Results of transient analyses of the MOSART Molten Salt Reactor design
Creators
- 1. Institute for Reactor Safety, Forschungszentrum Karlsruhe, Technik und Umwelt GmbH, Karlsruhe (Germany)
Description
The major characteristics of the Molten Salt Reactor are presented and examples of the activities in this area are given. MOSART kinetic data is presented. Transients recommended to be analysed for MOSART Molten Salt Reactor Concept are established and some limitations to be considered are outlined. Preliminary observations that can be made as regards the MOSART Molten Salt concepts are: 1. the critical MOSART design is immune to most unprotected transients except the UTOP transient (fuel agglomeration issue in piping system). 2. If fuel agglomeration issue should be an issue, we need to a). assess how large (in terms of reactivity) potential fuel particles could be, b). if fuel particles are below 300 pcm then design should be a 'critical' design. c). if fuel particles can be in excess of 500 pcm, then should consider core design to be 'sub-critical'. 3. If reactor design is 'sub-critical', then must be aware that the transient characteristics of sub-critical systems is less favourable to most unprotected transients in comparison to protected transients
Additional details
Publishing Information
- Imprint Title
- Technical Meeting (Research Coordination Meeting) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'. Working material
- Imprint Pagination
- 524 p.
- Journal Page Range
- p. 281-293
- Report number
- TWG-FR--124
Conference
- Title
- Technical meeting (Research Coordination Meeting) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'
- Dates
- 22-26 Nov 2004
- Place
- Hefei (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37062907
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGGLOMERATION; COMPARATIVE EVALUATIONS; DESIGN; FUEL PARTICLES; MOLTEN SALT REACTORS; MOLTEN SALTS; NUCLEAR FUELS; REACTIVITY; TRANSIENTS
- Descriptors DEC
- ENERGY SOURCES; EVALUATION; FUELS; MATERIALS; REACTOR MATERIALS; REACTORS; SALTS
Optional Information
- Notes
- Published as Power Point presentation only
- Secondary number(s)
- IAEA-RC--870.2