Advanced MOX Core Design Study of Sodium Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan

Mizuno, T; Niwa, H

Title: Advanced MOX Core Design Study of Sodium Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan

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Abstract

The Sodium cooled MOX core design studies are performed with the target burnup of 150 GWd/t and measures against the recriticality issues in core disruptive accidents (CDAs). Four types of core are comparatively studied in viewpoints of core performance and reliability. Result shows that all the types of core satisfy the target and that the homogeneous core with axial blanket partial elimination subassembly is the most superior concept in case the effectiveness of measures against recriticality issues by the axial blanket partial elimination is assured. (authors)

Authors:

Mizuno, T; Niwa, H ^[1]

Japan Nuclear Cycle development institute, O-arai Engineering Center, 4002 Narita-cho, O-arai-machi, Higashi-ibaraki-gun, Ibaraki-ken, 311-1393 (Japan)

Publication Date:: Mon Jul 01 00:00:00 EDT 2002

Research Org.:: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)

OSTI Identifier:: 21167856

Resource Type:: Conference

Resource Relation:: Conference: ICAPP'02: 2002 International congress on advances in nuclear power plants, Hollywood, FL (United States), 9-13 Jun 2002; Other Information: Country of input: France; 4 refs

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNUP; DESIGN; FAST REACTORS; FEASIBILITY STUDIES; PERFORMANCE; REACTOR CORE DISRUPTION; RELIABILITY; SODIUM; SODIUM COOLED REACTORS

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                    Mizuno, T, and Niwa, H. Advanced MOX Core Design Study of Sodium Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan.  United States: N. p., 2002. 
        Web.

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                    Mizuno, T, & Niwa, H. Advanced MOX Core Design Study of Sodium Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan.  United States.

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                    Mizuno, T, and Niwa, H. 2002.  
        "Advanced MOX Core Design Study of Sodium Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan".  United States.

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@article{osti_21167856,

  title        = {Advanced MOX Core Design Study of Sodium Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan},

  author       = {Mizuno, T and Niwa, H},

  abstractNote = {The Sodium cooled MOX core design studies are performed with the target burnup of 150 GWd/t and measures against the recriticality issues in core disruptive accidents (CDAs). Four types of core are comparatively studied in viewpoints of core performance and reliability. Result shows that all the types of core satisfy the target and that the homogeneous core with axial blanket partial elimination subassembly is the most superior concept in case the effectiveness of measures against recriticality issues by the axial blanket partial elimination is assured. (authors)},

  doi          = {},

  url          = {https://www.osti.gov/biblio/21167856},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Mon Jul 01 00:00:00 EDT 2002},

  month        = {Mon Jul 01 00:00:00 EDT 2002}

}

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