number
- JAERI-Conf--2003-019-PT2
Conference
- Title
- 7. international conference on nuclear criticality safety. Challenges in the pursuit of global nuclear criticality safety
- Acronym
- ICNC2003
- Dates
- 20-24 Oct 2003
- Place
- Tokai, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36116546
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNUP; CRITICALITY; DESIGN; FISSION PRODUCTS; FUEL ASSEMBLIES; O CODES; S CODES; SAFETY; SPENT FUELS; WWER TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; POWER REACTORS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 14 refs., 4 figs., 3 tabs.; This record replaces 35060921