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Kitagishi, Shigeru; Saito, Takashi; Kikuchi, Taiji; Endo, Yasuichi; Tsuchiya, Kunihiko
Nihon Kikai Gakkai Rombunshu, A, 78(788), p.564 - 570, 2012/04
The development of the friction welded joint between Zircaloy-2 (Zry-2) and Type 316L stainless steel (SUS316L) has been carried out for the fabrication of fuel irradiation capsules in Japan Materials Testing Reactor (JMTR). The welding condition was determined from the fabrication test results of total loss and tensile strength. The joint interface was characterized by metallographic observation, elemental analysis and micro-hardness test. It was found that heat-affected zones at the joint interface were different between the center and outside positions. The tensile strength of the joint was equal to that of base Zry-2 metals at 300
C. And, the joint performance was good from the results of helium leak test and hydraulic pressure burst test. From the results of these tests, it was obvious that the Zry-2/SUS316L friction welded joints were promised to use for the structural material of irradiation capsules for fuel irradiation tests.
Inoue, Shuichi; Yamaura, Takayuki; Saito, Takashi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; Sozawa, Shizuo; Tsuchiya, Kunihiko
JAEA-Technology 2009-076, 33 Pages, 2010/03
JAEA-Technology-2009-076.pdf:18.29MB
In Japan Material Testing Reactor (JMTR), a lot of experiments of fuel irradiation with the power ramping tests have been performed by using the shroud irradiation facility and the Boiling Water Capsule (BOCA). The fuel samples used in these tests were welded to re-instrumentation devices such as thermocouples and FP gas pressures. In this development, the mechanical connection method as "mechanical seal structure", that enables the re-use of re-instrumentation devices, was adopted in order to improve the utilization efficiency of the device. The test samples with mechanical seal structure were fabricated and the confirmatory tests such as He leakage test, thermal cycle test, autoclave test, etc. were carried out. The test samples with the mechanical seal structure showed an excellent result in various confirmatory tests, and the prospect are bright for the re-use of re-instrumentation devices with the mechanical seal structure.
Matsui, Yoshinori; Takahashi, Hiroyuki; Yamamoto, Masaya; Nakata, Masahito; Yoshitake, Tsunemitsu; Abe, Kazuyuki; Yoshikawa, Katsunori; Iwamatsu, Shigemi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; et al.
JAEA-Technology 2009-072, 144 Pages, 2010/03
JAEA-Technology-2009-072.pdf:45.01MB
"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from FY2006 in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupled irradiations or single irradiation by JOYO fast reactor and JRR-3 thermal reactor were performed for about two years. The irradiation specimens are very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we summarized about the overall plan, the work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.
Tomita, Kenji; Tsuchiya, Kunihiko; Onuma, Yuichi; Inoue, Shuichi; Watanabe, Hiroyuki; Saito, Takashi; Kikuchi, Taiji; Hayashi, Kimio; Kitajima, Toshio
JAEA-Technology 2008-036, 61 Pages, 2008/06
JAEA-Technology-2008-036.pdf:7.47MB
The second in-situ irradiation experiment using a mock-up (ORIENT-II, JMTR capsule Number: 99M-54J) with a tritium breeder (Li
TiO
) pebble bed in the Japan Materials Testing Reactor (JMTR) was finished on Aug. 1, 2006. Consideration on the detaching procedure of the irradiated mock-up contaminated with tritium with pebble bed and a detaching test of this mock-up was carried out. The tritium removal properties were examined in the irradiated mock-up, the sweep gas tube, the protective tube and the junction box, for the decreasing of the tritium release to the area of detaching test. Melting/enclosed tests of sealing plug were also carried out for the prevention of tritium leakage from sweep gas lines of pebble bed. Then, the detaching test of the pebble bed was carried out. This report describes the results of tritium removal tests, examination of the detaching procedure, and the detaching test, as well as knowledge obtained from these tests and works.
Kikuchi, Taiji; Ishikawa, Kazuyoshi; Matsui, Yoshinori; Itabashi, Yukio
JAERI-Tech 2004-043, 21 Pages, 2004/03
JAERI-Tech-2004-043.pdf:2.73MB
In the JMTR, the irradiation examinations for nuclear reactor material are usually requested high accurate irradiation temperature, neutron fluence and neutron spectrum. The general demands satisfy to choice the best irradiation hole in the JMTR. However, for more accuracy, it is necessary to produce capsule with special mechanisms. To get the expectant neutron spectrum (ratio of fast neutron and thermal neutron), the thickness of cadmium is calculated by nuclear calculation code. Cadmium is the material to absorb the thermal neutron. Therefore, the necessary thickness was plated the outside of the specimen container with the cadmium. This paper is reported (1) the various base examinations for the development, (2) the result of the evaluations and (3) the evaluation result of an actual irradiation examination about uniform irradiation capsule of the reversing mechanism.
Kikuchi, Taiji; Yamada, Hirokazu*; Saito, Takashi; Nakamichi, Masaru; Tsuchiya, Kunihiko; Kawamura, Hiroshi
JAERI-Tech 2004-026, 28 Pages, 2004/03
JAERI-Tech-2004-026.pdf:2.06MB
Iirradiation capsule for irradiation test of tritium breeder and inner capsule for pebble bed of tritium breeder is inserted. Post irradiation examination of tritium breeder will be performed after irradiation test. On cutting of irradiation capsule, sweep gas line should be sealed to prevent the tritium gas release or inflow of water to sweep gas line. However, general valve and plug cannot apply to sweep gas line sealing because of the effect of neutron irradiation or limited space in irradiation capsule. Therefore, sealing plug for sweep gas line sealing has to be developed. This report shows the development of sealing plug for sweep gas line sealing and operating procedure of sealing plug in irradiation capsule.
