Passive safety features of a bottom-supported fast breeder reactor vessel
- Toshiba Corp., 8 Shin-Sugita, Isogo-ku, Yokohama, Kanagawa 235 (JP)
- Bechtel Group, Inc., San Francisco, CA (United States)
- Japan Atomic Power Co., Tokyo (Japan)
In this paper a system dynamics analysis is applied to a pool-type fast breeder reactor to examine the influence of a bottom-supported reactor vessel (BSRV) design on anticipated transient without scram (ATWS) events such as an unprotected loss of flow (ULOF), an unprotected loss of heat sink (ULOHS), and an unprotected transient overpower (UTOP) by using the ARGO safety analysis code. The BSRV enhances negative feedback because of the differential displacement between the core and the control rod as compared with a top-supported reactor vessel. In particular, the BSRV has the potential, especially in a mixed-oxide-fueled core, to mitigate the design requirements to prevent boiling of the coolant during an ULOF and ULOHS through the elongation of the primary flow coastdown and enhancement of the axial expansion of the control rod drive line. In the metallic-fueled core, the effects of the BSRV on the ATWS events are diminished by the limitation of the sodium temperature increase.
- OSTI ID:
- 7255184
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 99:3; ISSN NUTYB; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
ATWS
BREEDER REACTORS
CONTAINERS
DESIGN
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FEEDBACK
FUELS
HEAT SINKS
LOSS OF FLOW
MATERIALS
METALS
NUCLEAR FUELS
POOL TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
SINKS
SODIUM
TEMPERATURE DEPENDENCE
TRANSIENT OVERPOWER ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS