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Study on Micro Reactor Physics for Improvement of Neutronics Calculation

Research Project

Project/Area Number 13480148
Research Category

Grant-in-Aid for Scientific Research (B)

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

Principal Investigator

TAKEDA Toshikazu  Osaka Univ., Graduate School of Engineering, Prof., 大学院・工学研究科, 教授 (30116058)

Co-Investigator(Kenkyū-buntansha) SHIROYA Seiji  Kyoto Univ., Research Reactor Institute, Prof., 原子炉実験所, 教授 (80027474)
KITADA Takanori  Osaka Univ., Graduate School of Engineering, res-assist, 大学院・工学研究科, 助手 (60263208)
YAMAMOTO Toshihisa  Osaka Univ., Graduate School of Engineering, Associ., 大学院・工学研究科, 助教授 (50273602)
YOSHIHIRO Yamane  Nagoya Univ., Graduate School of Engineering, Prof., 大学院・工学研究科, 教授 (60115649)
MISAWA Tsuyoshi  Kyoto Univ., Research Reactor Institute, Associ., 原子炉実験所, 助教授 (70219616)
Project Period (FY) 2001 – 2003
Project Status Completed (Fiscal Year 2003)
Budget Amount *help
¥9,900,000 (Direct Cost: ¥9,900,000)
Fiscal Year 2003: ¥2,400,000 (Direct Cost: ¥2,400,000)
Fiscal Year 2002: ¥2,600,000 (Direct Cost: ¥2,600,000)
Fiscal Year 2001: ¥4,900,000 (Direct Cost: ¥4,900,000)
KeywordsMicro Reactor Physics / Calculation Code / Theory / Collision Probability / Angular Distribution / Cells / Critical Experiment / Transient / ドップラー反応度係数 / 自己遮蔽 / 実効温度 / 温度分布 / 集合体 / 過渡解析 / 中性子束角度分布 / Critical experiment / KUCA / reaction rate / transient analysis / BWR / control rod / temperature / self-shielding / 燃料集合体 / CCCP法 / 時間依存 / ドップラー係数 / 反応度フィードバック / 飛び出し / 制御棒
Research Abstract

1)
We have developed the theory for transient analysis with the consideration of Micro-reactor physics effect, and have developed the calculation code based on the developed theory. The current Coupling Collision probability method (CCCP method) is adopted in the developed theory because the CCCP method can strictly model the heterogeneity such as a pin cell structure in a fuel assembly and can treat the heterogeneity in calculating the effective cross sections: New CCCP method, which can treat the transient in time has been developed, because the conventional CCCP method does not consider the transient
2)
The analysis based on Micro-reactor physics shows that the angular distribution of neutron flux is greatly affected by the surrounding geometry and composition. Therefore, we considered the technique to measure the angular distribution of neutron flux in the core. The designed technique uses the optical fiber detector and Cd tube. The technique was applied to the measurement of the angular distribution in the core assembled in C-core tank at KUCA, and the technique was found to be effective to measure the angular distribution of neutron flux.
3)
The neutronics-thermodynamics coupling code has been developed to evaluate the effect of temperature distribution in fuel rods during the transient phenomena. The developed code was used to analyze the control rod drop accidents at the cold and hot stand-by states with the direct modeling of the heterogeneity of temperature distribution etc. in fuel rods. As the results, it is found that the analysis based on Micro-reactor physics is necessary and useful to consider the complex temperature distribution in fuel rods at a transient, and also the effective temperature model, which has a flat temperature distribution in fuel rods, bring the miscellaneous results because of the complex temperature, distribution.

Report

(4 results)
  • 2003 Annual Research Report   Final Research Report Summary
  • 2002 Annual Research Report
  • 2001 Annual Research Report
  • Research Products

    (52 results)

All Other

All Publications (52 results)

  • [Publications] 北田孝典, 竹田敏一, 山本章夫, 山崎正俊: "連続エネルギーモンテカルロ計算による燃料実効温度に関する検討"日本原子力学会2001年秋の大会. 470-470 (2001)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Tsuyoshi AMA, Hideaki HYOUDOU, Toshikazu TAKEDA: "Effect of Void Distribution within Fuel Assembly on Assembly Neutronic Characteristics"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 39・1. 90-100 (2002)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Hideaki IKEDA, Toshikazu TAKEDA: "Development and Verification of an Efficient Spatial Neutron Kinetics Method for Reactibity-Initiated Event Analyses"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 38・7. 492-502 (2002)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Takumi HORIUCHI, Tatsuya IWAMOTO, Masaaki MORI: "Advanced Nodal Methods and Applications to LWR Core Design and Analysis in Japan"(印刷中).

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Takanori KITADA: "Direction and Region Dependent Cross Sections for Use to MOX Fuel Analysis"(印刷中).

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA: "Micro-Reactor Physics of MOX-Fueled Core"(印刷中).