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.
Matsui, Yoshinori; Kikuchi, Taiji; Kakuta, Tsunemi
JAERI-Tech 2002-060, 23 Pages, 2002/08
JAERI-Tech-2002-060.pdf:4.42MB
Recently, the number of in-situ tests using optical fibers as signal transmission lines is increasing in the JMTR, because of their noise-tolerant capability and recent development of irradiation proof type fibers. The convensional seal methods, however, have the problem of trust when they applied to the penetration of the irradiation capsule using optical fibers. As the solution of the problem, we selected soldering seal method that was already applied to the deep-sea optical fiber cables and, as its modification, the silver alloy brazing method. From the result of the out-of-pile test, it was confirmed that both soldering seal and silver alloy brazing seal would be applicable to the plug seal of irradiation capsules. Then the soldering seal was applied to a capsule with optical fibers and was irradiated for 5 operation cycles of the JMTR (about 3000 hours). No deterioration was found at the seal after irradiation. This suggested that in-core use of optical fiber was thought to be promising.
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
Matsui, Yoshinori; Ide, Hiroshi; Itabashi, Yukio; Kikuchi, Taiji; Ishikawa, Kazuyoshi; Abe, Shinichi; Inoue, Shuichi; Shimizu, Michio; Iwamatsu, Shigemi; Watanabe, Naoki*; et al.
UTNL-R-0416, p.5_1 - 5_10, 2002/03
no abstracts in English
Matsui, Yoshinori; Ide, Hiroshi; Itabashi, Yukio; Kikuchi, Taiji; Ishikawa, Kazuyoshi; Abe, Shinichi; Inoue, Shuichi; Shimizu, Michio; Iwamatsu, Shigemi; Watanabe, Naoki*; et al.
KAERI/GP-195/2002, p.33 - 40, 2002/00
Studies on the irradiation damage of the material of the RPV are inevitable for the LWR. Recently, the researches of annealing effect on the irradiation damage of RPV material were extensively carried out using specimens irradiated in the JMTR of the JAERI. As the next step, an annealing test of irradiated specimens and re-irradiation of annealed specimens were planned. The aim of the test is to evaluate the effect of annealing by comparing the damage of irradiated specimen, its recovery by annealing and the damage after re-irradiation. For the re-irradiation test of this study, JAERI developed a new capsule in which the specimens can be exchanged before and after annealing, and, re-irradiated afterward. The development of the capsule consisted of the design and fabrication of airtight connector for thermocouples and mechanical seal device which was fit to remote handling. Remote operation procedures for handling the radioactive capsule and for exchanging specimens were carefully performed. The results of the re-irradiation proved that the development was technically successful.
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
Kurata, Yuji; Itabashi, Yukio; Mimura, Hideaki*; Kikuchi, Taiji; Amezawa, Hiroo; Shimakawa, Satoshi; Tsuji, Hirokazu; Shindo, Masami
Journal of Nuclear Materials, 283-287(Part.1), p.386 - 390, 2000/12
Times Cited Count：6 Percentile：41.99(Materials Science, Multidisciplinary)no abstracts in English
Tsuchiya, Kunihiko; Kawamura, Hiroshi; Kikuchi, Taiji
Interface Science and Materials Interconnection, p.455 - 458, 1996/00
no abstracts in English
Kikuchi, Taiji; Kawamura, Hiroshi
JAERI-M 88-150, 30 Pages, 1988/08
no abstracts in English
Maeda, Akio; Oyama, Koji; Kikuchi, Taiji
no journal, ,
no abstracts in English
Matsui, Yoshinori; Takahashi, Hiroyuki; Ichise, Kenichi; Usami, Koji; Endo, Shinya; Iwamatsu, Shigemi; Yonekawa, Minoru; Ito, Kazuhiro; Yamamoto, Masaya; Soga, Tomonori; et al.
no journal, ,
"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from 2006 fiscal year in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupling irradiations or single irradiations by JOYO fast reactor and JRR-3 fission reactor were performed for about two years. The irradiation specimens are the very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we will present about the overall plan, work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.
Matsui, Yoshinori; Nabeya, Hideaki; Kusunoki, Tsuyoshi; Takahashi, Hiroyuki; Aizawa, Masao; Nakata, Masahito; Numata, Masami; Usami, Koji; Endo, Shinya; Ito, Kazuhiro; et al.
no journal, ,
We are proceeding with the study of "R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant". For the study, it is important that the irradiated specimens are gotten by the coupling of JRR-3 and JOYO. This reports the total irradiation plan in the study, and the executed work for the coupling irradiation (JRR-3 and JOYO) including the Hot facilities work of Tokai and Oarai in the 2006 fiscal year.
Usami, Koji; Ichise, Kenichi; Numata, Masami; Endo, Shinya; Onozawa, Atsushi; Takahashi, Hiroyuki; Kikuchi, Taiji; Ishikawa, Kazuyoshi; Yoshikawa, Katsunori; Nakata, Masahito; et al.
no journal, ,
In the R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant, the specimens to be obtained by coupling irradiation between JOYO and JRR-3 is necessary to establish the evaluation method by using the irradiation damage indicator of them. Therefore, the techniques for assembling of JRR-3 re-irradiation capsule in the Waste Safety Testing Facility (WASTEF) were developed to perform the coupling irradiation. The techniques contributed to the first coupling irradiation in the world.
