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JAEA Reports

Conceptual design of multipurpose compact research reactor; Annual report FY2011

Watahiki, Shunsuke; Hanakawa, Hiroki; Imaizumi, Tomomi; Nagata, Hiroshi; Ide, Hiroshi; Komukai, Bunsaku; Kimura, Nobuaki; Miyauchi, Masaru; Ito, Masayasu; Nishikata, Kaori; et al.

JAEA-Technology 2013-021, 43 Pages, 2013/07

JAEA-Technology-2013-021.pdf:5.12MB

The number of research reactors in the world is decreasing because of their aging. On the other hand, the necessity of research reactor, which is used for human resources development, progress of the science and technology, industrial use and safety research is increasing for the countries which are planning to introduce the nuclear power plants. From above background, the Neutron Irradiation and Testing Reactor Center began to discuss a basic concept of Multipurpose Compact Research Reactor (MCRR) for education and training, etc., on 2010 to 2012. This activity is also expected to contribute to design tool improvement and human resource development in the center. In 2011, design study of reactor core, irradiation facilities with high versatility and practicality, and hot laboratory equipment for the production of Mo-99 was carried out. As the result of design study of reactor core, subcriticality and operation time of the reactor in consideration of an irradiation capsule, and about the transient response of the reactor to the reactivity disturbance during automatic control operation, it was possible to do automatic operation of MCRR, was confirmed. As the result of design study of irradiation facilities, it was confirmed that the implementation of an efficient mass production radioisotope Mo-99 can be expected. As the result of design study with hot laboratory facilities, Mo-99 production, RI export devised considered cell and facilities for exporting the specimens quickly was designed.

JAEA Reports

Conceptual design for simulator of irradiation test reactors

Takemoto, Noriyuki; Oto, Tsutomu; Magome, Hirokatsu; Izumo, Hironobu; Hori, Naohiko

JAEA-Technology 2012-011, 53 Pages, 2012/03

JAEA-Technology-2012-011.pdf:4.22MB

A simulator of irradiation test reactors has been developed since JFY 2010 for understanding reactor behavior and for upskilling in order to utilize for a nuclear human resource development (HRD) and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the one of the irradiation test reactors, the JMTR, and it simulates operating, irradiation tests and various kinds of accidents caused in the reactor and the irradiation facility. The development of the simulator is sponsored by the Japanese government as one of the specialized projects of advanced research infrastructure in order to promote basic as well as applied researches. The training of operation using the simulator will be started for the nuclear HRD from JFY 2012. This report summarizes the result of the conceptual design of the simulator in JFY 2010.

JAEA Reports

Newly organized training course using JMTR and related facilities as advanced research infrastructures

Imaizumi, Tomomi; Takemoto, Noriyuki; Izumo, Hironobu; Ide, Hiroshi; Matsui, Yoshinori; Sozawa, Shizuo; Hori, Naohiko

JAEA-Review 2012-012, 25 Pages, 2012/03

JAEA-Review-2012-012.pdf:4.21MB

A training course using JMTR and the related facilities was newly organized for domestic students and young engineers from FY 2010 from a viewpoint of nuclear Human Resource Development (HRD) in order to support global expansion of nuclear power industry. In FY2010, preparation for the training course was curried out and the 1st training course was held on February 14 to 25, 2011 with ten domestic students as a trainie. In this training course, mainly carried out was practical training of neutronic calculation for an irradiation test about the hydraulic rabbit irradiation facility which is one of the irradiation facilities in the JMTR. This report summarizes outline of training course using cutting-edge research infrastructure JMTR and the related facilities and result of the 1st training course.

Journal Articles

Report of the 1st Asian Symposium on Materials Testing Reactor

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.

Journal Articles

Development of in-pile instruments for fuel and material irradiation tests

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.

Journal Articles

Training program for students and young engineers in JMTR

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.

Journal Articles

Real time simulator for material testing reactor

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.

JAEA Reports

Status of international cooperation in nuclear technology on testing/research reactors between JAEA and INP-NNC

Kawamura, Hiroshi; Chakrov, P.*; Tsuchiya, Kunihiko; Gizatulin, S.*; Takemoto, Noriyuki; Chakrova, Y.*; Kimura, Akihiro; Ludmila, C.*; Tanimoto, Masataka; Asset, S.*; et al.

