Výsledky vyhledávání - "Mitsuyuki Sagisaka"

Microstructural characterization and density change of 304 stainless steel reflector blocks after long-term irradiation in EBR-II

Autor: Taira Okita, Yoshihiro Isobe, Paula D. Freyer, Jörg M.K. Wiezorek, Todd R. Allen, Y. Huang, F.A. Garner, Mitsuyuki Sagisaka

Publikováno v: Journal of Nuclear Materials. 465:516-530

While thin reactor structural components such as cladding and ducts do not experience significant gradients in dpa rate, gamma heating rate, temperature or stress, thick components can develop strong local variations in void swelling and irradiation

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::107b776de9894fc4c2d8973ef81283b4
https://doi.org/10.1016/j.jnucmat.2015.06.031

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Validation of Ultrasonic Velocity Measurements for Detecting Void Swelling in First-Wall Structural Materials

Autor: Paula D. Freyer, Taira Okita, Takashi Matsunaga, Mitsuyuki Sagisaka, Junji Etoh, F.A. Garner, Jörg M.K. Wiezorek, Y. Huang, Yoshihiro Isobe

Publikováno v: Fusion Science and Technology. 66:77-82

Time-of-flight ultrasonic measurements were conducted on a thick hexagonal block of 304 stainless steel irradiated to ∽33 dpa in EBR-II, and the results of ultrasonic-implied void swelling and carb...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::6060de3f75c63b3d11b1740deb60f66a
https://doi.org/10.13182/fst13-755

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Development of a nondestructive inspection method for irradiation-induced microstructural evolution of thick 304 stainless steel blocks

Autor: Paula D. Freyer, Junji Etoh, Jörg M.K. Wiezorek, Taira Okita, Y. Huang, F.A. Garner, Yoshihiro Isobe, Mitsuyuki Sagisaka, Takashi Matsunaga

Publikováno v: Journal of Nuclear Materials. 440:500-507

Ultrasonic testing was conducted on two long, Type 304 stainless steel blocks with a hexagonal cross-section that were removed from the reflector region of the decommissioned EBR-II reactor. One block had a dose range of 17–33 displacements per ato

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d04e055e3bf8caca528736e806ea0f07
https://doi.org/10.1016/j.jnucmat.2013.02.036

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Development of nondestructive inspection techniques for measurement of void swelling in irradiated microscopy disks

Autor: Mitsuyuki Sagisaka, S. Fujita, Taira Okita, Yoshihiro Isobe, F.A. Garner

Publikováno v: Journal of Nuclear Materials. 417:992-995

Results are presented of resistivity change measurements made on a model Fe–Cr–Ni–Ti–C austenitic alloy irradiated in the Fast Flux Test Facility to doses ranging from 1.87 to 67.8 dpa. Two different electrical resistivity measurement systems

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::25b21b613f835937e90a7d0c254bfe21
https://doi.org/10.1016/j.jnucmat.2010.12.199

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Dr. Mainte: An Integrated Simulator for Optimization of Maintenance Strategies of Light Water Reactors

Autor: Hiroshi Akiba, Mitsuyuki Sagisaka, Shinobu Yoshimura, Kazuo Furuta, Yoshihiro Isobe, Michiyasu Noda

Publikováno v: Transactions of the Atomic Energy Society of Japan. 9:125-138

A number of probabilistic safety assessment (PSA) studies have been conducted to optimize maintenance activities in nuclear power plants from the viewpoint of safety focusing on the risk of core meltdown. However, even a small-scale incident of compo

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::fbe950d1da482067b3bf5a49677fa016
https://doi.org/10.3327/taesj.j09.020

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Influence of damage rate on physical and mechanical properties and swelling of 18Cr–9Ni austenitic steel in the range of 3×10−9 to 4×10−8dpa/s

Autor: E.A. Kinev, Taira Okita, A. V. Kozlov, P. I. Yagovitin, M. V. Evseev, E. N. Shcherbakov, F.A. Garner, Mitsuyuki Sagisaka, Naoto Sekimura, V. L. Panchenko, I. Isobe

Publikováno v: Journal of Nuclear Materials. :152-156

The results of the examination of the specimens constructed from the Fe–18Cr–9Ni steel thick-wall pipe irradiated at temperatures 370–375 °С to damage rates from 1.5 to 21 dpa at displacement rates from 3 × 10 −9 to 4 × 10 −8 dpa/s are

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::dcda68540f4bf374360f0c03636cfd89
https://doi.org/10.1016/j.jnucmat.2008.12.080

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Precipitate evolution in low-nickel austenitic stainless steels during neutron irradiation at very low dose rates

Autor: Taira Okita, Yoshihiro Isobe, Francis A. Garner, S. Fujita, Mitsuyuki Sagisaka

Publikováno v: Journal of Nuclear Materials. :661-665

Neutron-induced microstructural evolution in response to long term irradiation at very low dose rates was studied for a Russian low-nickel austenitic stainless steel designated Х18Н9 that is analogous to AISI 304. The irradiated samples were obtain

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::bdec879f5fc70d378e78bf7601ffd73e
https://doi.org/10.1016/j.jnucmat.2008.12.255

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Economic Evaluation of Maintenance Strategies for Steam Generator Tubes Using Probabilistic Fracture Mechanics and a Financial Method

Autor: Mitsuyuki Sagisaka, Yoshihiro Isobe, Genki Yagawa, Shinobu Yoshimura

Publikováno v: Solid State Phenomena. 120:119-126

As an application of probabilistic fracture mechanics (PFM) and a financial method, a risk-benefit model was developed for the purpose of optimizing maintenance activities of steam generator (SG) tubes used in pressurized water reactors (PWRs). To ju

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3f068afd73b65c77cb059af02e93560b
https://doi.org/10.4028/www.scientific.net/ssp.120.119

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