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Basic Experiments on Criticality Safety with Data Processing Based on Stochastic Process Theory

Research Project

Project/Area Number 60460233
Research Category

Grant-in-Aid for General Scientific Research (B)

Allocation TypeSingle-year Grants
Research Field Nuclear engineering
Research InstitutionNagoya University

Principal Investigator

NISHINA Koujirou  School of Engineering, Nagoya University Professor, 工学部, 教授 (60023222)

Co-Investigator(Kenkyū-buntansha) 小林 岩夫  日本原子力研究所, 燃料安全工学部臨界安全研究室, 室長
YAMANE Yoshihiro  School of Engineering, Nagoya University Assistant Professor, 工学部, 講師 (60115649)
KOBAYASHI Iwao  Japan Atomic Energy Research Institute Division of Fuel Safety Engineering Head
Project Period (FY) 1985 – 1987
Project Status Completed (Fiscal Year 1987)
Budget Amount *help
¥4,500,000 (Direct Cost: ¥4,500,000)
Fiscal Year 1987: ¥1,000,000 (Direct Cost: ¥1,000,000)
Fiscal Year 1986: ¥1,700,000 (Direct Cost: ¥1,700,000)
Fiscal Year 1985: ¥1,800,000 (Direct Cost: ¥1,800,000)
KeywordsNoise analysis / Reactor fuel / Criticality safety / Californium / Power spectrum / Stochastic process / Subcriticality / 中性子増倍モニター / 核燃料 / 原子炉動特性 / 末臨界度 / 中性子増倍率
Research Abstract

In this project the possibility of using the Cf-neutron-source noise method as a criticality safety monitor in plant environment is investigated. Therr detectors are used.one ionization chamber containing a Cf source. and two neutron detectors. A ratio called "spectral ratio" is evaluated from therr cross-power of the detector outputs and auto-power spectrum of the Cf detector. By stochastic process theory this ratio is related to the neutron multiplication factor which is the quantity of out interest. The following progress was made during the present period of the project:
(1) A theoretical formula was derived which predicts the apparent dependence of the spectral ratio. and hence neutron multiplication factor, on the locations of the three detectors.
(2) This formula was verified experimentally,although the numder of experimental points are seill limited.
(3) With a Monte Carlo code programmed. the formula described in (1) was verified for a modeled system.
(4) With this code. the dependence of the specral ratio on the Cf source intensity was verified to be weak.
(5) To adapt this moise method to a two-unit system, a formula expressing the depencdence of spectral ratio on the unit distance was derived based on two-point kinetic formula.
(6) A rigorous formula was derived including the effect of delayed neutron. which which relates the spectral ratio to the neutron multiplication factor. The conventional neglection of delayed neutron turned out to be legitimate.

Report

(2 results)
  • 1987 Final Research Report Summary
  • 1986 Annual Research Report
  • Research Products

    (5 results)

All Other

All Publications (5 results)

  • [Publications] 山根義宏, 渡辺昭次, 仁科浩二郎, 三好憲典, 須崎武則, 小林岩夫: 日本原子力学会誌. 28. 850-858 (1987)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] YOSHIHIRO YAMANE;HIROSHI YANAGISAWA and KOUJROU NISHINA: Proceedings of the Onternational Seminar on Criticality Safety, Atomic Energy Society of Japan, Tokyo (October, 1987). 393-400 (1987)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Yoshihiro.Yamane,Shouji.Watanabe,Koujirou.Nishina, Yoshinori.Miyoshi,Takenori.suzaki,and Iwao.Kobayashi: "Determination of Nuclear Fuel System Subcriticality by the Mihalczo Method (in Japanese)" Journal of the Atomic Energy Society of Japan. 28. 850-858 (1986)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Yoshihiro.Yamane,Hiroshi.Yanagisawa,and Koujirou.Nishina: "Derivation of Space-dependent Formula for the Cf-252-driven Neutron Noise Experiment" Proceedings of the International Seminar on Criticality Safety, Atomic Enerby Society of Japan (October, 1987). 393-400 (1987)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] 山根義宏,渡辺昭次,仁科浩二郎,三好慶典,須崎武則,小林岩夫: 日本原子力学会誌. 28. 850-858 (1986)

    • Related Report
      1986 Annual Research Report

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Published: 1987-03-31   Modified: 2016-04-21  

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