JAEA-Review 2011-042, 46 Pages, 2012/02

JAEA-Review-2011-042.pdf:2.69MB

Based on the implementing agreement between National Nuclear Center of the Republic of Kazakhstan (NNC) and the Japan Atomic Energy Agency (JAEA) for the Nuclear Technology on Testing/Research Reactors in the cooperation in Nuclear Energy Research and Development in Nuclear Energy and Technology, four specific topics of cooperation (STC) have been carried out from June, 2009. Four STCs are as follows; (1) STC No.II-1: International Standard of Instrumentation, (2) STC No.II-2: Irradiation Technology of RI Production, (3) STC No.II-3: Lifetime Expansion of Beryllium Reflector, (4) STC No.II-4: Irradiation Technology for NTD-Si. The information exchange, personal exchange and cooperation experiments are carried out under these STCs. The status in the field of nuclear technology on testing/research reactors in the implementing arrangement is summarized, and future plans of these specific topics of cooperation are described in this report.

JAEA Reports

Conceptual design of multipurpose compact research reactor; Annual report FY2010 (Joint research)

Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.

JAEA-Technology 2011-031, 123 Pages, 2012/01

JAEA-Technology-2011-031.pdf:16.08MB

The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.

Journal Articles

Proposal of world network on material testing reactors

Takemoto, Noriyuki; Izumo, Hironobu; Hori, Naohiko; Ishitsuka, Etsuo; Ishihara, Masahiro

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 4 Pages, 2011/12

Establishment of a world network is proposed to achieve efficient facility utilization and provide high quality irradiation data by role sharing of irradiation tests with materials testing reactors in the world. As for the first step, mutual understanding among materials testing reactors is thought to be necessary. From this point, an international symposium on materials testing reactors (ISMTR) was held to construct the world network from 2008 every year, and a common understanding of world network has begun to be shared. The ISMTR-5 will be held on USA in 2012, and the ISMTR-6 will be held on Argentine in 2013.

JAEA Reports

Survey of LEU based $$^{99m}$$Tc generators loading process

Tanimoto, Masataka; Amaya, D.*; Aoyama, Masashi; Kimura, Akihiro; Izumo, Hironobu; Tsuchiya, Kunihiko

JAEA-Review 2011-012, 13 Pages, 2011/06

JAEA-Review-2011-012.pdf:2.1MB

$$^{99m}$$Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine, accounting for more than 80% of all diagnostic nuclear medicine procedure. The $$^{99m}$$Tc is obtained from $$^{99}$$Mo, which is produced by fission of $$^{235}$$U ((n, f) method) and the neutron capture (n, $$gamma$$) method using the $$^{98}$$Mo target. However, a supplying of $$^{99}$$Mo is only depends on imports from any other countries, so JAEA find a way out at domestic production of a part of $$^{99}$$Mo that (n, $$gamma$$) method in cooperation with the industrial circles. On the other hand, INVAP has been working in the supply of $$^{99}$$Mo production facilities using LEU. This report provides descriptions the detail technical aspects related to the facility and operations for loading $$^{99m}$$Tc generator. These key issues and technical provided in this report is believed to be useful for developing and updating them.

Journal Articles

Status of development on $$^{99}$$Mo production technologies in JMTR

Inaba, Yoshitomo; Iimura, Koichi; Hosokawa, Jinsaku; Izumo, Hironobu; Hori, Naohiko; Ishitsuka, Etsuo

IEEE Transactions on Nuclear Science, 58(3), p.1151 - 1158, 2011/06

 Times Cited Count:4 Percentile:36.36(Engineering, Electrical & Electronic)

The Japan Materials Testing Reactor (JMTR) is now under refurbishment, and the operation of the new JMTR will start in FY 2011. The new JMTR has a plan to produce $$^{99}$$Mo, which is the parent nuclide of $$^{99m}$$Tc, and two $$^{99}$$Mo production technologies have been developed: one is a solid irradiation method, and the other is a solution irradiation method. In this paper, the present status of the development on the $$^{99}$$Mo production technologies with the solid and solution irradiation methods was described. In the solid irradiation method, it was found that JMTR can provide about 20% of the $$^{99}$$Mo imported into Japan. In the solution irradiation method, the fundamental characteristics of the aqueous molybdate solutions selected as candidates for the irradiation target were cleared by the $$gamma$$-ray irradiation test.

