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Ueta, Shohei; Shaimerdenov, A.*; Gizatulin, S.*; Chekushina, L.*; Honda, Masaki*; Takahashi, Masashi*; Kitagawa, Kenichi*; Chakrov, P.*; Sakaba, Nariaki
Proceedings of 7th International Topical Meeting on High Temperature Reactor Technology (HTR 2014) (USB Flash Drive), 7 Pages, 2014/10
A capsule irradiation test with the high temperature gas-cooled reactor (HTGR) fuel is being carried out using WWR-K research reactor in the Institute of Nuclear Physics of the Republic of Kazakhstan (INP) to attain 100 GWd/t-U of burnup under normal operating condition of a practical small-sized HTGR. This is the first HTGR fuel irradiation test for INP in Kazakhstan collaborated with Japan Atomic Energy Agency (JAEA) in frame of International Science and Technology Center (ISTC) project. In the test, TRISO coated fuel particle with low-enriched UO
(less than 10% of 
U) is used, which was newly designed by JAEA to extend burnup up to 100 GWd/t-U comparing with that of the HTTR (33 GWd/t-U). Both TRISO and fuel compact as the irradiation test specimen were fabricated in basis of the HTTR fuel technology by Nuclear Fuel Industries, Ltd. in Japan. A helium-gas-swept capsule and a swept-gas sampling device installed in WWR-K were designed and constructed by INP. The irradiation test has been started in October 2012 and will be completed up to the end of February 2015. The irradiation test is in the progress up to 69 GWd/t of burnup, and integrity of new TRISO fuel has been confirmed. In addition, as predicted by the fuel design, fission gas release was observed due to additional failure of as-fabricated SiC-defective fuel.
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.
Tobita, Masahiro*; Matsui, Yoshinori
JAERI-Tech 2003-042, 132 Pages, 2003/03
JAERI-Tech-2003-042.pdf:7.19MB
Prediction of irradiation temperature is one of the important issues in the design of the capsule for irradiation test. Many kinds of capsules with complex structure have been designed for recent irradiation requests, and three-dimensional (3D) temperature calculation becomes inevitable for the evaluation of irradiation temperature. For such 3D calculation, however, many works are usually needed for input data preparation, and a lot of time and resources are necessary for parametric studies in the design. To improve such situation, JAERI introduced 3D-FEM (finite element method) code NISA (Numerically Integrated elements for System Analysis) and developed several subprograms, which enabled to support input preparation works in the capsule design. The 3D temperature calculation of the capsule are able to carried out in much easier way by the help of the subprograms, and specific features in the irradiation tests such as non-uniform gamma heating in the capsule, becomes to be considered.
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.
Tobita, Masahiro*; Itabashi, Yukio
JAERI-Tech 2002-042, 40 Pages, 2002/03
JAERI-Tech-2002-042.pdf:2.09MB
In relation to aging of light water reactors (LWRs), Irradiation Assisted Stress Corrosion Cracking (IASCC) has been regarded as a significant and urgent issue for reliability of in-core components of LWRs. It is essential for IASCC studies to irradiate test materials under well-controlled of Boiling Water Reactor (BWR) conditions simulating the in-core environment. Therefore, the study for the design of the new water control unit to supply high temperature water into saturated temperature capsules in the Japan Materials Testing Reactor (JMTR) has been carried out. This report summarizes the results of estimation using ORIGEN-2 and QAD-CGGP2 codes of dose equivalent rate on outer surface of the concrete wall of installation room and dose equivalent rate around the ion-exchangers where the highest dose equivalent rate is expected in the unit after the reactor shutdown.
Tobita, Masahiro*; Matsui, Yoshinori
KAERI/GP-195/2002, p.87 - 95, 2002/00
In the Japan Materials Testing Reactor (JMTR) of Japan Atomic Energy Research Institute (JAERI), the temperature distribution inside of irradiation specimens and capsules structure material are evaluated in the design of irradiation capsules. For the evaluation of detailed temperature distribution, NISA (Numerically Integrated elements for System Analysis) code has been introduced, and subprograms are developed to simplify the input data of the capsules structure and the analysis conditions using the three-dimensional finite element method. By the development of subprograms, prediction of the temperature distribution inside of irradiation specimens and capsules structure material became detailed and more accurate than calculation by one-dimensional code. Also estimation of detail temperature distribution during irradiation became possible based on the indication of thermocouple.
