1. Integrity Confirmation Tests and Post-irradiation Test Plan of the HTTR First-Loading Fuel
- Author
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Toshio Koya, Shouhei Ueta, Kazuo Minato, Hajime Sekino, Shuichi Suzuki, Junya Sumita, Takashi Saito, Tsutomu Tobita, and Kazuhiro Sawa
- Subjects
Nuclear and High Energy Physics ,Fabrication ,Materials science ,Nuclear fuel ,Nuclear engineering ,Nuclear reactor ,Fuel element failure ,law.invention ,Nuclear physics ,chemistry.chemical_compound ,Nuclear Energy and Engineering ,chemistry ,law ,Silicon carbide ,Irradiation ,Test plan ,Post Irradiation Examination - Abstract
Since the first-loading fuel of the High Temperature Engineering Test Reactor (HTTR) is the first mass-production High Temperature Gas-cooled Reactor (HTGR) fuel in Japan, their quality should be carefully inspected. For the quality control related to the fabrication process, Japan Atomic Energy Research Institute (JAERI) carried out the tests to certify the fuel integrity during operation. The tests comprise (1) as-fabricated SiC failure fraction measurement, (2) high-temperature heatup test of irradiated fuel and (3) accelerated irradiation test. For (1), the SiC failure fraction was measured independently in JAERI in addition to the measurement in the fabrication process. The measured failure fractions agreed within 95% confidence limit. In order to confirm the integrity of the SiC layer with respect to the 1,600°C criterion, the high-temperature heatup test of irradiated fuel compact was carried out. The result showed that no failed particle was present in the fuel compact after heating. The diffusion...
- Published
- 2001
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