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

Mizuno, Tomoyasu; Niwa, Hajime

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

Sodium-cooled mixed-oxide core design studies are performed with a target burnup of 150 GWd/t and possible measures against the recriticality issues in core disruptive accidents. Four types of core are compared from the viewpoints of core performance and reliability. Results show that all the types of core satisfy the target and that a homogeneous core with an axial blanket partial elimination subassembly is the superior concept, although experimental demonstration is required of molten fuel motion for mitigation of recriticality following fuel melting and loss of fuel pin integrity.

Authors:

Mizuno, Tomoyasu; Niwa, Hajime ^[1]

Japan Nuclear Cycle Development Institute (Japan)

Publication Date:: Sat May 15 00:00:00 EDT 2004

OSTI Identifier:: 20837852

Resource Type:: Journal Article

Journal Name:: Nuclear Technology

Additional Journal Information:: Journal Volume: 146; Journal Issue: 2; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0029-5450

Country of Publication:: United States

Language:: English

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

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                    Mizuno, Tomoyasu, and Niwa, Hajime. 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., 2004. 
        Web.

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                    Mizuno, Tomoyasu, & Niwa, Hajime. 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, Tomoyasu, and Niwa, Hajime. 2004.  
        "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_20837852,

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

  author       = {Mizuno, Tomoyasu and Niwa, Hajime},

  abstractNote = {Sodium-cooled mixed-oxide core design studies are performed with a target burnup of 150 GWd/t and possible measures against the recriticality issues in core disruptive accidents. Four types of core are compared from the viewpoints of core performance and reliability. Results show that all the types of core satisfy the target and that a homogeneous core with an axial blanket partial elimination subassembly is the superior concept, although experimental demonstration is required of molten fuel motion for mitigation of recriticality following fuel melting and loss of fuel pin integrity.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/20837852},
  journal      = {Nuclear Technology},

  issn         = {0029-5450},

  number       = 2,

  volume       = 146,

  place        = {United States},

  year         = {Sat May 15 00:00:00 EDT 2004},

  month        = {Sat May 15 00:00:00 EDT 2004}

}

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