Japan-US Joint Research Project PHENIX (2013–2018); Heat Transfer Tests, Neutron Irradiation and Post-Irradiation Examinations for Development of He-Cooled Tungsten Divertor

Conference · Tue May 01 00:00:00 EDT 2018

OSTI ID:1649648

Ueda, Yoshio ^[1]; Clark, Daniel ^[2]; Yokomine, Takehiko ^[3]; Sabau, Adrian  ^[4]; Yoda, Minami ^[5]; Hinoki, Tatsuya ^[3]; Hasegawa, Akira ^[6]; Kato, Yutai  ^[4]; Garrison, Lauren M.  ^[4]; Oya, Yasuhisa ^[7]; Shimada, Masashi ^[8]; Buchenauer, Dean ^[9]; Fukuda, Makoto ^[6]; Tanaka, T. ^[10]; Muroga, Takeo ^[10]; Hatano, Yuji ^[11]

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1. Osaka University, Japan
2. U.S. Department of Energy (DOE)
3. Kyoto University, Japan
4. ORNL
5. Georgia Institute of Technology, Atlanta
6. Tohoku University, Japan
7. Shizuoka University, Japan
8. Idaho National Laboratory (INL)
9. Sandia National Laboratories (SNL)
10. National Institute for Fusion Science, Toki, Japan
11. Toyama University, Japan

The goal of the Japan-US joint research project PHENIX (2013–2018) is to understand the feasibility of He-cooled W divertor for DEMO applications. To achieve this goal, the project has three major objectives: (1) to understand heat transfer in a divertor module cooled with high-temperature and high-pressure He gas, (2) to establish database on thermomechanical properties of W materials after high temperature (~500, ~800 and ~1100 °C) neutron irradiation with fusion-relevant energy spectrum, and (3) to clarify tritium (T) trapping and permeation in neutron-irradiated W materials. Heat transfer tests for a He-cooled modular divertor with multi-jet (HEMJ) have been performed, and the problem of heat transfer degradation by re-laminarization was identified.The irradiation capsule with thermal neutron shielding was designed for high temperature neutron irradiation in the High Flux Isotope Reactor (HFIR), Oak Ridge National Laboratory (ORNL) with fusion-relevant transmutation. The expected damage level is 1–1.5 displacements per atom (dpa). Heat load resistance, thermal conductivity, mechanical properties and microstructures are examined in ORNL after the irradiation. Mechanical properties of W single crystal samples irradiated with neutrons in HFIR at 90– 850 °C without thermal neutron shielding were examined for comparison. Significant hardening was observed after irradiation to >1 dpa. Microstructural examinations revealed that the hardening was mainly caused by formation of irradiation-induced precipitates consisting of W, Re and Os. Comparison with new samples irradiated in the capsule with thermal neutron shielding will show the effects of irradiation temperatures and transmutation elements. Retention and permeation of hydrogen isotopes including T in neutron-irradiated samples are examined in Idaho National Laboratory, and permeation of H and D in samples damaged with surrogate irradiations (heavy ions, electrons, etc.) is measured in Sandia National Laboratories, Livermore, to study hydrogen-defect interactions in wider conditions. The measurement of D retention in the single crystal W sample after neutron irradiation to 0.1 dpa at 360 °C and subsequent plasma exposure at 400 °C showed significant trapping effects by radiation-induced defects.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1649648
• Resource Relation: Conference: 26th IAEA Fusion Energy Conference - Kyoto, , Japan - 10/17/2016 4:00:00 AM-10/22/2016 4:00:00 AM
• Country of Publication: United States
• Language: English