Published October 1999
| Version v1
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Project of molten salt reactor for spent fuel transmutation. Neutron-physical characteristics: models and calculations
- 1. Russian Research Center 'Kurchatov Institute', Nuclear Reactor Institute, Department of physical and Technical Researches of Advanced Reactors (Russian Federation)
Description
A brief review of the codes available for the neutron-physical calculations of the heterogeneous nuclear reactors and critical assemblies is presented. These program can be used for simulation of the reactor part in the Accelerator Driven Transmutation Technology for Molten salt reactor Projects. Present review describes the programs that do not use empirical coefficients typical for the existing engineering program complexes intended for the calculation of thermal reactors. This is particularly important for the calculation of the non-standard situations in reactor as well as for designing the new reactor concepts. (Authors)
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Additional details
Publishing Information
- Publisher
- Kiadja and KFKI Atomenergia Kutato Intezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 963-372-616-6
- Imprint Title
- Proceedings of the ninth Symposium of Atomic Energy Research
- Imprint Pagination
- [780 p.]
- Journal Page Range
- p. 761-770
- Report number
- INIS-SK--00-027
Conference
- Title
- 9. Symposium of Atomic Energy Research
- Dates
- 4-8 Oct 1999
- Place
- Demanovska Dolina (Slovakia)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Slovakia
- INIS RN
- 31062493
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CROSS SECTIONS; DESIGN; HETEROGENEOUS REACTOR CORES; MOLTEN SALT REACTORS; MONTE CARLO METHOD; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; REACTOR CELLS; SIMULATION; SPENT FUELS; TRANSMUTATION
- Descriptors DEC
- CALCULATION METHODS; ENERGY SOURCES; FUELS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUELS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR CORES; REACTOR MATERIALS; REACTORS
Optional Information
- Notes
- 25 refs. Imprint:Additional corporate organizations: NPP Kozloduy, Kozloduy (Bulgaria); NPP Bohunice, Jaslovske Bohunice (Slovakia); Nuclear Power Plants Research Institute Trnava Inc., 918 64 Trnava (Slovakia); Forschungszentrum Rossendorf, Institute of Safety Research, D-01314 Dresden (Germany); Energoprojekt Praha a.s., 140 21 Praha 4 (Czech Republic); VTT Energy, Technical Research Centre of Finland, P.O.Box 1604, FIN-02044 VTT (Finland); RRC 'Kurchatov Institute', Moscow (Russian Federation); Nuclear Technology Center, Higher Institute of Nuclear Science and Technology (Cuba); Mochovce NPP, Mochovce (Slovakia)