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Journal Articles

Application of a fiber optic grating strain sensor for the measurement of strain under irradiation environment

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:29.2(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$$times$$1023n/m$$^{2}$$ (E$$>$$1MeV) by a fiber optic grating sensor, because in-pile temperature characteristics were in good agreement with out-of-pile test results.

Journal Articles

Application of capsule type strain gage and fiber optic grating strain sensor for measurement of strain under irradiation environment

Kaji, Yoshiyuki; Matsui, Yoshinori; Kita, Satoshi; Ide, Hiroshi; Tsukada, Takashi; Tsuji, Hirokazu

Nihon Genshiryoku Gakkai-Shi, 43(2), p.160 - 167, 2001/02

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Integrity evaluations for the 2nd Fugen pressure tube surveillance test

; ; ; ; ; Shibahara, Itaru

PNC TN9410 92-321, 30 Pages, 1992/10

PNC-TN9410-92-321.pdf:0.67MB

Integrity evaluations have been performed for the 2nd Fugen pressure tube test (8 years irradiation, 5.6 $$times$$ 10$$^{21}$$n/cm$$^{2}$$ (E$$>$$1Mev)). Test items mainly consist of tensile test, bending test, corrosion test and hydrogen analysis. It has become clear using these data that the pressure tube material has maintained its integrity during the irradiation by the integrity assessment on both tensile and fracture toughness properties. Besides, both thickness loss by corrosion and absorbed hydrogen content were lower than those of design values.

Journal Articles

Creep test of neutron irradiated hastelloy-X

Ogawa, Yutaka; ; ; ; Kondo, Tatsuo

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 19(3), p.311 - 319, 1978/00

no abstracts in English

Oral presentation

Nuclear data for material damage assessment and its use in material irradiation research, 3; Development of materials irradiation environment using research reactors

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.

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