Development and benchmarking of the DYN3D/RELAP5 code system
- 1. Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation)
- 2. Forschungszentrum Rossendorf e.V. (FZR), Dresden (Germany)
Description
The integration of advanced computer codes from different safety analysis areas into code systems of expanded modeling capabilities results in a more detailed and accurate representation of reactor plant structural components. Less conservative predictions of advanced codes are needed to represent the transient behavior of advanced fuels (inert-matrix fuels or IMFs) being developed for burning the plutonium in thermal reactors and/or for improving the safety features of LWRs. IPPE is participating in domestic and international research programs on advanced reactor concepts based on new fuel types for LWRs. These programs cover both fuel technology and analytical tool development areas and, as one of their aspects, envisages elaboration of the interface for coupling the US system code RELAP5/MOD3 and the German 3-dimensional neutron kinetics code DYN3D. As a result of the joint FZR-IPPE research project, the coupled code system DYN3D/RELAP5 has been developed. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2001. Tagungsband
Publishing Information
- Publisher
- Inforum
- Imprint Place
- Bonn (Germany)
- Imprint Title
- Annual meeting on nuclear technology 2001. Proceedings
- Imprint Pagination
- 734 p.
- Journal Page Range
- p. 15-18
- ISSN
- 0720-9207
Conference
- Title
- 2001 annual meeting on nuclear technology
- Original Conference Title
- Jahrestagung Kerntechnik (JK) 2001
- Dates
- 15-17 May 2001
- Place
- Dresden (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 32052345
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; D CODES; KINETICS; NEUTRON TRANSPORT; R CODES; REACTOR PHYSICS; SAFETY ANALYSIS; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; NEUTRAL-PARTICLE TRANSPORT; PHYSICS; RADIATION TRANSPORT
Optional Information
- Notes
- 4 refs. Imprint:Jahrestagung Kerntechnik 2001. Tagungsband