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Preparation of Criticality Benchmark Data for the Validation of Neutronic Calculation Method

Research Project

Project/Area Number 17560743
Research Category

Grant-in-Aid for Scientific Research (C)

Allocation TypeSingle-year Grants
Section一般
Research Field Nuclear engineering
Research InstitutionKyoto University

Principal Investigator

NAKAJIMA Ken  Kyoto University, Research Reactor Institute, Professor (60355047)

Co-Investigator(Kenkyū-buntansha) UNESAKI Hironobu  Kyoto University, Research Reactor Institute, Professor (40213467)
Project Period (FY) 2004 – 2007
Project Status Completed (Fiscal Year 2007)
Budget Amount *help
¥2,880,000 (Direct Cost: ¥2,700,000、Indirect Cost: ¥180,000)
Fiscal Year 2007: ¥780,000 (Direct Cost: ¥600,000、Indirect Cost: ¥180,000)
Fiscal Year 2006: ¥500,000 (Direct Cost: ¥500,000)
Fiscal Year 2005: ¥1,600,000 (Direct Cost: ¥1,600,000)
KeywordsNuclear energy / Validation of neutronic calculation method / Critical experiment / Benchmark / KUCA / ベンチマークデータ / 核計算手法 / 熱中性子スペクトル / PCクラスター
Research Abstract

Benchmark data of critical systems have been prepared for the validation of the neutronic calculation method. At first, a parallel computer system using PC cluster was constructed and the calculation code systems were installed. Then, the standard cores for benchmark calculations were selected from the KUCA and TCA experiments, and the following evaluations were conducted.
・Chemical analyses of polyethylene and aluminum, which are the core components, were performed, and the accuracy of KUCA critical experiments was evaluated using the errors of core componentsetc. Then, the benchmark calculation model was developed for the validation of calculation methods. Consequently, the accuracy of nuclear data was evaluated by using the developed model.
・The experimental errors of criticality for TCA's MOX cores and the effective delayed neutron fraction for uranium cores were evaluated, and the benchmark data for those cores were prepared. Using these data, the benchmark analyses were conducted to evaluate the nuclear data libraries.
・Based on the above results, the neutronic analysis method for KUR core was investigated, and the benchmark evaluation using the experimental data of highly enriched uranium cores was conducted. Then, the prediction evaluation for the low enriched uranium cores was performed. This evaluation confirms that the safe operation can be performed with the low enriched uranium cores.

Report

(4 results)
  • 2007 Annual Research Report   Final Research Report Summary
  • 2006 Annual Research Report
  • 2005 Annual Research Report
  • Research Products

    (7 results)

All 2008 2006

All Presentation (7 results)

  • [Presentation] Nuclear Characteristics Evaluation for Kyoto University Research React or with Low-Enriched Uranium Core2008

    • Author(s)
      中島健、宇根崎博信
    • Organizer
      炉物理国際会議PHYSOR'08 (International Conference on the Physics of Reactors)
    • Place of Presentation
      スイス・インターラーケン市
    • Year and Date
      2008-09-17
    • Related Report
      2007 Annual Research Report
  • [Presentation] Nuclear characteristics evaluation for Kyoto University Research Reactor with low-enriched uranium core2008

    • Author(s)
      Ken Nakajima, Hironobu Unesaki
    • Organizer
      Int. Conf. on Physics of Reactors (PHYSOR08), "Nuclear Power : A Sustainable Resource"
    • Place of Presentation
      Interlaken, Switzerland
    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2007 Final Research Report Summary
  • [Presentation] Nuclear characteristics evaluation for Kyoto University Research Reactor with low-enriched uranium core2008

    • Author(s)
      Ken Nakajima, Hironobu Unesaki
    • Organizer
      Proc. Int. Conf. on Physics of Reactors (PHYSOR08), "Nuclear Power: A Sustainable Resource"
    • Place of Presentation
      Interlaken, Switzerland
    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2007 Final Research Report Summary
  • [Presentation] On the Analysis Method of Effective Delayed Neutron Fraction at Thermal Neutron Systems2006

    • Author(s)
      Ken Nakajima, Hironobu Unesaki
    • Organizer
      PHYSOR-2006, American Nuclear Society's Topical Meeting on Reactor Physics
    • Place of Presentation
      Vancouver, Canada
    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2007 Final Research Report Summary
  • [Presentation] Criticality Analysis of Uranium Fueled Thermal Spectrum Cores of Kyoto University Critical Assembly using JENDL-3.3, ENDF/B-VI. 8 and JEFF3.1 Libraries2006

    • Author(s)
      Hironobu Unesaki, et al.
    • Organizer
      PHYSOR-2006, American Nuclear Society's Topical Meeting on Reactor Physics
    • Place of Presentation
      Vancouver, Canada
    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2007 Final Research Report Summary
  • [Presentation] On the Analysis Method of Effective Delayed Neutron Fraction at Thermal Neutron Systems2006

    • Author(s)
      Ken Nakajima, Hironobu Unesaki
    • Organizer
      Proc. PHYSOR-2006, American Nuclear Society's Topical Meeting on Reactor Physics
    • Place of Presentation
      Vancouver, Canada
    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2007 Final Research Report Summary
  • [Presentation] Criticality Analysis of Uranium Fueled Thermal Spectrum Cores of Kyoto University Critical Assembly using JENDL-3.3, ENDF/B-VI. 8 and JEFF3.1 Libraries2006

    • Author(s)
      Hironobu Unesaki, et al.
    • Organizer
      Proc. PHYSOR-2006, American Nuclear Society's Topical Meeting on Reactor Physics
    • Place of Presentation
      Vancouver, Canada
    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2007 Final Research Report Summary

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Published: 2005-04-01   Modified: 2016-04-21  

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