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1992 Fiscal Year Final Research Report Summary

Thorium Fuel Cycle as a Promising Energy Source in and after 21st Century

Research Project

Project/Area Number 02302089
Research Category

Grant-in-Aid for Co-operative Research (A)

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

Principal Investigator

KIMURA Itsuro  Kyoto University, Fac. of Engg., Professor, 工学部, 教授 (40027404)

Co-Investigator(Kenkyū-buntansha) FURUYA Hirotaka  Kyushu University, Fac. of Engg., Professor, 工学部, 教授 (30112311)
FURUKAWA Kazuo  Tokai University, Inst, of Research and Development, Professor, 開発技術研究所, 教授 (90165465)
SEKIMOTO Hiroshi  Tokyo Institute of Technology, Res. Lab. for Nuclear Reactors, Professor, 原子炉工学研究所, 教授 (00108242)
YAMAWAKI Michio  University of Tokyo, Fac. of Engg., Professor, 工学部, 教授 (30011076)
HIRAKAWA Naohiro  Tohoku University, Fac of Engg., Professor, 工学部, 教授 (20005391)
Project Period (FY) 1990 – 1992
Keywordsthorium / thorium fuel / thorium cycle / uranium 233 / reactor design / critical experiment / molten salt / reprocessing
Research Abstract

1. Design studies of thorium fueled reactors: (1) Nuclear data; mass yield and neutron spectrum of the fission of U-233 and double differential cross section of Th-232 for 18 MeV neutrons were measured. (2) Reactor design studies; molten salt reactors for transmutation of long-lived minor actinides, fast reactors loading Th-232, three types of thermal reactors for U-233 production, molten salt power reactors named FUJI and mini-FUJI and accelerator breeders were designed. (3) Critical experiment of thorium loaded cores was carried out at KUCA and the result is compared with calculation. (4) Preliminary study of 14 MeV neutron transport in thorium and in thoria was done at KUCA. 2. Studies of thorium fuels and other reactor materials: (1) Thorium fuels; U-Th-Ti-Zr alloy was newly made and its hydrogen absorption properties were measured. The chemical diffusion coefficients of oxygen in ThO_2-UO_<2+x>was obtained. High burnup behavior of thorium oxide fuels was observed. (2) Molten salt studies; corrosion of Ni and Cr by residual moisture in molten LiF-BeF_2, diffusion coefficient of actinides and fission products in molten LiF-BeF_2, electrochemical behavior of Y in molten LiCl-KCl-Nacl and release rate of T from molten LiF-BeF_2 were measured. (3) Uranium enrichment; Anomalous isotope effects in chemical exchange uranium enrichment process was discovered. (4) Reprocessing; Solvent extraction of Th, U and some metals from nitrate solution of organophosphinic acid was investigated. 3. Study of radiation safety in thorium cycle: A passive integrating thoron(^<222>Rn) monitor was developed and was applied to measure thoron and radon(^<220>Rn) in a city.

  • Research Products

    (24 results)

All Other

All Publications (24 results)

  • [Publications] H.Chatani: "Measure of ^<232>Th(n,2n)^<231>Th Reaction Cross Section with 14.5 MeV Neutrons" Annals of nuclear Energy. 19. 425-429 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Ohsawa: "Analysis of Fission Neutron Spectra by Non-equitemperature Madland-Nix Model" Nuclear Data for Science and Technology. 1. 965-967 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] M.Baba: "Double Differential Neutron Emission Cross Section of U-238 and Th-232 for 18 Mev Incident Neutrons" Nuclear Data for Science and Technology. 1. 349-351 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] N.Takagi: "Feasibility of Fast Fission System Confining Long-Lived Nuclides" Journal of Nuclear Science and Technology. 29. 276-283 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] Z.Su'ud: "Reactor Physics Characteristics of Lead Cooled and Lead-Bismuth Cooled Fast Reactors" Design and Safety of Advanced Nuclear Power Plants. 2. P.9.7,1-6 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] P.H.Liem: "Neutronic Modeling for Modular High Temperature Pebble Bed Reactor during Reactivity Accident" Journal of Nuclear Science and Technology. 29. 805-812 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] K.Furukawa: "Small Molten-Salt Reactors with a Rational thorium-Fuel-Cycle" Nuclear Engineering and Design. 139. 157-165 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] K.Furukawa: "New Global Energy Strategy by Thorium Melten-Salt Nuclear Energy Synergetics" Design and Safety of Advanced Nuclear Power Plants. 1. 3,9,1-7 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] V.D.Kazaritsky: "Practical Teatment of Minor Actinides by Single-Fiuid Molten Salt Reactor Concepts" Design and Safety of Advanced Nuciear Power Plants. 1. P.3.8,1-7 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] 三田地 紘史: "小型溶融塩発電炉の炉心減速材および燃料塩の温度分布" 原子力学会誌. 34. 1143-1150 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] S.A.Hayashi: "Integral Experiments with Rigard to the Thorium Based Hydrid Fusion Blanket" Nuclear Data for Science and Technology. 1. 220-222 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] S.Hikino: "Electrochemical Behavior of Yttrium Ion in Lic1-KC1-NaC1 Eutectic Melt" Journal of Electrochemical Society. 139. 1820-1824 (1992)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] H.Chatani: "Measurement of ^<232>Th(n, 2n)^<231>Th Reaction Cross Section with 14.5 MeV Neutrons" Annals nucl.Energy. 19-8. 425-429 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T.Ohsawa: "Analysis of Fission Neutron Spectra by Non-equitemperature Madland Nix Model" Nuclear Data for Sci.and Tech.965-967 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] M.Baba: "Double Differential Neutron Emission Cross Section of U-238 and Th-232 for 18 MeV Incident Neutrons" Nuclear Data for Sci.and Tech.349-351 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] N.Takagi: "Feasibility of Fast Fission System Confining Long-Lived Nuclides" J.Nucl.Sci.Tech.29-3. 276-283 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] Z.Su'ud: "Reactor Physics Characteristics of Lead Cooled and Lead-Bismuth Cooled Fast Reactors" Design and Safety of Advanced Nuclear Power Plants. 2-P.9.7. 1-6 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] P.H.Liem: "Neutronic Modeling for Modular High Temperature Pebble Bed Reactor during Reactivity Accident" J.Nucl.Sci.Tech.29-8. 805-812 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] K.Furukawa: "Small Molten-Salt Reactors with a Rational Thorium-Fuel-Cycle" Nucl.Eng.and Design. 139-1. 157-165 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] K.Furukawa: "New Global Energy Strategy by Thorium Molten Salt Nuclear Energy Synergetics" Design and Safety of Advanced Nuclear Power Plants. 1-P.3.8.1-7 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] V.D.Kazaritsky: "Practical Treatment of Minor Actinides by Single-Fluid Molten Salt Reactor Concept" Design and Safety of Advanced Nuclear Power Plants. 1-P.3.9,1-7 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] K.Mitaji: "Temperature Distribution in Graphite Moderators and Fuel Salt in Core of Small Molten-Salt Power Reactor (in Japanese)" J.Atomic Energy Soc.Japan. 34-12. 1143-1150 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] S.A.Hayashi: "Integral Experiments with Regard to the Thorium Based Hybrid Fusion Blanket" Nuclear Data for Sci.and Tech.220-222 (1992)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] S.Hikino: "Electrochemical Behavior of Yittrium Ion in LiCl-KCl-NaCl Eutectic Melt" J.Electrochemical Soc.139-7. 1820-1824 (1992)

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

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Published: 1994-03-24  

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