JAEA Reports

Survey of LEU based $$^{99}$$Mo production process

Tanimoto, Masataka; Amaya, D.*; Aoyama, Masashi; Kimura, Akihiro; Izumo, Hironobu; Tsuchiya, Kunihiko

JAEA-Review 2011-002, 26 Pages, 2011/03

JAEA-Review-2011-002.pdf:1.46MB

Recently, worldwide demand of $$^{99}$$Mo became rises. However the availability and supply of $$^{99}$$Mo for the manufacturing of generators has been a matter of concern. Concern arose from several factors including, amongst others, the shutdown of some nuclear reactors at Canada (NRU, etc.), uncertainty of reliable operating condition for radioisotope production and difficulties in the availability of highly enriched $$^{235}$$U (HEU) target material used in the majority of the production facilities. As countermeasure for this issue, the HEU is not used but $$^{99}$$Mo production from low enriched $$^{235}$$U (LEU) is performed. This production process was developed in Argentina by the Argentine Atomic Energy Commission (CNEA). In the last ten years, INVAP has been working in the supply of $$^{99}$$Mo production facilities using LEU. This report provides descriptions for the detail technical aspects related to a $$^{99}$$Mo production system using irradiated LEU targets.

Journal Articles

$$^{99}$$Mo production plan from $$^{98}$$Mo by (n,$$gamma$$) reaction in JMTR

Izumo, Hironobu; Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Tanase, Masakazu*; Fujisaki, Saburo*; Ota, Akio*

Proceedings of 1st Asian Symposium on Material Testing Reactors (ASMTR 2011), p.77 - 82, 2011/02

no abstracts in English

JAEA Reports

Feasibility study on mass production of (n,$$gamma$$)$$^{99}$$Mo

Jun, B. J.; Tanimoto, Masataka; Kimura, Akihiro; Hori, Naohiko; Izumo, Hironobu; Tsuchiya, Kunihiko

JAEA-Research 2010-046, 103 Pages, 2011/01

JAEA-Research-2010-046.pdf:2.63MB

The world is currently suffering from a severe shortage of $$^{99}$$Mo and various R&Ds have been given for its availability. The only but critical shortage of (n,$$gamma$$)$$^{99}$$Mo is its extremely low specific activity, which gives inconveniency in the extraction of $$^{99m}$$Tc and is consequently converted to additional cost. Potential technologies which make the (n,$$gamma$$)$$^{99}$$Mo competitive by reducing the additional cost are already available. Because Japan and Korea import all $$^{99}$$Mo from long distance, the cost benefit of local (n,$$gamma$$)$$^{99}$$Mo production in these countries is especially large. In this report, we studied feasibility of the mass (n,$$gamma$$)$$^{99}$$Mo production from viewpoints of global and regional status of $$^{99}$$Mo demand and supply, competitiveness with other production methods, requirements and flow of the $$^{99}$$Mo, production capability, cost, convenience in usage, and alternative technologies to overcome its shortage.

JAEA Reports

Retesting of $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution characteristics of molybdenum adsorbents for (n,$$gamma$$) method; Joint experiment report on irradiation technology of RI production (STC No.2$$-$$II) (Joint research)

Kimura, Akihiro; Izumo, Hironobu; Tsuchiya, Kunihiko; Hori, Naohiko; Ishihara, Masahiro; Bannykh, V.*; Gluschenko, N.*; Chakrova, Y.*; Chakrov, P.*

JAEA-Testing 2010-002, 20 Pages, 2010/08

JAEA-Testing-2010-002.pdf:2.92MB

JMTR has a plan to produce $$^{99}$$Mo, which is the parent nuclide of radiopharmaceutical $$^{rm rm 99m}$$Tc, by (n,$$gamma$$) method. The cooperation experiments for $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution with the Poly-Zirconium Compound (PZC) and the Molybdate Zirconium Gel (Zr-gel) methods were carried out at Kazakhstan National Nuclear Energy Center (NNC) in October, 2009. The $$^{99}$$Mo adsorption capability was the same level as reference data, however the $$^{rm 99m}$$Tc elution capability with PZC was lower than reference data in this test. Therefore, re-experiments of $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution with both methods were carried out at NNC. As a result, the $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution capabilities were obtained as the same levels as reference data. Additionally, $$^{rm 99m}$$Tc solution was high purity by the elution method connected with alumina column.

JAEA Reports

Revaluation of $$^{99}$$Mo production by (n,$$gamma$$) method at HANARO

Jun, B. J.; Lee, B. C.*; Kimura, Akihiro; Hori, Naohiko; Izumo, Hironobu; Tsuchiya, Kunihiko

JAEA-Review 2010-032, 26 Pages, 2010/07

JAEA-Review-2010-032.pdf:2.52MB

After the feasibility study on $$^{99}$$Mo production by (n,$$gamma$$) method at HANARO was published by a KAERI report, worldwide supply of $$^{99}$$Mo became worse and a need for early available alternative $$^{99}$$Mo became stronger. Previous study indicated that the (n,$$gamma$$)$$^{99}$$Mo has a potential to be an alternative mass $$^{99}$$Mo available earlier than those by any other methods. It can be realized when radioisotope industry of each country accepts the use of (n,$$gamma$$)$$^{99}$$Mo for a meaningful portion of national demand. A good backup supply system among high flux reactors in the region is a prerequisite to guarantee a stable and sufficient availability of the (n,$$gamma$$)$$^{99}$$Mo for the region, for which active collaboration among reactors is essential. As the initial stage of collaboration between HANARO and JMTR for the (n,$$gamma$$)$$^{99}$$Mo supply, the specific experience and $$^{99}$$Mo production capability in HANARO have been discussed and revisited on the base of the previous report.