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Takanori KITADA: "Direction and Region Dependent Cross Sections for Use to MOX Fuel Analysis"Journal of NUCLEAR SCIENCE and TECHNOLOGY. Supplement2. 1057-1060 (2002)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Tsuyoshi AMA, Hideaki IKEDA, Shinya KOSAKA, Hideaki HYOUDOU, Toshikazu TAKEDA: "Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boling Water Reactor Cross"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 39・5. 487-498 (2002)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] 山本敏久, 竹田敏一: "仮想的粒子「ミサイロン」を使った中性子モンテカルロシミュレーション"日本原子力学会2002年秋の大会予稿集. 240 (2002)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] 山路和也, 竹田敏一: "ミクロ炉物理に基づく軽水炉部分"日本原子力学会2002年秋の大会予稿集. 242 (2002)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] 竹田敏一, 北田孝典: "ウラン及びプルトニウム燃料軽水炉格子におけるドップラー反応度係数の比較"日本原子力学会2002年秋の大会予稿集. 249 (2002)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] 竹田敏一 他: "今、なぜ、炉物理なのか?何がおもしろいのか?"日本原子力学会誌. 45・2. 85-111 (2003)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Hideaki HYOUDOU, Takanori Kitada: "EFFECT OF NONUNIFORM 3-D VOID DISTRIBUTION WITHIN BWR FUEL ASSEMBLIES ON NEUTRONIC CHARACTERISTICS"PROCEEDINGS 18^<th> International Conference on Transport Theory. 205-210 (2003)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] 竹田 敏一: "アイデアを生み出す炉物理"日本原子力学会誌. 45・7. 424-427 (2003)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Tadashi Ushio, Toshikazu Takeda: "The Characteristics and Subgroup Methods in Square Light Water Reactor Cell Calculations"NUCLEAR SCIENCE AND ENGINEERING. 144. 61-80 (2003)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Tadashi USHIO, Toshikazu TAKEDA, Masaaki MORI: "Neutron Anisotropic Scattering in Heterogeneous Cell Calculations of Light Water Reactors"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 40・7. 464-480 (2003)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Kazuya YAMAJI, Akiko SAWADA: "TRANSIENTANAL OF NEUTRONIC BEHAVIOR IN FUEL ASSEMBLIES BASED ON MICRO REACTOR PHYSICS"International Conference on Supercomputing in Nuclear Applications SNA'2003. 27 (2003)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Yzuru HAMADA, Takanori KITADA: "3D Transport Theory Method Based on MOC for Analyzing Integral Data of Transmutation"Global2003. 1005-1010 (2003)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Takanori KITADA, Toshikazu TAKEDA, Akiko Yamamoto, Masatoshi Yamasaki: "Effective Temperature by Contimuous Energy Monte Carlo Method"ATOMIC ENERGY SOCIETY OF JAPAN 2001 AESJ2001 FALL MEETING. 470. (2001)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Tsuyoshi AMA, Hideaki HYOUDOU, Toshikazu TAKEDA: "Effect of Void Distribution within Fuel Assembly on Assembly Neutronic Characteristics"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 39・1. 90-100 (2002)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Hideaki IKEDA, Toshikazu TAKEA: "Development and Verification of an Efficient Spatial Neutron Kinetics Method for Reactibity-Initiated Event Analyses"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 38・7. 492-502 (2002)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Takumi HORIUCHI, Tatsuya IWAMOTO, Masaaki MORI: "Advanced Nodal Methods and Applications to LWR Core Design and Analysis in Japan"(in press).

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Takanori KITADA: "Direction and Region Dependent Cross Sections for Use to MOX Fuel Analysis"(in press).

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA: "Micro-Reactor Physics of MOX-Fueled Core"(in press).

