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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Part of:
Specialists' meeting on passive and active safety features of LMFRs

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