Kanno, Masaru; Kitajima, Toshio; Homma, Kenzo
KAERI/GP-195/2002, p.71 - 75, 2002/00
Recent irradiation studies aiming at clarifying the detailed mechanisms of irradiation damages to the reactor materials require to maintain the specimens at constant temperature regardless of the reactor power level,in order to avoid artificial effects of temperature transient due to reactor power change. In order to deal with this problem, JMTR has adopted feed-foward control to the gas pressure based on the reactor power signal, and developed new temperature control technique in combination with feedback control of heater power.
Komori, Yoshihiro; Matsui, Yoshinori; Itabashi, Yukio; Yamaura, Takayuki; Nagao, Yoshiharu
KAERI/GP-195/2002, p.59 - 69, 2002/00
JAERI has been developing irradiation technique and facilities for irradiation tests in the JMTR to improve irradiation capability keeping up with progress of nuclear fuels and materials research. This paper summarizes recent development on irradiation technique for the JMTR. Design study and installation of the IASCC (Irradiation Assisted Stress Corrosion Cracking) irradiation test facility was main and the most urgent task of the field in the last five years since two large projects for IASCC were planned in Japan to start irradiation tests in 2002. Almost four years were devoted to preliminary design study, detail design and installation of the facility, then IASCC irradiation test started in March, 2002. Instrumentation technique and capsules development for other research purposes also have been steadily progressing during the term, and new type of off-line temperature monitor, dual re-instrumentation device and the uniform irradiation capsule became available for the irradiation tests.
Komori, Yoshihiro; Amezawa, Hiroo; Komukai, Bunsaku; Narui, Minoru*; Konashi, Kenji*
KAERI/GP-195/2002, p.3 - 10, 2002/00
The actinide-hydride(UTh
Zr
H
) fuel has been studied for transmutation of long-lived actinide contained in the high level wastes and the first irradiation test was successfully carried out in the Japan Materials Testing Reactor (JMTR) of JAERI. Fuel pellets were fabricated by alloying and hydrogenation within an expected diameter error. The fuel pellets were designed to be irradiated below 873K on the fuel surface in consideration of hydrogen dissociation. Irradiation temperature was well agreed with designed value. Fuel burnup reached 0.2%FIMA for two JMTR operation cycles.
Sawa, Kazuhiro; Tobita, Tsutomu*; Takahashi, Masashi; Saito, Takashi; Iimura, Katsumichi; Yokouchi, Iichiro; Serizawa, Hiroyuki; Sekino, Hajime; Ishikawa, Akiyoshi
JAERI-Research 2001-043, 52 Pages, 2001/09
JAERI-Research-2001-043.pdf:14.92MB
no abstracts in English
Abe, Hiroaki
Diamond and Related Materials, 10(3-7), p.1201 - 1204, 2001/07
Times Cited Count：16 Percentile：63.53(Materials Science, Multidisciplinary)no abstracts in English
Matsui, Yoshinori; Itabashi, Yukio; Shimizu, Michio; Tsuji, Hirokazu
Journal of Nuclear Materials, 283-287(Part.2), p.997 - 1000, 2000/12
Times Cited Count：0 Percentile：0.01(Materials Science, Multidisciplinary)no abstracts in English
Sawa, Kazuhiro; Minato, Kazuo
Journal of Nuclear Science and Technology, 36(9), p.781 - 791, 1999/00
Times Cited Count：10 Percentile：60.71(Nuclear Science & Technology)no abstracts in English
March 31, 1995)Department of JMTR
JAERI-Review 96-004, 89 Pages, 1996/03
JAERI-Review-96-004.pdf:3.96MB
no abstracts in English
Sawa, Kazuhiro; Fukuda, Kosaku; R.Acharya*
JAERI-Tech 94-038, 46 Pages, 1995/01
no abstracts in English
Arigane, Kenji; ; Sasajima, Fumio; Takahashi, Hidetake; Seguchi, Tadao; *
JAERI-Tech 94-004, 33 Pages, 1994/07
no abstracts in English
Nakamura, Takehiko; ; Sobajima, Makoto
JAERI-M 94-029, 99 Pages, 1994/03
no abstracts in English
; Hoshiya, Taiji; ; Niimi, Motoji; *
Journal of Nuclear Science and Technology, 30(4), p.291 - 301, 1993/04
Times Cited Count：4 Percentile：44.87(Nuclear Science & Technology)no abstracts in English
Nomura, Yasushi; ;
JAERI-M 92-163, 66 Pages, 1992/11
no abstracts in English
