Tsuchiya, Kunihiko; Mutalib, A.*; Chakrov, P.*; Kaminaga, Masanori; Ishihara, Masahiro; Kawamura, Hiroshi
JAEA-Conf 2011-003, p.137 - 141, 2012/03
As one of effective uses of the JMTR, JAEA has a plan to produce Mo by (n,) method, a parent nuclide of Tc. In case of Japan, the supplying of Mo depends only on imports from foreign countries, the R&D on production method of Mo-Tc has been performed with foreign countries and Japanese industrial users under the cooperation programs. The main R&D items for the production are (1) Fabrication of irradiation target such as the sintered MoO pellets, (2) Separation and concentration of Tc by the solvent extraction from Mo solution, (3) Examination of Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. Especially, it is important to establish the separation and extraction methods in the item (2) and the experiments and information exchanges in some methods have been carried out under the international cooperation. In this paper, the status of the R&D is introduced for the production of Mo-Tc.
Dorn, C. K.*; Tsuchiya, Kunihiko; Hatano, Yuji*; Chakrov, P.*; Kodama, Mitsuo*; Kawamura, Hiroshi
JAEA-Conf 2011-003, p.93 - 97, 2012/03
The JMTR has used beryllium reflector since it began operation in 1968. Beryllium has been used as the reflector element material in the reactor, specifically S-200F structural grade beryllium in JMTR. As a part of the reactor upgrade, the Japan Atomic Energy Agency (JAEA) has carried out the cooperation experiments to extend the operating lifetime of the beryllium reflector elements. Thus, three kinds of beryllium metals such as S-200F, S-65H and I-220H were selected at the viewpoints of production methods, impurities and grain size of beryllium starting powders, mechanical properties. Now, data of the material properties of these beryllium grades are accumulated under un-irradiated and irradiated conditions. In this paper, the results of various properties and irradiation test plan for lifetime expansion of beryllium are described for material testing reactors.
Kawamura, Hiroshi; Ishitsuka, Etsuo; Abdul Farid, M.*; Abdul Karim, J.*; Izumo, Hironobu; Abu, M. P.*; Muhd Yunus, M.*; Hj Khalid, M.*
JAEA-Conf 2011-003, p.277 - 279, 2012/03
This paper will discuss about the outcomes of organizing of 1st Asian Symposium on Materials Testing Reactor (ASMTR 2011). The ASMTR2011 was held from February 16 to 18, 2011 at the Kuala Lumpur, Malaysia. The objective of this symposium is exchange of information among each testing reactors for mutual understanding status of each reactor, and discuss about construction of Asian network for testing reactors. This symposium is jointly organized by Malaysian Nuclear Agency (Nuclear Malaysia) and Japan Atomic Energy Agency (JAEA). Papers were called for the following areas; Status and future plan of testing reactors, Research and development of Irradiation tests include RI and Si semiconductor production technology, Research and development of PIEs, Utilization of testing reactors, Nuclear Human Resource Development, Best practice for Nuclear Non-Proliferation. In this symposium, 47 persons from Asian countries have attended, and the construction of the Asian network for testing reactors was discussed.
Shibata, Akira; Kitagishi, Shigeru; Kimura, Nobuaki; Saito, Takashi; Nakamura, Jinichi; Omi, Masao; Izumo, Hironobu; Tsuchiya, Kunihiko
JAEA-Conf 2011-003, p.185 - 188, 2012/03
To get measurement data with high accuracy for fuel and material behavior studies in irradiation tests, two kinds of measuring equipments have been developed; these are the Electrochemical Corrosion Potential (ECP) sensor, the Linear Voltage Differential Transformer (LVDT) type gas pressure gauge. The ECP sensor has been developed to determine the corrosive potential under high temperature and high pressure water condition. The structure of the joining parts was optimized to avoid stress concentration. The LVDT type gas pressure gauge has been developed to measure gas pressure in a fuel element during neutron irradiation. To perform stable measurements with high accuracy under high temperature, high pressure and high dosed environment, the coil material of LVDT was changed to MI cable. As a result of this development, the LVDT type gas pressure gauge showed high accuracy at 1.8% of a full scale, and good stability.
Miura, Kuniaki*; Shibata, Akira; Nakamura, Jinichi; Ogasawara, Toshihiko*; Saito, Takashi; Tsuchiya, Kunihiko
JAEA-Conf 2011-003, p.193 - 195, 2012/03
In the Fukushima accident, measurement failure of water level was one of the most important factors which caused this serious situation. The differential pressure type water level indicators are widely used in various place of nuclear plant but after the accident of TMI-2, the need of other reliable method has been demanded. And the BICOTH type and the TRICOTH type water level indicator for light water power reactors had been developed for in-pile water level indicator but currently those are not adopted to a nuclear power plant. In this study, the development of new type water level indicator which composed of thermocouple and heater, and the demonstration test and characteristic evaluation of the water level indicator were described.
