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Study on Heavy Neutron Irradiation Effects of Refractory-Metal-Base, High-Z and High-Heat-Flux Materials for Fusion Power Reactors

Research Project

Project/Area Number 07458109
Research Category

Grant-in-Aid for Scientific Research (B)

Allocation TypeSingle-year Grants
Section一般
Research Field Nuclear fusion studies
Research InstitutionTohoku University

Principal Investigator

ABE Katsunori  Tohoku Univ., Faculty of Tech., Professor, 工学部, 教授 (70005940)

Co-Investigator(Kenkyū-buntansha) SATOU Manabu  Tohoku Univ., Research associate, 工学部, 助手 (40226006)
HASEGAWA Akira  Tohoku Univ., Faculty of Tech., Assistant Professor, 工学部, 助教授 (80241545)
UEDA Kazukiyo  Tohoku Univ., Graduate school
Project Period (FY) 1995 – 1996
Project Status Completed (Fiscal Year 1996)
Budget Amount *help
¥700,000 (Direct Cost: ¥700,000)
Fiscal Year 1996: ¥700,000 (Direct Cost: ¥700,000)
KeywordsRefractory Metal / Fusion Reactor / High-Heat-Flux Material / Neutron Irradiation / 各融合炉 / 核融合炉材料 / モリブデン合金 / 照射損傷 / 中性子照射 / 高熱流束材料 / 硬さ試験 / 曲げ試験
Research Abstract

Neutron irradiation effects of refractory metals, molybdenum (Mo), tungsten (W) and their alloys were studied in the program. The aim is to propose the availability of high-Z materials in the condition of high thermal load and heavy neutron irradiation as in fusion power reactors. In power reactors, high-heat flux materials must be survived after neutron exposure at high temperatures. In these materials, it is important to control the microstructure during irradiation in order to suppress the neutron-irradiation embrittlement.
In this study, Mo, TZM,Mo-Re and W-Re alloys were used. These materials are added with titanium and zirconium (for TZM alloy) and rhenium to improve the weldability and ductility after recrystallization. Material properties of these alloys after neutron heavy irradiation up to high fluence have not been studied well. The influence of irradiation conditions and materials parameters on the mechanical properties was studied.
The specimens were irradiated in the Fast Flux Test Facility (FFTF) at temperatures from 360C to 800C and fluence up to 34 dpa. With these specimen, the observations of microstructure, tensile tests and bend tests were carried out. It was found that heat treatments before irradiation affect the ductility change caused by neutron irradiation. Especially, stress-relieved treatment is found to be effective to suppress irradiation-induced embrittlement. Re addition is effective for suppression of recrystallization during irradiation at high temperatures over 800C.But excessive Re content enhances irradiation-induced precipitation, which results in conspicuous irradiation hardening and embrittlement.
As used in irradiation environment at high temperatures, such as in power fusion reactors, the alloys of Mo and W must be required with optimum Re content, as much as to suppress the growth of grain boundary and retard irradiation-induced precipitation.

Report

(3 results)
  • 1996 Annual Research Report   Final Research Report Summary
  • 1995 Annual Research Report
  • Research Products

    (5 results)

All Other

All Publications (5 results)

  • [Publications] A.Hesegawa et al.: "Influence of heat-treatment on tensile behavior of neutron irradiated molybdendum" Journal of Nuclear Materials. 233-237. 565-569 (1996)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1996 Final Research Report Summary
  • [Publications] A.Hasegawa et al.: "Influence of heat-treatment on tensile behavior of neutron irradiated molybdenum" Journal of Nuclear Materials. 233-237. 565-569 (1996)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1996 Final Research Report Summary
  • [Publications] A.Hasegawa et al.: "Tensile Behavior and microstructure of neutron-irradiated Mo-5%Re alloy" Journal of Nuclear Materials. 225. 259-266 (1995)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1996 Final Research Report Summary
  • [Publications] A. Hasegawa et al.: "Influence of heat-treatment on tensile behavior of neutron irradiated molybdendum" Journal of Nuclear Materials. 233-237. 565-569 (1996)

    • Related Report
      1996 Annual Research Report
  • [Publications] A.Hasegawa et.al.: "Tensile behavior and microstructure of neutron-irradiated Mo-5% Re alloy" Journal of Nuclear Materials. 225. 259-266 (1995)

    • Related Report
      1995 Annual Research Report

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Published: 1996-04-01   Modified: 2016-04-21  

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