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Sayato, Natsuki; Otsuka, Kaoru; Fuyushima, Takumi; Endo, Yasuichi; Otsuka, Noriaki; Kitagishi, Shigeru; Tobita, Masahiro*; Isozaki, Futoshi*; Matsumoto, Satoshi*; Takemoto, Noriyuki
JAEA-Technology 2024-016, 247 Pages, 2025/02
JAEA-Technology-2024-016.pdf:28.43MB
Japan Materials Testing Reactor (JMTR, 50MW) was selected as a project to be subsidized by the Ministry of Education, Culture, Sports, Science and Technology (MEXT) for the "Establishment of an International Research and Development Center through Advanced Utilization of the World's Most Advanced Research Reactor". As part of this project, JMTR has installed "LWR Water Environment Simulation Tests" since 2010. This facility can control temperature, pressure, and water quality (dissolved oxygen, dissolved hydrogen, etc.) to simulate the water environment of light water reactors (BWR and PWR) and perform neutron irradiation of in-core structural materials, etc. In addition, this facility is also designed for PWR conditions. Chemical injection system for adding boron and lithium was added to the facility for PWR conditions. After the equipment was installed, test operation was carried out to confirm the performance of the facility. This report summarizes the establishment and test operation of LWR Water Environment Simulation Tests after the establishment.
Isozaki, Futoshi*; Kikuchi, Taiji; Ioka, Ikuo; Ishikawa, Kazuyoshi; Hirata, Yuji*
JAERI-Tech 2002-074, 22 Pages, 2002/09
JAERI-Tech-2002-074.pdf:4.98MB
The pressurized tube specimens which enclosed high pressure inert gas were produced for the irradiation creep test. The pressurized tube specimen with 7mm outer diameter and 0.5mm wall thickness must be sealed by the welding, after the helium gas was impressed in the inside of tube. In this process, there was a technical problem of welding under high pressure, and it is difficult to seal the pressurized tube specimen in the present facility of our group. The production process was examined by taking shortening in production period and reduction in the cost into consideration. The sealing technology to enclose the helium gas up to 5.5MPa was established by new technique using the present facility and the mock-up test. And, it is necessary to measure the outer diameter of the pressurized tube specimen with high accuracy in order to predict irradiation creep deformation arising from neutron radiation and internal pressure. Therefore, the method for measuring at the 0.01mm measurement accuracy was established, which combined laser measuring instrument with the lathe.
Ishikawa, Kazuyoshi; Kikuchi, Taiji; Isozaki, Futoshi*; Inoue, Hiromi; Oba, Toshihiro; Matsui, Yoshinori; Saito, Takashi; Nakano, Junichi; Tsuji, Hirokazu
JAERI-Tech 2002-061, 69 Pages, 2002/08
JAERI-Tech-2002-061.pdf:12.21MB
Study of irradiation assisted stress corrosion cracking (IASCC) is an important subject for the plant life assessment and extension of the light water reactors (LWRs). It is necessary that initiation mechanism of IASCC should be made clear under combined effect of irradiation, environment and stress in order to understand IASCC phenomena. Under the existing circumstance, Saturated Temperature Capsule (SATCAP) were fabricated for the irradiation test of IASCC studies in Japan Material Testing Reactor (JMTR). SATCAP is the irradiation rig to irradiate materials in high pressure water of controlled chemistry and temperature simulating Boiling water reactors (BWRs) core environment from the new water feelding system of out-of-pile. This report describes (1) investigation of technical problems for the design and fabrication of SATCAP, (2) the tests results of the problems and (3) fabrication and inspection of SATCAP.
Oba, Toshihiro; Inoue, Hiromi*; Kikuchi, Taiji; Taka, Isamu; Chiba, Masaaki; Ishikawa, Kazuyoshi; Tsuda, Kazumi*; Takeyama, Tomonori; Isozaki, Futoshi*; Terunuma, Isao*; et al.
NIFS-MEMO-36, p.121 - 124, 2002/06
no abstracts in English
Oba, Toshihiro; Kikuchi, Taiji; Taka, Isamu; Isozaki, Futoshi*; Chiba, Masaaki; Ishikawa, Kazuyoshi; Inoue, Hiromi*; Terunuma, Isao*; Sawabe, Masaki*; Tsuda, Kazumi*; et al.
JAERI-Tech 2001-067, 29 Pages, 2001/11
JAERI-Tech-2001-067.pdf:1.93MB
no abstracts in English
Takeyama, Tomonori; Chiba, Masaaki; Isozaki, Futoshi*; Amezawa, Hiroo; Itabashi, Yukio; Kikuchi, Taiji; Otabe, Yoshikiyo*; Hirata, Yuji*; Taka, Isamu; Oba, Toshihiro
JAERI-Tech 2001-024, 32 Pages, 2001/03
JAERI-Tech-2001-024.pdf:4.41MB
no abstracts in English
Kitagishi, Shigeru; Isozaki, Futoshi; Takita, Kenji; Aoyama, Masashi; Matsui, Yoshinori
no journal, ,
As one of the production of radioisotopes, JMTR has a plan to produce 
Mo which is a parent nuclide of 
Tc. The new hydraulic-rabbit-irradiation-facility is carried out to be set up in the preparation of the Mo production facility. For the expansion of use, the new facility was designed to be able to irradiate rabbits more than it used to be. However, it takes more than about ten days to assemble the rabbit. For this reason, it is required shortening of the assembly period. The improved type of rabbit, which was developed to shorten the assembly period in JRR-3, was focused. And, out-pile tests were carried out for research of the fabrication of the improved type rabbit and the endurance performance under the usage environment in JMTR. In these tests, first, the assembly device for the improved type of rabbit was designed and fabricated, and the fabrication test was carried out using the assembly device. Next, the endurance performance tests were carried out using mock-up rabbits. From the results of these tests, there were bright prospects of the manufacturability of the improved type of rabbit had good sealing performance and utilizing in the irradiation test of JMTR.