JAEA Reports

Conceptual study for new $$^{99}$$Mo-production facility in JMTR

Kimura, Akihiro; Iimura, Koichi; Hosokawa, Jinsaku; Izumo, Hironobu; Hori, Naohiko; Nakagawa, Tetsuya; Kanno, Masaru; Ishihara, Masahiro; Kawamura, Hiroshi

JAEA-Review 2009-072, 18 Pages, 2010/03

JAEA-Review-2009-072.pdf:9.29MB

JAEA has a plan to produce $$^{99}$$Mo, a parent nuclide of $$^{99m}$$Tc. At present, radioisotopes are indispensable for a diagnosis and treatment in the medical field. Demand of $$^{99m}$$Tc (half life 6h) used as a radiopharmaceutical increases up year by year. Moreover, the expansion of demand will be expected in future. However, the supply of $$^{99}$$Mo in Japan depends fully on the import from foreign countries. Therefore, it is necessary to supply $$^{99}$$Mo stably by the domestic production. There are two methods of $$^{99}$$Mo (half life 65.9h) production; the one is the nuclear fission (n,fiss) method, and the other is the (n,$$gamma$$) method using the $$^{98}$$Mo target. $$^{99}$$Mo production in the JMTR with the (n,$$gamma$$) method was studied and evaluated. As a result, it was found that the partial amount of $$^{99}$$Mo demand is possible to supply stably if a new hydraulic-rabbit-irradiation-facility (HR) is used.

JAEA Reports

$$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution characteristics of molybdenum adsorbents for (n,$$gamma$$); Method-joint experiment report on irradiation technology of RI production (STC No. 2-II) (Joint research)

Kimura, Akihiro; Izumo, Hironobu; Tsuchiya, Kunihiko; Hori, Naohiko; Ishihara, Masahiro; Bannykh, V.*; Gluschenko, N.*; Chakrova, Y.*; Chakrov, P.*

JAEA-Technology 2009-075, 23 Pages, 2010/02

JAEA-Technology-2009-075.pdf:7.41MB

Japan Materials Testing Reactor (JMTR) of the Japan Atomic Energy Agency (JAEA) has a plan to produce $$^{99}$$Mo, which is the parent nuclide of radiopharmaceutical $$^{rm 99m}$$Tc, by (n,$$gamma$$) method. The $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution characteristics of molybdenum adsorbents should be evaluated since the specific activity of $$^{99}$$Mo obtained by (n,$$gamma$$) method is low. Therefore, $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution tests with molybdenum adsorbents for the (n,$$gamma$$) method such as poly-zirconium compound (PZC) and molybdate zirconium gel were carried out under cooperation with the Kazakhstan National Nuclear Energy Center (NNC). As a result, the $$^{99}$$Mo adsorption performance of the adsorbents was the same level as conventional data, whereas the $$^{rm 99m}$$Tc elution performance of the adsorbents was lower than conventional data. The $$^{99}$$Mo adsorption and $$^{rm 99m}$$Tc elution performance will be investigated again in future.

Journal Articles

Status of development on $$^{99}$$Mo production technologies in JMTR

Inaba, Yoshitomo; Iimura, Koichi; Hosokawa, Jinsaku; Izumo, Hironobu; Hori, Naohiko; Ishitsuka, Etsuo

Proceedings of 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA 2009) (USB Flash Drive), 8 Pages, 2009/06

The Japan Materials Testing Reactor (JMTR) is now under refurbishment, and the operation of the new JMTR will be started in FY 2011. The new JMTR has a plan to produce $$^{99}$$Mo, which is the parent nuclide of $$^{99m}$$Tc, and two $$^{99}$$Mo production technologies have been developed; the one is a solid irradiation method, and the other is a solution irradiation method. $$^{99}$$Mo production in the JMTR will be started by the solid irradiation method, and it was found that the JMTR can produce about 20% of the demand for $$^{99}$$Mo in Japan. In the solution irradiation method, the fundamental characteristics of the aqueous molybdate solutions selected as the candidates for the irradiation target were cleared.

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