Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Onozawa, Atsushi; Harada, Akio; Honda, Junichi; Nakata, Masahito; Kanazawa, Hiroyuki; Sagawa, Tamio
JAEA-Conf 2008-010, p.325 - 332, 2008/12
The measurement technique for hydrogen concentration using Backscattered Electron Image analysis (BEI method) had been developed by Studsvik Nuclear AB. The hydride in claddings is identified using BEIs with SEM and the hydrogen concentration is calculated from the area fractions of the hydride in those BEIs. In the RFEF, the sample polishing techniques and image processing procedure for BEI method were improved to measure the hydrogen concentration in the irradiated fuel claddings more precisely. In the previous tests using the un-irradiated fuel claddings, it is confirmed improved BEI method has high reliability. The radial and axial hydrogen concentration profiles of the irradiated fuel claddings were measured with improved BEI method. As the results of these measurements, the local hydrogen concentration could be indicated more precisely with the improved BEI method compared to the other methods for the hydrogen concentration measurement and observation.
Shibata, Akira; Omi, Masao; Nakagawa, Tetsuya
JAEA-Conf 2008-010, p.54 - 66, 2008/12
The hot laboratory accompanied with the Japan Materials Testing Reactor (JMTR-HL) was founded in 1971 to examine objects irradiated mainly at the JMTR. The JMTR-HL has three kinds of beta-
hot-cell lines for research and development of nuclear fuels and materials. The JMTR-HL has the advantage of being connected by a canal between the hot cell and the JMTR. Hence it is easy to transport irradiated capsules and specimens through the canal. Since 1971, about 2,400 irradiated capsules have been treated in the JMTR-HL. Many various post irradiation examinations (PIEs) have been widely performed here. Mentioned in this report are overview of the hot laboratory, the present organization, the current status of the PIEs, and the modification plan of the facility to treat high burn-up fuels up to about 100 GWD/t in this presentation.
Taguchi, Taketoshi; Sozawa, Shizuo; Hanawa, Yoshio; Kitagishi, Shigeru; Tsuchiya, Kunihiko
JAEA-Conf 2008-010, p.343 - 352, 2008/12
Beryllium has been utilized as a moderator and/or reflector in Japan Materials Testing Reactor (JMTR), because of nuclear properties of beryllium, low neutron capture and high neutron scattering cross sections. At present, it is necessary to exchange the beryllium frames within every fixed period; frames were exchanged five times up to the JMTR operation periods of 165th cycles, and amount of irradiated beryllium frames in JMTR is about 2 tons in the JMTR canal. In this study, preliminary irradiation test with two kinds of beryllium metals (S-200F and S-65C) was performed from 162nd to 165th operation cycles of JMTR as irradiation and PIE technique development for lifetime expansion of beryllium frames. The design study of irradiation capsule, development of dismount device of irradiation capsule and the high accuracy size measurement device were carried out. The results of PIEs such as tensile tests, metallurgical observation, and size change measurement were presented in this seminar.
Taguchi, Taketoshi; Inaba, Yoshitomo; Kawamata, Kazuo; Nakagawa, Tetsuya; Tsuchiya, Kunihiko
JAEA-Conf 2008-010, p.193 - 202, 2008/12
The JMTR-HL is directly connected with reactor core by a water canal. Hence irradiated radioactive capsules are efficiently transported under water through the canal in a short time. As the part of PIE technology development, several kinds of welding techniques have been systematically developed. These techniques are as follows; (1) re-instrumentation of FP gas pressure gauge and thermocouple to an irradiated fuel rod, (2) welding procedure development for re-capsuling of irradiated materials, (3) joining technique and PIEs development of different materials with friction welding for new typed irradiation capsules and (4) rewelding with irradiated and un-irradiated materials and fabrication of test specimen with the rewelding for fusion reactor development. These welding techniques have been very indispensable for supporting the irradiation tests and post-irradiation examinations and were introduced in this seminar.
Iimura, Koichi; Hosokawa, Jinsaku; Izumo, Hironobu; Hori, Naohiko; Nakagawa, Tetsuya; Kanno, Masaru; Kawamura, Hiroshi
JAEA-Conf 2008-010, p.251 - 258, 2008/12
At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) being advanced is the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in FY 2011. As one of effective use of the JMTR, JAEA has a plan to product 
Mo, a parent nuclide of 
Tc. Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of Mo depends only on imports from foreign countries, therefore JAEA is aiming at domestic production of a part of Mo in cooperation with industrial users. As JAEA's activities, mentioned are the process, the selection and fabric of the irradiation facilities for Mo production, the technical study of commercializing equipment after irradiation, and the cost evaluation for Mo production.
