Published 1994
| Version v1
Book
Influence of neutron data uncertainties on accuracy of prediction of advanced reactor characteristics
Creators
- 1. Institute of Physics and Power Engineering, Obninsk (Russian Federation)
Description
Different sources of uncertainties caused by different nuclear cross sections are analyzed for a few types of advanced reactors: the BN-800 FBR core, advanced FBR core with Pb-Bi coolant, modular FBR core with U-Pu and U-Th fuel, HCLWR lattices. Estimations have been made with help of the INDECS System of Codes and Archives. Constructed convariance matrices of uncertainties of the ABB-90 group constants were used for estimation of accuracy of prediction of the most important neutronics characteristics of advanced reactor cores
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Title
- Proceedings of the international conference nuclear data for science and technology. Volume 2
- Imprint Pagination
- 571 p.
- Journal Page Range
- p. 993-999.
Conference
- Title
- nuclear data for the twenty-first century.
- Acronym
- International conference on nuclear data for science and technology
- Dates
- 9-13 May 1994.
- Place
- Gatlinburg, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26067219
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BN-800 REACTOR; CALCULATION METHODS; CROSS SECTIONS; NEUTRON REACTIONS; REACTOR KINETICS
- Descriptors DEC
- BARYON REACTIONS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HADRON REACTIONS; KINETICS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; NUCLEAR REACTIONS; NUCLEON REACTIONS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS