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2001 Fiscal Year Final Research Report Summary

Chemical Behavior of Molten Salt Tritium Breeding Material for Fusion Reactors

Research Project

Project/Area Number 09480107
Research Category

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

Allocation TypeSingle-year Grants
Section一般
Research Field Nuclear fusion studies
Research InstitutionThe University of Tokyo

Principal Investigator

TERAI Takayuki  Graduate School of Engineering, The University of Tokyo, Prof., 大学院・工学系研究科, 教授 (90175472)

Co-Investigator(Kenkyū-buntansha) YONEOKA Toshiaki  Graduate School of Engineering, The University of Tokyo, R. assoc., 大学院・工学系研究科, 助手 (40013221)
YAMAGUCHI Kenji  Graduate School of Engineering, The University of Tokyo, A. Prof., 大学院・工学系研究科, 助教授 (50210357)
TANAKA Satoru  Graduate School of Engineering, The University of Tokyo, Prof., 大学院・工学系研究科, 教授 (10114547)
Project Period (FY) 1997 – 1999
Keywordsfusion reactor / tritium breeding material / molten salt / tritium release / permeation / corrosion / structural material / blanket
Research Abstract

A molten salt mixture of LiF and BeF_2 (denoted as Flibe) has been proposed to be a candidate material for tritium breeding and cooling medium in fusion reactor blanket systems. In this study, its chemical properties such as tritium release property and compatibility with structural materials under blanket-simulated conditions were investigated.
In-situ tritium release experiments were carried out under neutron irradiation at the temperatures of 500-700 C using the fast neutron source reactor "YAYOI", University of Tokyo in order to measure the released chemical species of tritium, diffusion coefficient of tritium in molten Flibe and tritium release rate. Based on these parameters, a model on tritium release from Flibe was constructed. In addition, the tritium permeation rate through structural wall facing molten Flibe was measured. By using, all the date obtained in the experiments, an effective tritium recovery system with low tritium permeation was proposed.
A compatibility test of structural materials with molten Flibe was also carried out. Specimens of some candidate materials including Mo, W, V, Fe and their alloys as well as SiC/SiC_f composite were immersed in molten Flibe at 550 C for 1 - 30 days, and they were examined by XRD, RBS, SEM, XPS, etc. on the composition and the crystallographic change of the surface. The corrosion rate was evaluated and the mechanism was discussed in comparison with thermodynamic calculation.

  • Research Products

    (42 results)

All Other

All Publications (42 results)

