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.

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.

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

https://jopss.jaea.go.jp/pdfdata/JAEA-Conf-2011-003.pdf#page=195

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.

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

https://jopss.jaea.go.jp/pdfdata/JAEA-Conf-2011-003.pdf

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.

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.

Survey of LEU based 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

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 Tc is obtained from Mo, which is produced by fission of U ((n, f) method) and the neutron capture (n, ) method using the Mo target. However, a supplying of Mo is only depends on imports from any other countries, so JAEA find a way out at domestic production of a part of Mo that (n, ) method in cooperation with the industrial circles. On the other hand, INVAP has been working in the supply of Mo production facilities using LEU. This report provides descriptions the detail technical aspects related to the facility and operations for loading Tc generator. These key issues and technical provided in this report is believed to be useful for developing and updating them.

Survey of LEU based 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 Mo became rises. However the availability and supply of 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 U (HEU) target material used in the majority of the production facilities. As countermeasure for this issue, the HEU is not used but Mo production from low enriched 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 Mo production facilities using LEU. This report provides descriptions for the detail technical aspects related to a Mo production system using irradiated LEU targets.

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

Revaluation of Mo production by (n,) 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 Mo production by (n,) method at HANARO was published by a KAERI report, worldwide supply of Mo became worse and a need for early available alternative Mo became stronger. Previous study indicated that the (n,)Mo has a potential to be an alternative mass Mo available earlier than those by any other methods. It can be realized when radioisotope industry of each country accepts the use of (n,)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,)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,)Mo supply, the specific experience and Mo production capability in HANARO have been discussed and revisited on the base of the previous report.

Mo adsorption and Tc elution characteristics of molybdenum adsorbents for (n,); 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 Mo, which is the parent nuclide of radiopharmaceutical Tc, by (n,) method. The Mo adsorption and Tc elution characteristics of molybdenum adsorbents should be evaluated since the specific activity of Mo obtained by (n,) method is low. Therefore, Mo adsorption and Tc elution tests with molybdenum adsorbents for the (n,) 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 Mo adsorption performance of the adsorbents was the same level as conventional data, whereas the Tc elution performance of the adsorbents was lower than conventional data. The Mo adsorption and Tc elution performance will be investigated again in future.