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Published 2005 | Version v1
Report

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

Part of:
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

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