Published 1991
| Version v1
Report
Open
Study on large FBR core optimization to enhance core safety
- 1. Mitsubishi Atomic Power Industries Inc., Shiba-koen, Minato-ku, Tokyo (Japan)
Description
A design study has been made on high burnup and large sized FBR cores which mitigate the consequences of unprotected accidents. The reactivity feedbacks due to the core radial expansion, the sodium density change and the Doppler effect have significant influence on the maximum coolant temperature in the unprotected loss of flow event. The excess reactivity is also an important parameter for the safety in the unprotected transient over-power event. As the results of sensitivity analysis, a pancake-shaped and low power density core concept is proposed which offers effectively enhanced safety. (author)
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31042194.pdf
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Additional details
Publishing Information
- Imprint Title
- Specialists' meeting on passive and active safety features of LMFRs
- Imprint Pagination
- 253 p.
- Journal Page Range
- p. 244-249
- Report number
- IWGFR--85
Conference
- Title
- IAEA-IWGFR specialists' meeting on passive and active safety features of LMFRs
- Dates
- 5-7 Nov 1991
- Place
- Oarai, Ibaraki (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31042194
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FBR TYPE REACTORS; LOSS OF FLOW; POWER DENSITY; REACTIVITY COEFFICIENTS; REACTOR CORE RESTRAINTS; SENSITIVITY ANALYSIS; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; ENGINEERED SAFETY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; RESTRAINTS
Optional Information
- Notes
- 3 refs, 7 figs, 5 tabs