Comparison of oxide- and metal-core behavior during CRBRP (Clinch River Breeder Reactor Plant) station blackout

Polkinghorne, S T; Atkinson, S A

Title: Comparison of oxide- and metal-core behavior during CRBRP (Clinch River Breeder Reactor Plant) station blackout

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Abstract

A resurrected concept that could significantly improve the inherently safe response of Liquid-Metal cooled Reactors (LMRs) during severe undercooling transients is the use of metallic fuel. Analytical studies have been reported on for the transient behavior of metal-fuel cores in innovative, inherently safe LMR designs. This paper reports on an analysis done, instead, for the Clinch River Breeder Reactor Plant (CRBRP) design with the only innovative change being the incorporation of a metal-fuel core. The SSC-L code was used to simulate a protected station blackout accident in the CRBRP with a 943 MWt Integral Fast Reactor (IFR) metal-fuel core. The results, compared with those for the oxide-fueled CRBRP, show that the margin to boiling is greater for the IFR core. However, the cooldown transient is more severe due to the faster thermal response time of metallic fuel. Some additional calculations to assess possible LMR design improvements (reduced primary system pressure losses, extended flow coastdown) are also discussed. 8 refs., 13 figs., 2 tabs.

Authors:: Polkinghorne, S T; Atkinson, S A

Publication Date:: Wed Jan 01 00:00:00 EST 1986

Research Org.:: EG and G Idaho, Inc., Idaho Falls (USA)

OSTI Identifier:: 5934119

Report Number(s):: EGG-M-01086; CONF-860906-28
ON: DE88001601

DOE Contract Number:: AC07-76ID01570

Resource Type:: Conference

Resource Relation:: Conference: Advances in reactor physics and safety meeting, Saratoga Springs, NY, USA, 17 Sep 1986; Other Information: Portions of this document are illegible in microfiche products

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CLINCH RIVER BREEDER REACTOR; BLACKOUTS; LOSS OF FLOW; REACTOR CORES; REACTOR SAFETY; HEAT TRANSFER; HYDRAULICS; NATURAL CONVECTION; S CODES; THEORETICAL DATA; TRANSIENTS; ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; CONVECTION; DATA; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; INFORMATION; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MASS TRANSFER; MECHANICS; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SODIUM COOLED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding

Citation Formats


                    Polkinghorne, S T, and Atkinson, S A. Comparison of oxide- and metal-core behavior during CRBRP (Clinch River Breeder Reactor Plant) station blackout.  United States: N. p., 1986. 
        Web.

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                    Polkinghorne, S T, & Atkinson, S A. Comparison of oxide- and metal-core behavior during CRBRP (Clinch River Breeder Reactor Plant) station blackout.  United States.

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                    Polkinghorne, S T, and Atkinson, S A. 1986.  
        "Comparison of oxide- and metal-core behavior during CRBRP (Clinch River Breeder Reactor Plant) station blackout".  United States.  https://www.osti.gov/servlets/purl/5934119.

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@article{osti_5934119,

  title        = {Comparison of oxide- and metal-core behavior during CRBRP (Clinch River Breeder Reactor Plant) station blackout},

  author       = {Polkinghorne, S T and Atkinson, S A},

  abstractNote = {A resurrected concept that could significantly improve the inherently safe response of Liquid-Metal cooled Reactors (LMRs) during severe undercooling transients is the use of metallic fuel. Analytical studies have been reported on for the transient behavior of metal-fuel cores in innovative, inherently safe LMR designs. This paper reports on an analysis done, instead, for the Clinch River Breeder Reactor Plant (CRBRP) design with the only innovative change being the incorporation of a metal-fuel core. The SSC-L code was used to simulate a protected station blackout accident in the CRBRP with a 943 MWt Integral Fast Reactor (IFR) metal-fuel core. The results, compared with those for the oxide-fueled CRBRP, show that the margin to boiling is greater for the IFR core. However, the cooldown transient is more severe due to the faster thermal response time of metallic fuel. Some additional calculations to assess possible LMR design improvements (reduced primary system pressure losses, extended flow coastdown) are also discussed. 8 refs., 13 figs., 2 tabs.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/5934119},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Wed Jan 01 00:00:00 EST 1986},

  month        = {Wed Jan 01 00:00:00 EST 1986}

}

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