Inaba, Yoshitomo; Inoue, Shuichi; Izumo, Hironobu; Kitagishi, Shigeru; Tsuchiya, Kunihiko; Saito, Takashi; Ishitsuka, Etsuo
JAEA-Conf 2008-010, p.30 - 41, 2008/12
Irradiation Engineering Section of the Neutron Irradiation and Testing Reactor Center was organized to development the new irradiation technology for the application at JMTR re-operation. The new irradiation engineering building was remodeled from the old building for RI development, and will be used from the end of September, 2008. Advanced in-situ instrumentation technology (high temperature multi-paired thermocouple, ceramic sensor, application of light measurement), Mo production technology by the new Mo solution irradiation method, recycling technology on used beryllium reflector, and so on are planned as the development of new irradiation technologies. The development will be also important for the education and training program through the development to young generation in not only Japan but also Asian counties. In this seminar, as the status of the new irradiation technology development, new irradiation engineering building, high temperature multi-paired thermocouple, experiences of light measurement, recycling technology on used beryllium reflector will be introduced.
Takemoto, Noriyuki; Hanawa, Yoshio; Gorai, Shigeru; Fukasaku, Akitomi; Miyazawa, Masataka; Niimi, Motoji
JAEA-Conf 2008-010, p.97 - 105, 2008/12
Operation of the Japan Materials Testing Reactor (JMTR), a light-water-cooling tank-type reactor with a 50 MW thermal power, was stopped in August 2006, and now its refurbishment is on going. The reactor facilities are to be refurbished during four years from the beginning of FY 2007, and the renewed JMTR will be operated from FY 2011 until around FY 2030. As for the decision of the refurbishment, reactor facilities to be renewed and to be continuously used were selected from a viewpoint of ensuring safety, improvement of availability-factor, etc. The selected renewal reactor facilities were the reactor instrument and control system, cooling system, radioactive waste facility, power supply system, boiler, etc. Presented are the basic idea on selection of the renewal facilities, outline of these facilities and schedule of refurbishment work.
Mo production technology by molybdenum solution irradiation methodInaba, Yoshitomo; Ishikawa, Koji*; Ishida, Takuya; Tatenuma, Katsuyoshi*; Ishitsuka, Etsuo
JAEA-Conf 2008-010, p.259 - 267, 2008/12
Tc for the medical diagnosis is the most widely used radioisotope in the world and it's demand is growing up year by year. In case of Japan, all Mo which is parent nuclide of Tc, is imported. However, the importance of the domestic production is pointed out from a viewpoint of the stable supply of Mo because of some troubles on transportation or the research reactor, and so on. Therefore, the (n,) method using solid molybdenum target had been planned in JMTR. However, it will be difficult to satisfy domestic demand because of the limited irradiation volumes of the hydraulic rabbit irradiation facility. In order to increase the amount of Mo production, the molybdenum solution irradiation method was proposed as a new production method. This method is based on the neutron irradiation of molybdenum solution, and several advantages can be pointed out such as a large irradiation volume, high efficient and low cost comparing with conventional methods using enriched 
U(n,f)Mo as the major method or using a solid molybdenum target of MoO
as the minor (n,) method. Aiming at the realization of the molybdenum solution irradiation method, un-irradiated and ray irradiated tests of the molybdenum solution were carried out, and the data of chemical stability and compatibility with the structural materials were shown.
Tanaka, Kosuke; Hirosawa, Takashi; Obayashi, Hiroshi; Koyama, Shinichi; Yoshimochi, Hiroshi; Tanaka, Kenya
JAEA-Conf 2008-010, p.288 - 296, 2008/12
In order to investigate the effect of americium addition to MOX fuels on the irradiation behavior, the "Am-1" program is being conducted in JAEA. The Am-1 program consists of two short-term irradiation tests of 10-minute and 24-hour irradiations and a steady-state irradiation test. The short-term irradiation tests were successfully completed and the post irradiation examinations (PIEs) are in progress. The PIEs for Am-containing MOX fuels focused on the microstructural evolution and redistribution behavior of Am at the initial stage of irradiation and the results to date are reported.
Sasaki, Shinji; Abe, Kazuyuki; Nagamine, Tsuyoshi
JAEA-Conf 2008-010, p.362 - 371, 2008/12
An innovative technique to measure the deformation of irradiated wrapper tube of FBR fuel assembly was developed, and installed in the hot cell of the Fuels Monitoring Facility in JAEA. In order to confirm the performance of this instrument, a number of measurements were carried out in the wrapper tubes irradiated to high burnup in the experimental fast reactor Joyo. In the instrument used until now, only three face to face distances in the hexagonal wrapper tube have been measured along the axial direction. On the other hand, in the instrument developed in this technique the face to face distances could be continuously measured along the lateral direction in the outer surfaces of wrapper tube. Using data obtained by this technique, the detailed analyses of deformation can be done throughout a whole wrapper tube.
