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Hanawa, Satoshi; Uchida, Shunsuke; Hata, Kuniki; Chimi, Yasuhiro; Kasahara, Shigeki*; Nishiyama, Yutaka
Proceedings of 20th Nuclear Plant Chemistry International Conference (NPC 2016) (USB Flash Drive), 11 Pages, 2016/10
ECP is the exclusive index to evaluate corrosion condition directly at the points of interest in the mixing of neutron and 
-ray environment. ECP can be calculated through the combination of water radiolysis and ECP model. A water radiolysis model have been applied to experiments performed in in-pile loops in the experimental reactors and applicability was confirmed. An ECP model based on the Butler-Volmer equation was also prepared. ECP of stainless steel was measured under well controlled water chemistry condition in in-pile loop in the Halden reactor, and the model was applied to evaluate ECP measured in the Halden reactor. The measured data were well explained by the water radiolysis calculation and ECP model. Accumulation of in-pile ECP data are expected for further validation of the models.
Kaji, Yoshiyuki; Matsui, Yoshinori; Kita, Satoshi; Ide, Hiroshi; Tsukada, Takashi; Tsuji, Hirokazu
Nuclear Engineering and Design, 217(3), p.283 - 288, 2002/09
Times Cited Count：4 Percentile：29.25(Nuclear Science & Technology)In the Japan Atomic Energy Research Institute (JAERI), in-pile strain measurement techniques have been developed using the Japan Materials Testing Reactor (JMTR). In order to evaluate the performance of fiber optic grating sensors under irradiation environment, heat-up and performance tests at elevated temperatures before irradiation and in-pile tests were performed in JMTR. It was determined that it is possible to measure strain under irradiation environment below 1
1023n/m
(E
1MeV) by a fiber optic grating sensor, because in-pile temperature characteristics were in good agreement with out-of-pile test results.
*
JNC TN1400 2000-007, 100 Pages, 2000/07
JNC-TN1400-2000-007.pdf:4.67MB
no abstracts in English
Suzudo, Tomoaki; Yamaguchi, Masatake
no journal, ,
BCC transition metals are being discussed as candidates of structural materials in future nuclear systems, but their embrittlement at low temperatures is a concern. Besides, possibilities of so-called non-hardening embrittlement caused by grain boundary (GB) helium segregation have been pointed out. In the current study, we model GB helium segregation and following GB embrittlement based on the first principles calculations, and as an application of this modeling we numerically evaluate decrease in the GB strength of various BCC transition metals after they are exposed at the first wall of concept future nuclear fusion reactor, DEMO.
Oba, Hironori; Akaoka, Katsuaki; Karino, Takahiro; Wakaida, Ikuo; Tamura, Koji*; Nakanishi, Ryuzo*; Sakamoto, Kan*; Taira, Takunori*
no journal, ,
Development of remote inspection and elemental analysis methods in a harsh radiation environment is required, such as inspection of the nuclear fuel debris at the bottom of the post-accident nuclear reactor (Tokyo Electric Power Company, Fukushima Daiichi Nuclear Power Plant). Laser-induced breakdown spectroscopy (LIBS) has been utilized as an effective qualitative and quantitative analytical method for elemental analysis. Inspecting the damaged reactor vessels requires a longer fiber-optic (FO) cable, which significantly attenuates the delivered laser energy by absorption and scattering in the fiber. We report on the first trial of our FO-LIBS system using the microchip laser (MCL) to identify and quantify elements in surrogate nuclear fuel debris under gamma irradiation, the results of trials on surrogate debris analysis, containing uranium oxide, using the MCL, and the results of 100 m-long fiber-delivered LIBS.
Kaji, Yoshiyuki
no journal, ,
In order to improve the material irradiation environment in JRR-3, the capsule temperature control system was transferred from JMTR to JRR-3, the irradiation capsule design technology was inherited, and basic technologies such as neutron irradiation dose evaluation were developed. In this paper, the basic technologies for irradiation tests, such as the constant temperature control capsule and temperature control device developed in the JMTR and neutron irradiation dose evaluation, which are the basis of this basic technology, are outlined.
