International review on safety requirements for the prototype fast breeder reactor "Monju" (Translated document)
Description
In response to the lessons learned from the serious nuclear accidents at the TEPCO's Fukushima Daiichi Nuclear Power Stations, an advisory committee, which was set up by the Japan Atomic Energy Agency, issued the report "Safety Requirements Expected to the Prototype Fast Breeder Reactor Monju" taking into account the SFR specific safety characteristics in July 2014. The report was reviewed by the leading international experts on SFR safety from five countries and one international organization in order to obtain independent and objective evaluation. The international review comments on each subsection were collected and compiled, and then a summary of results was derived through the discussion at the review meeting and individual feedbacks. As a result the basic concept for prevention of severe accidents and mitigation of their consequences of Monju is appropriate in consideration of SFR specific safety characteristics, and is in accordance with international common understanding. (author)
Availability note (English)
Available from JAEA; DOI: https://doi.org/10.11484/jaea-review-2015-029
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 58 p.
- Report number
- JAEA-Review--2015-029
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48077121
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Translation
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; ATWS; CONTAINMENT BUILDINGS; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; MONJU REACTOR; NUCLEAR FUELS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR CORE DISRUPTION; REACTOR SHUTDOWN; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BREEDER REACTORS; BUILDINGS; CALCULATION METHODS; CONTAINMENT; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTOR SITES; REACTORS; REMOVAL; SEVERE ACCIDENTS; SHUTDOWN; SODIUM COOLED REACTORS; THERMAL POWER PLANTS
Optional Information
- Notes
- Translated from JAEA-Evaluation-2015-013; 1 ref., 1 tab.; This record replaces 47091315