Kishi, Toshiaki; Ichimura, Shigeju; Kinase, Masami; Wada, Shigeru
JAEA-Conf 2008-010, p.146 - 158, 2008/12
The Department of Research Reactor and Tandem Accelerator operates three research reactors, JRR-3, JRR-4 and NSRR. JRR-3 was operated for 180 days in Japanese Fiscal Year 2007. The neutron bender system was installed on the cold neutron guide tube. As a result, the cold beam intensity has increased by about 10 times. JRR-4 was operated for 93 days in Japanese Fiscal Year 2007. Boron neutron capture therapy was carried out 25 times. The trouble of reflector occurred in December 2007. At present, the reactor has stopped to replace the reflectors. NSRR has been built for the investigation of light water reactor fuel behavior during off-normal conditions such as reactivity-initiated accident. Recently the investigation is performed for the behavior of high burnup fuel and mixed oxide fuel. At present, the NSRR experiments with the new capsule are continuing for high burnup fuels of 59, 67 and 71 GWd/t.
Nishinoiri, Kenji; Akasaka, Naoaki; Ogawa, Ryuichiro; Inoue, Toshihiko
no journal, ,
In fast reactor, deformation behavior and failure strength of fuel cladding tube (C/T) under loss of coolant flow (LOF) event are important evaluation items of reactor safeties. To evaluate C/T behavior under the primary phase of LOF event, transient bust examination was conducted by neutron irradiated C/T. Specimens of C/T made of PNC316 were irradiated in experimental fast reactor JOYO. In this paper reported the transient burst techniques and the results of the post irradiated examination. In the results, the failure temperature of irradiated C/T has no extreme degradation by comparison of the failure temperature of un-irradiated C/T.
Kawamura, Hiroshi; Niimi, Motoji; Ishihara, Masahiro; Miyazawa, Masataka; Hori, Naohiko; Nagao, Yoshiharu
no journal, ,
The Japan Materials Testing Reactor (JMTR) of Japan Atomic Energy Agency (JAEA) is a light water cooling tank typed reactor with first criticality in March 1968. The JMTR has been applied to fuel/material irradiation examinations for LWRs, HTGR, fusion reactor and RI production. Owing to the connection between the JMTR and hot laboratory by a canal, easy re-irradiation tests can conduct with safety and quick transportation of irradiated samples. The JMTR operation was stopped in August 2006 in order to conduct its refurbishment. The reactor facilities will be refurbished during four years from the beginning of FY 2007, and necessary examination and work are carrying out on schedule. The renewed JMTR will be started from FY 2011, and be operated for a period of about 20 years (until around FY 2030). The usability improvement of the JMTR, e.g. higher reactor available factor, shortening turnaround time to get irradiation results, attractive irradiation cost, business confidence, is also discussing as the preparations for re-operation.
Hori, Naohiko; Izumo, Hironobu; Kanno, Masaru; Nakagawa, Tetsuya; Kawamura, Hiroshi
no journal, ,
At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) is advancing the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation from FY 2011. At the JMTR, the iridium-192 (192Ir) source for the medical treatment as well as for the industrial using in the non-destructive inspection has been irradiated. As one of effective use of the renewed JMTR, JAEA has a plan to product molybdenum-99 (99Mo), a parent nuclide of technetium-99 (99mTc). 99mTc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Furthermore, production of radioisotope (RI) for which increasing demand is expected, e.g. rhenium-188 (188Re) which being expected as a cancer treatment medicine.
Hanawa, Satoshi; Ogiyanagi, Jin; Chimi, Yasuhiro; Sasajima, Hideo; Nakamura, Jinichi; Nishiyama, Yutaka; Nakamura, Takehiko
no journal, ,
A continuous endeavor for solving irradiation-related issues on the fuels for high-duty uses and the plant aging are essential to realize the up-graded uses of LWR safely. In order to respond adequately to these demand, Japanese regulator has decided to install new irradiation test facilities in the Japan Material Testing Reactor (JMTR) at the Japan Atomic Energy Agency (JAEA). For the fuels tests, transient tests facility is being constructed for the power transient tests of new design BWR fuels. For the materials tests, the irradiation test loops under well controlled environment simulating BWR water chemistry condition and a large irradiation capsule, which can accommodate 1 inch-thickness compact tension specimens in an inert gas environment, are being prepared for the researches on stress corrosion cracking and irradiation embrittlement, respectively. These fuels and materials irradiation tests will be started in 2011 after refurbishment of JMTR.
