• Search Research Projects
  • Search Researchers
  • How to Use
  1. Back to project page

1989 Fiscal Year Final Research Report Summary

STUDY OF REACTIVITY COEFFICIENTS BASED ON REACTOR TRANSIENT ANALYSIS

Research Project

Project/Area Number 63580180
Research Category

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

Allocation TypeSingle-year Grants
Research Field Nuclear engineering
Research InstitutionOSAKA UNIVERSITY

Principal Investigator

TAKEDA Toshikazu  OSAKA UNIVERSITY, DEPARTMENT OF NUCLEAR ENGINEERING, ASSOCIATE PROFESSOR, 工学部, 助教授 (30116058)

Project Period (FY) 1988 – 1989
KeywordsTransient Characteristics / Reactivity Coefficients / Self-Shielding Effect / Multi-Band Method / Space-Time Kinetics / Coarse-Mesh Method
Research Abstract

Foi reactor safety, it is necessary to study the transient response of reactor power, coolant temperature, etc. against various causes of accidents. In the present work, we have used a space-time kinetics code to study the effects of reactivity coefficients on some fundamental transient characteristics.
First, we have studied the methodology of producing the effective group cross sections. A highly accurate treatment of the self shielding is very important in detailed nuclear characteristics calculations, and we have developed a method of applying the multi-band theory to heterogeneous lattices. The new methodology has been applied to the analysis of a tight-pitch lattice experiment carried out on the Kyoto University Critical Assembly, and the results have been compared with those of the conversational self-shielding factor method and of the Monte Carlo method to see its validity.
Next, we have investigated a method for space-time transient analysis. Because of the weak neutronic coupling in large reactors, a reactivity insertion causes a strong local distortion in the neutron flux distribution, which makes it necessary to develop an efficient three-dimensional method. We have newly formulated the neutron currents in the framework of time-dependent diffusion theory, and developed a coarse-mesh, but very accurate, method of transient analysis. The method has been applied to a fast breeder reactor to estimate the coarse-mesh effect on the transient power distributions and sodium temperature distributions.
Finally, we have summarized the problems deferred to a future work.

  • Research Products

    (12 results)

All Other

All Publications (12 results)

  • [Publications] T.Takeda et al.: "Analysis of Laorge liquid Metal Fast Breeder Reactor Critical Experiments by Improued Methods" Nuclear Science and Engineering. 100. 538-544 (1988)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] 竹田敏一: "わが国原子力研究最近10年の歩み-その概要と展望-「数値解析・計算コ-ド」" 日本原子力学会誌. 31. 19-20 (1989)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Takada,A.Yoshimura: "Calculational method error correlation effect in data adjustment for large LMFBRS" Transactions,American Nuclear Society. 60. 599-600 (1989)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Takeda,et al: "Prediction uncertainty evaluation methods of core performance parameters in large liquid-metal past breeder reactors" Nuclear Science and Engineering. 103. 157-165 (1989)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Takeda,M.Tanaka: "Three dimensional kinetics calculations with improved coarse mesh method for fast reactors" Proceedings,American Nuclear Society,Nashville June 1990. (1990)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Takeda,et al: "Improvement of a three-dimensional transport code and its application to core analysis of large LMFBRS" Proceedings,Marseille April 1990. (1990)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T. Takeda, et al.: "Improvement of a three-dimensional transport code and its application to core analysis of large LMFBRs" Proceedings, Marseille. (April, 1990)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Takeda and M. Tanaka: "Three-dimensional kinetics calculations with improved coarse mesh method for fast reactors" Proceedings, American Nuclear Society, Nashville, June, 1990.

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Takeda, A. Yoshimura, T. Kamei, and K. Shirakata: "Prediction uncertainty evaluation methods of core performance parameters in large liquidmetal fast breeder reactors" Nuclear Science and Engineering. 103. 157 (1989)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Takeda, A. Yoshimura: "Calculational method error correlation effect in data adjustment for large LMFBRs" Transactions, American Nuclear Society, 60, 599, 1989.

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Takeda: "One decade's progress in nuclear research in Japan - Numerical analysis and codes (in Japanese)" Journal of the Atomic Energy Society of Japan, 31, 19, 1989.

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Takeda, et al.: "Analysis of large liquid-metal fast breeder reactor critical experiments by improved methods" Nuclear Science and Engineering, 100.538, 1988.

    • Description
      「研究成果報告書概要(欧文)」より

URL: 

Published: 1993-03-26  

Information User Guide FAQ News Terms of Use Attribution of KAKENHI

Powered by NII kakenhi