Passive safety features of a bottom-supported fast breeder reactor vessel

Endo, H; Kumaoka, Y; Golan, S; Nakagawa, H

Title: Passive safety features of a bottom-supported fast breeder reactor vessel

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Abstract

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.

Authors:

Endo, H; Kumaoka, Y ^[1]; Golan, S ^[2]; Nakagawa, H ^[3]

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)

Publication Date:: Tue Sep 01 00:00:00 EDT 1992

OSTI Identifier:: 7255184

Resource Type:: Journal Article

Journal Name:: Nuclear Technology; (United States)

Additional Journal Information:: Journal Volume: 99:3; Journal ID: ISSN 0029-5450

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BREEDER REACTORS; REACTOR VESSELS; FAST REACTORS; POOL TYPE REACTORS; ATWS; DESIGN; FEEDBACK; HEAT SINKS; LOSS OF FLOW; METALS; NUCLEAR FUELS; REACTOR CORES; REACTOR SAFETY; SODIUM; TEMPERATURE DEPENDENCE; TRANSIENT OVERPOWER ACCIDENTS; ACCIDENTS; ALKALI METALS; CONTAINERS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SAFETY; SINKS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding

Citation Formats


                    Endo, H, Kumaoka, Y, Golan, S, and Nakagawa, H. Passive safety features of a bottom-supported fast breeder reactor vessel.  United States: N. p., 1992. 
        Web.

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                    Endo, H, Kumaoka, Y, Golan, S, & Nakagawa, H. Passive safety features of a bottom-supported fast breeder reactor vessel.  United States.

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                    Endo, H, Kumaoka, Y, Golan, S, and Nakagawa, H. 1992.  
        "Passive safety features of a bottom-supported fast breeder reactor vessel".  United States.

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@article{osti_7255184,

  title        = {Passive safety features of a bottom-supported fast breeder reactor vessel},

  author       = {Endo, H and Kumaoka, Y and Golan, S and Nakagawa, H},

  abstractNote = {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.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/7255184},
  journal      = {Nuclear Technology; (United States)},

  issn         = {0029-5450},

  number       = ,

  volume       = 99:3,

  place        = {United States},

  year         = {Tue Sep 01 00:00:00 EDT 1992},

  month        = {Tue Sep 01 00:00:00 EDT 1992}

}

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