Takemoto, Noriyuki; Izumo, Hironobu; Hori, Naohiko; Ishitsuka, Etsuo; Suzuki, Masahide
JAEA-Conf 2011-003, p.265 - 269, 2012/03
The JMTR is expected to be a key infrastructure to contribute the nuclear Human Resource Development (HRD) by a research and On-Job-Training (OJT) in order to support global expansion of nuclear power industry. The training program for Asian young researchers and engineers were started from JFY 2011 in JAEA, and ten trainees from Kazakhstan and Thailand had attended in this program in JFY 2011. In addition, in the nuclear HRD initiative program sponsored by the MEXT, the training course was newly established for domestic students and young engineers from JFY 2010 to JFY 2012. In this course, basic understanding on irradiation test and post irradiation examination is aimed to achieve by overall and practical training such as the neutronic/thermal designs of irradiation capsule, post irradiation examination, measurement and evaluation of neutron fluence, etc. using the JMTR and the related facilities. The 1st training course was held with 10 trainees in JFY 2010. The 2nd and 3rd training courses were also held with 19 trainees and 16 trainees in JFY 2011. From JFY 2012, two courses will be held in every year, and 20 trainees will be accepted in each course.
Takemoto, Noriyuki; Imaizumi, Tomomi; Izumo, Hironobu; Hori, Naohiko; Suzuki, Masahide; Ishitsuka, Tatsuo*; Tamura, Kazuo*
JAEA-Conf 2011-003, p.271 - 275, 2012/03
Japan Atomic Energy Agency (JAEA) is now developing a real time simulator for a material testing reactor in order to utilize a nuclear human resource development and promotion of partnership with developing countries which have a plan to introduce nuclear power plant and/or experimental research reactor. The simulator is scheduled to be operated in JFY2012. The simulator is based on Japan Materials Testing Reactor (JMTR), and treats most of JMTR, e.g. reactor, primary cooling system, secondary cooling system, emergency cooling system, instrumentation and control system, safety and protection systems and electricity system. It simulates normal operation condition, transient operation condition such as excess reactivity addition due to testing material insertion and condition of the LOCA. Moreover, it simulates an irradiation experiment using irradiation equipments such as material testing under BWR condition. The simulator is composed of a computer system, a console for reactor control, process control, irradiation equipments, and an instructor and large-size displays. The simulator has the control functions, such as load and store of initial conditions, selection of core conditions, control of execution (run/freeze/fast/slow), save of backtrack snapshots at regular intervals, etc. in order to increase education effects. Furthermore, it has actions, such as malfunctions, remote functions, global component failures, annunciator master control, etc.
Kobayashi, Tetsuya; Araki, Masaaki; Oba, Toshinobu; Torii, Yoshiya; Takeuchi, Masaki*
JAEA-Conf 2011-003, p.83 - 86, 2012/03
Nagata, Hiroshi; Yamaura, Takayuki; Naka, Michihiro; Kawamata, Kazuo; Izumo, Hironobu; Hori, Naohiko; Nagao, Yoshiharu; Kusunoki, Tsuyoshi; Kaminaga, Masanori; Komori, Yoshihiro; et al.
no journal, ,
Conceptual design of the high-performance and low-cost next generation materials testing reactor which will be assumed to introduce to the nuclear power plant introduction country started from 2010 in the JAEA. Japanese atomic energy-related companies participate in this project, and this activity role as the environmental management and nuclear human resource development for the new research reactor designs. 10 MW thermal power by plate type fuel elements and swimming pool type was assumed as a design base. High safety, high cost performance, high reactor operation rate, high technology irradiation are targets of this conceptual design.
Ishimi, Akihiro; Katsuyama, Kozo; Maeda, Koji; Nagamine, Tsuyoshi; Asaka, Takeo
no journal, ,
no abstracts in English
Izumo, Hironobu; Hori, Naohiko; Kaminaga, Masanori; Kusunoki, Tsuyoshi; Ishihara, Masahiro; Komori, Yoshihiro; Suzuki, Masahide; Kawamura, Hiroshi
no journal, ,
The refurbishment project of the JMTR was promoted with two subjects, the one was the replacement of reactor components, and the other was the construction of new irradiation facilities. On the replacement of reactor components, an investigation on aged components was carried out, for concrete structures, tanks, tubes in order to identify their integrity. After the investigation, some components were decided to replace from viewpoints of future maintenance and improvement of reliability. On the construction of new irradiation facilities, corresponding to the user's irradiation request, new irradiation facilities, such as for LWRs materials or fuels, were installed. Furthermore, new project was selected in order to install new irradiation facilities, such as for Mo production and PIE equipments. The new JMTR will contribute the promotion on research and development of the nuclear energy from basic to applied fields as an internationally utilized facility.
Yamashita, Kiyonobu; Murakami, Hiroyuki; Nakagawa, Norio; Arai, Nobuyoshi; Matsuura, Kenichi; Ozeki, Yoshiyuki
no journal, ,
The Nuclear Human Resource Development Center of the Japan Atomic Energy Agency (NuHRDeC/JAEA) has continuously and comprehensively conducted a variety of education and training courses in the nuclear field over a half century since its establishment (1958). The main recent activities are (1) Education and training for domestic nuclear engineers, (2) Education and training for foreign nuclear engineers, (3) Cooperation with domestic universities for nuclear education, (4) Cooperation with international organization for nuclear human resource development, and (5) Central role as secretariat for Japan Nuclear Human Resource Development Network (JN-HRD Net). These recent activity is reported in the meeting.