  • [Publications] A.Suzuki et al.: "In-situ Tritium Release Bahavior from Molten Li_2BeF_4 Salt under Neutron Irradiation"Fusion Technology 1996. 1459-1462 (1997)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Sagara et al.: "Blanket Design Using Flibe In Helical-type Fusion Reactor FFHR"J. Nucl. Mater.. 248. 147-152 (1997)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Terai et al.: "Tritium Release Behavior from Liquid Tritium Breeding Materials for Fusion Reactor Blanket under Neutron irradiation"Progress in Nuclear Energy. 32. 97-112 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Terai et al.: "Mechanism of Tritium Release from Li_2BeF_4 Molten Salt Breeder under Neutron Irradiation at Elevated Temperature"Fusion Technology 1998. 1453-1456 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] Y.Hosoya et al.: "Compatibility of Structural Materials with Molten Fluoride Breeder"Fusion Technology 1998. 1457-1460 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Suzuki et al.: "In-situ HT Release Behavior from Molten Li_2BeF_4 Salt"Fus. Eng. Des.. 39-40. 781-785 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Sagara et al.: "Design Studies of Helical-type Reactor FFHR"Fus. Eng. Des.. 41. 349-355 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] H.Yamanishi et al.: "Design Studies on Nuclear Properties on the Flibe Blanket Helical-type Fusion Reactor FFHR"Fus. Eng. Des.. 41. 583-588 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] FFHR Group et al.: "Study of Safety Concept for a Helical-type Fusion Reactor FFHR"Fus. Eng. Des.. 42. 115-125 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Suzuki et al.: "Mechanism on Change of Tritium Species in Li_2BeF_4 Molten Salt Breeder under Neutron Irradiation at Elevated Temperature"Fus. Technol.. 34. 526-530 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Terai et al.: "Compatibility of Structural Materials with Li_2BeF_4 Molten Salt Breeder"J. Nucl. Mater.. 258-263. 513-518 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Suzuki et al.: "Changes of Tritium Species in Li_2BeF_4 Molten Salt Breeder under Neutron Irradiation at Elevated Temperature"J. Nucl. Mater.. 258-263. 519-524 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Sagara et al.: "Materials Design and Relates R&D Issues for the Force-free Helical Reactor (FFHR)"J. Nucl. Mater.. 258-263. 2079-2082 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] H.Nishimura et al.: "Compatibility of Strucliral Condiate Materials with LiFBeF_2 Molten Salt Mixture"J. Nucl. Mater.. 283-287. 1326-1331 (2000)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Sagara et al.: "Design and Development of the Flibe Blanket for Helical-type Fusion Reactor FFHR"Fus. Eng. Des.. 49-50. 661-666 (2000)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Suzuki et al.: "Tritium Behavior from Li_2BeF_4 Molten Salt by Permeation through Structural Materials"Fus. Eng. Des.. 51-52. 863-868 (2000)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Sagara et al.: "Studies on Flibe Blanket Designs in Helical Reactor FFHR"Fus. Technol.. 39. 753-757 (2001)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Terai et al.: "Tritium Release from Li_2BeF_4 Molten Salt Breeder under Neutron Irradiation at Elevated Temperature"Fus. Technol.. 39. 768-772 (2001)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Terai et al.: "Compatibility of Structural Materials with Li_2BeF_4 Molten Salt Breeder"Fus. Technol.. 39. 784-788 (2001)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] K.Nomura et al.: "Characterization of Oxide Layers and Interface Layers of Feoritic Stainless Steel (SUS430) by ^<57>Fe CEMS"Czechoslovic J. Phys.. 51. 773-780 (2001)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] H.Nishimura et al.: "Chemical Behavior of Li_2BeF_4 Molten Salt as a Liquid Tritium Breeder"Fus. Eng. Des.. 58-59. 667-672 (2001)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A. Suzuki, T. Terai and S. Tanaka: "In-situ Tritium Release Behavior from Molten Li_2BeF_4 Salt under Neutron Irradiation"Fusion Technology (C. Varandas and F. Serra, eds., Elsevier, 1997). 1459-1462 (1996)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A. Sagara, O. Motojima, O. Mitarai, et al.: "Blanket Design Using FLiBe in Helical-type Fusion Reactor FFHR"Journal of Nuclear Materials. 248. 147-152 (1997)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Terai and S. Tanaka: "Tritium Release Behavior from Liquid Tritium Breeding Materials for Fusion Reactor Blanket under Neutron Irradiation"Progress in Nuclear Energy. 32 (FRM, HMM, T). 97-112 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Terai, A. Suzuki and S. Tanaka: "Mechanism of Tritium Release from Li_2BeF_4 Molten Salt breeder under Neutron Irradiation at Elevated Temperature"Fusion Technology (Ed. by B. Beaumont et al., Elsevier, 1998). 1453-1456 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] Y. Hosoya, T. Terai, S. Tanaka, et al.: "Compatibility of Structural Materials with Molten Fluoride Breeder"Fusion Technology (Ed. by B. Beaumont et al., Elsevier, 1998). 1457-1460 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A. Suzuki, T. Terai and S. Tanaka: "In-situ HT Release Behavior from Molten Li_2BeF_4 Salt"Fusion Engineering and Design. 39-40. 781-785 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A. Sagara, O. Motojima, S. Imagawa et al.: "Design Studies of Helical-type Reactor FFHR"Fusion Engineering and Design. 41. 349-355 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] H. Yamanishi, A. Sagara, O. Motojima, T. Noda, S. Tanaka, T. Terai, T. Uda and FFHR Group: "Design Studies on Nuclear Properties on the Flibe Blanket Helical-type Fusion Reactor FFHR"Fusion Engineering and Design. 41. 583-588 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] FFHR Group, T. Uda, A. Sagara et al.: "Study of Safety Concept for a Helical-type Fusion Reactor FFHR"Fusion Engineering and Design. 42. 115-125 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A. Suzuki, T. Terai and S. Tanaka: "Mechanism on Change of Tritium Species in Li_2BeF_4 Molten Salt Breeder under Neutron Irradiation at Elevated Temperature"Fusion Technology. 34. 526-530 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Terai, Y. Hosoya, S. Tanaka et al.: "Compatibility of Structural Materials with Li_2BeF_4 Molten Salt Breeder"Journal of Nuclear Materials. 258-263. 513-518 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A. Suzuki, T. Terai and S. Tanaka: "Changes of Tritium Species in Li_2BeF_4 Molten Salt Breeder under Neutron Irradiation at Elevated Temperature"Journal of Nuclear Materials. 258-263. 519-524 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A. Sagara, T. Muroga, O. Motojima et al.: "Materials Design and Related R&D Issues for the Force-free Helical Reactor (FFHR)"Journal of Nuclear Materials. 258-263. 2079-2082 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] H. Nishimura, T. Terai, T. Yoneoka et al.: "Compatibility of Structural Candidate Materials with LiF-BeF_2 Molten Salt Mixture"Journal of Nuclear Materials. 283-287. 1326-1331 (2000)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A. Sagara, H. Yamanishi, S. Imagawa et al.: "Design and Development of the Flibe Blanket for Helical-type Fusion Reactor FFHR"Fusion Engineering and Design. 49-50. 661-666 (2000)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A. Suzuki, T. Terai and S. Tanaka: "Tritium Release Behavior from Li_2BeF_4 Molten Salt by Permeation through Structural Materials"Fusion Engineering and Design. 51-52. 863-868 (2000)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] Akio Sagara, Hirokuni Yamasaki, Tatsuhiko Uda et al.: "Studies on Flibe Blanket Designs in Helical Reactor FFHR"Fusion Technology. 39. 753-757 (2001)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] Takayuki Terai, Akihiro Suzuki and Satoru Tanaka: "Tritium Release from Li_2BeF_4 Molten Salt Breeder under Neutron Irradiation at Elevated Temperature"Fusion Technology. 39. 768-772 (2001)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T. Terai, H. Nishimura, K. Yamaguchi et al.: "Compatibility of Structural Materials with Li_2BeF_4 Molten Salt Breeder"Fusion Technology. 39. 784-788 (2001)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] K. Nomura, Y. Hosoya, H. Nishimura et al.: "Characterization of Oxide Layers and Interface Layers of Ferritic Stainless Steel (SUS430) by ^<57>Fe CEMS"Czechoslovac Journal of Physics. 51. 773-780 (2001)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] H. Nishimura, A. Suzuki, T. Terai et al.: "Chemical Behavior of Li_2BeF_4 Molten Salt as a Liquid Tritium Breeder"Fusion Engineering and Design. 58-59. 667-672 (2001)

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

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Published: 2003-09-17  

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