Role and approach to the recriticality elimination with utilizing the in-pile test reactor of the IGR research graphite reactor
Creators
- 1. The Japan Atomic Power Company, Tokyo (Japan)
- 2. Tokyo Electric Power Company, Tokyo (Japan)
- 3. FBR Engineering Co., Ltd., Tokyo (Japan)
- 4. Advanced Reactor Technology Co., Ltd., Tokyo (Japan)
- 5. Power Reactor and Nuclear Fuel Development Corporation (Japan)
- 6. Tokyo Institute of Technology (Japan)
Description
A basic concept of the recriticality-free core is to prevent any large-scale molten fuel compaction that might induce super-prompt criticality and this is achieved by assuring sufficient early fuel discharge from the core in case of fuel melting. For this purpose, a function of Controlled Material Relocation (CMR) is required, when the fuel assembly becomes molten and begins to propagate to the neighboring subassemblies. A simples design to realize CMR is proposed as FAIDUS, i.e., Fuel Assembly with Inner Duct Structure, core concept, where the inner duct has a role to enhance the axial discharge capability of molten fuel from the core. The advantage of FAIDUS is that the behavior of molten fuel discharge can be rather one-dimensional and thus this mechanism can be demonstrated in the experiment
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29067937.pdf
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Additional details
Publishing Information
- Publisher
- Sigma
- Imprint Place
- Kurchatov (Kazakhstan)
- Imprint Title
- 2. International conference on non-proliferation problems. Abstracts of reports
- Imprint Pagination
- 291 p.
- Journal Page Range
- p. 57-58
- Report number
- INIS-KZ--018
Conference
- Title
- 2. International conference on non-proliferation problems
- Dates
- 14-17 Sep 1998
- Place
- Kurchatov (Kazakhstan)
INIS
- Country of Publication
- Kazakhstan
- Country of Input or Organization
- Kazakhstan
- INIS RN
- 29067937
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICALITY; FBR TYPE REACTORS; FUEL ASSEMBLIES; KAZAKHSTAN; MELTDOWN; REACTOR CORE DISRUPTION; REACTOR SAFETY EXPERIMENTS
- Descriptors DEC
- ACCIDENTS; ASIA; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; REACTOR ACCIDENTS; REACTORS
Optional Information
- Notes
- Imprint:Russian and Kazak versions of this document are also included as part of this report