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Takanori KITADA: "Direction and Region Dependent Cross Sections for Use to MOX Fuel Analysis"Journal of NUCLEAR SCIENCE and TECHNOLOGY. Supplement2. 1057-1060 (2002)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Tsuyoshi AMA, Hideaki IKEDA, Shinya KOSAKA, Hideaki HYOUDOU, Toshikazu TAKEDA: "Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boling Water Reactor Cross"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 39・5. 487-498 (2002)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshihisa Yamamoto, Toshikazu TAKEDA: "Neutoron Monte Carlo Simulation Using a Hypothetical Particle "MISSILON""ATOMIC ENERGY SOCIETY OF JAPAN 2001 AESJ2002 FALL MEETING proceeding. 240. (2002)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Kazuya Yamaji, Toshikazu TAKEDA: "Transient Analysis of LWR Assembly Based on Micro Reactor Physics"ATOMIC ENERGY SOCIETY OF JAPAN 2001 AESJ2002 FALL MEETING proceeding. 242. (2002)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Takanori Kitada: "Comparison of Doppler Reactivities for U and Pu Fueled LWR Cells"ATOMIC ENERGY SOCIETY OF JAPAN 2001 AESJ2002 FALL MEETING proceeding. 249. (2002)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA etc.: "Why Reactor Physics is interesting?"ATOMIC ENERGY SOCIETY OF JAPAN.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Hideaki HYOUDOU, Takanori Kitada: "EFFECT OF NONUNIFORM 3-D VOID DISTRIBUTION WITHIN BWR FUEL ASSEMBLIES ON NEUTRONIC CHARACTERISTICS"PRPCEEDINGS 18^<th> International Conference on Transport Theory. 205-210 (2003)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA: "Reactor Physics Producing"ATOMIC ENERGY SOCIETY OF JAPAN. 45・7. 424-427 (2003)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Tadashi Ushio, Toshikazu Takeda: "The Characteristics and Subgroup Methods in Square Light Water Reactor Cell Calculations"NUCLEAR SCIENCE AND ENGINEERING. 144. 61-80 (2003)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Tadashi USHIO, Toshikazu TAKEDA, Masaaki MORI: "Neutron Anisotropic Scattering in Heterogeneous Cell Calculations of Light Water Reactors"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 40・7. 464-480 (2003)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Kazuya YAMAJI, Akiko SAWAD: "TRANSIENTANAL OF NEUTRONIC BEHAVIOR IN FUEL ASSEMBLIES BASED ON MICRO REACTOR PHYSICS"International Conference on Supercomputing in Nuclear Applications SNA'2003. 27. (2003)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Yzuru HAMADA, Takanori KITADA: "3D Transport Theory Method Based on MOC for Analyzing Integral Data of Transmutation"Global. 1005-1010 (2003)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2003 Final Research Report Summary
  • [Publications] Toshikazu TAKEDA, Hideaki HYOUDOU, Takanori KITADA: "EFFECT OF NONUNIFORM 3-D VOID DISTRIBUTION WITHIN BWR FUEL ASSEMBLIES ON NEUTRONICS CHARACTERISTICS"PRPCEEDINGS 18^<th> International Conference on Transport Theory. 205-210 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] 竹田 敏一: "アイデアを生み出す炉物理"日本原子力学会誌. 45・7. 424-427 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] Tadashi Ushio, Toshikazu Takeda: "The Characteristics and Subgroup Methods in Square Light Water Reactor Cell Calculations"NUCLEAR SCIENCE AND ENGINEERING. 144. 61-80 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] Tadashi USHIO, Toshikazu TAKEDA, Masaaki MORI: "Neutron Anisotropic Scattering in Heterogeneous Cell Calculations of Light Water Reactors"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 40・7. 464-480 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] Toshikazu TAKEDA, Kazuya YAMAJI, Akiko SAWADA: "TRANSIENTANALYSIS OF NEUTRONIC BEHAVIOR IN FUEL ASEEMBLIES BASED ON MICRO REACTOR PHYSICS"International Conference on Supercomputing in Nuclear Applications SNA'2003. 27 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] Toshikazu TAKEDA, Yuzuru HAMADA, Takanori KITADA: "3D Transport Theory Method Based on MOC for Analyzing Integral Data of Transmutation"Global2003. 1005-1010 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] Tadashi Ushio, Toshikazu Takeda, Masaaki Mori: "The Characteristics and Subgroup Methods in Square Light Water Reactor Cell Calculations"NUCLEAR SCIENCE AND ENGINEERING. 143. 61-80 (2003)

    • Related Report
      2002 Annual Research Report
  • [Publications] 山路和也, 竹田敏一: "ミクロ炉物理による軽水炉燃料集合体過度解析"(印刷中).

    • Related Report
      2002 Annual Research Report
  • [Publications] 津田章子, 山路和也, 竹田敏一: "マルチバンド法におけるバンドパラメータ作成手法の改良"(印刷中).

    • Related Report
      2002 Annual Research Report
  • [Publications] 佐野忠史, 竹田敏一: "モンテカルロ燃焼計算における計算誤差伝播"(印刷中).

    • Related Report
      2002 Annual Research Report
  • [Publications] 北田孝典, 竹田敏一, 山本章夫, 山崎正俊: "連続エネルギーモンテカルロ計算による燃料実効温度に関する検討"日本原子力学会2001年秋の大会. 470-470 (2001)

    • Related Report
      2001 Annual Research Report
  • [Publications] Tsuyoshi AMA, Hideaki HYOUDOU, Toshikazu TAKEDA: "Effect of Radial Void Distribution with in Fuel Assembly on Assembly Neutronic Characteristics"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 39・1. 90-100 (2002)

    • Related Report
      2001 Annual Research Report
  • [Publications] Hideaki IKEDA, Toshikazu TAKEDA: "Development and Verification of an Efficient Spatial Neutron Kinetics Method for Reactivity-Initiated Event Analyses"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 38・7. 492-502 (2002)

    • Related Report
      2001 Annual Research Report
  • [Publications] Toshikazu TAKEDA, Takumi HORIUCHI, Tatsuya IWAMOTO, Masaaki MORI: "Advanced Nodal Methods and Applications to LWR Core Design and Analysis in Japan"(印刷中).

    • Related Report
      2001 Annual Research Report
  • [Publications] Toshikazu TAKEDA, Takanori KITADA: "Direction and Region Dependent Cross Sections for Use to MOX Fuel Analysis"(印刷中).

    • Related Report
      2001 Annual Research Report
  • [Publications] Toshikazu TAKEDA: "Micro-Reactor Physics of MOX-Fueled Core"(印刷中).

    • Related Report
      2001 Annual Research Report

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Published: 2001-04-01   Modified: 2016-04-21  

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