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Journal Articles

CIELO collaboration summary results; International evaluations of neutron reactions on uranium, plutonium, iron, oxygen and hydrogen

Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Kahler, A. C.*; Talou, P.*; Plompen, A. J.*; Schillebeeckx, P.*; et al.

Nuclear Data Sheets, 148, p.189 - 213, 2018/02

 Times Cited Count:8 Percentile:4(Physics, Nuclear)

The CIELO collaboration has studied neutron cross sections on nuclides that significantly impact criticality in nuclear facilities - $$^{235}$$U, $$^{238}$$U, $$^{239}$$Pu, $$^{56}$$Fe, $$^{16}$$O and $$^{1}$$H - with the aim of improving the accuracy of the data and resolving previous discrepancies in our understanding. This multi-laboratory pilot project, coordinated via the OECD/NEA Working Party on Evaluation Cooperation (WPEC) Subgroup 40 with support also from the IAEA, has motivated experimental and theoretical work and led to suites of new evaluated libraries that accurately reflect measured data and also perform well in integral simulations of criticality. This report summarizes our results and outlines plans for the next phase of this collaboration.

JAEA Reports

Internship using nuclear facilities in Oarai Research and Development Center

Takemoto, Noriyuki; Itagaki, Wataru; Kimura, Nobuaki; Ishitsuka, Etsuo; Nakatsuka, Toru; Hori, Naohiko; Ooka, Makoto; Ito, Haruhiko

JAEA-Review 2013-063, 34 Pages, 2014/03

JAEA-Review-2013-063.pdf:8.46MB

Nuclear energy is important from a viewpoint of economy and energy security in Japan. However, the lack of nuclear engineers and scientists in future is concerned after the sever accident of TEPCO's Fukushima Daiichi Nuclear Power Station has occurred. Institute of National Colleges of Technology planned to carry out training programs for human resource development of nuclear energy field including on-site training in nuclear facilities. Oarai Research and Development Center in Japan Atomic Energy Agency cooperatively carried out an internship for nuclear disaster prevention and safety utilizing the nuclear facilities such as the JMTR. Thirty two students joined in total in the internship from FY 2011 to FY2013. In this paper, contents and results of the internship are reported.

JAEA Reports

Development of safety management system for works in radiation controlled area (Joint research)

Hiyama, Kazuhisa; Hanawa, Nobuhiro; Kurosawa, Akihiko; Eguchi, Shohei; Hori, Naohiko; Kusunoki, Tsuyoshi; Ueda, Hisao; Shimada, Hiroshi; Kanda, Hiroaki*; Saito, Isamu*

JAEA-Technology 2013-045, 32 Pages, 2014/02

JAEA-Technology-2013-045.pdf:5.83MB

This report summarizes regarding to develop of real-time multifunctional access control system which is able to manage worker's access control and exposure dose at real-time in the reactor building, besides worker's location and worker might be fall down by accident.

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

Simulator for materials testing reactors

Takemoto, Noriyuki; Sugaya, Naoto; Otsuka, Kaoru; Hanakawa, Hiroki; Onuma, Yuichi; Hosokawa, Jinsaku; Hori, Naohiko; Kaminaga, Masanori; Tamura, Kazuo*; Hotta, Koji*; et al.

JAEA-Technology 2013-013, 44 Pages, 2013/06

JAEA-Technology-2013-013.pdf:4.42MB

A real-time simulator for operating both a reactor and irradiation facilities of a materials testing reactor, Simulator of Materials Testing Reactors, was developed for understanding reactor behavior and upskilling in order to utilize for a nuclear human resource development and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the JMTR (Japan Materials Testing Reactor) and it simulates operation, irradiation tests and various kinds of anticipated operational transients and accident conditions caused by the reactor and irradiation facilities. The development of the simulator was 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. This report summarizes the simulation model, hardware specification and operation procedure of the simulator.

JAEA Reports

Design, fabrication and transportation of Si rotating device

Kimura, Nobuaki; Imaizumi, Tomomi; Takemoto, Noriyuki; Tanimoto, Masataka; Saito, Takashi; Hori, Naohiko; Tsuchiya, Kunihiko; Romanova, N. K.*; Gizatulin, S.*; Martyushov, A.*; et al.

JAEA-Technology 2012-012, 34 Pages, 2012/06

JAEA-Technology-2012-012.pdf:12.91MB

Si semiconductor production by Neutron Transmutation Doping (NTD) method using the Japan Materials Testing Reactor (JMTR) has been investigated in Neutron Irradiation and Testing Reactor Center, Japan Atomic Energy Agency (JAEA) in order to expand industry use. As a part of investigations, irradiation test of silicon ingot for development of NTD-Si with high quality was planned using WWR-K in Institute of Nuclear Physics (INP), National Nuclear Center of Republic of Kazakhstan (NNC-RK) based on one of specific topics of cooperation (STC), Irradiation Technology for NTD-Si (STC No.II-4), on the implementing arrangement between NNC-RK and the JAEA for "Nuclear Technology on Testing/Research Reactors" in cooperation in research and development in nuclear energy and technology. As for the irradiation test, Si rotating device was fabricated in JAEA, and the fabricated device was transported with irradiation specimens from JAEA to INP-NNC-RK. This report described the design, the fabrication, the performance test of the Si rotating device and transportation procedures.

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

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

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

Feasibility study of sublimation type $$^{99m}$$Tc master-milker; Comparison with PZC based wet method

Ishitsuka, Etsuo; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Norihito*; Hori, Naohiko; Awaludin, R.*; Gunawan, A. H.*; Lubis, H.*; Mutalib, A.*

JAEA-Technology 2011-019, 18 Pages, 2011/06

JAEA-Technology-2011-019.pdf:2.61MB

Feasibility study of sublimation type $$^{99m}$$Tc master-milker was carried out as a $$^{99}$$Mo/$$^{99m}$$T production development with the JMTR. As the feasibility study, the experimental equipment for sublimation method and wet method with PZC based $$^{99m}$$Tc solution were tentatively manufactured, and their properties as the master-milker were investigated by comparing two methods with each other. As a result, it was found that the $$^{99m}$$Tc recovery rate and process time of the sublimation method were about 80% and 1.5 hour, respectively, and the similar values were observed with the wet method. Superior points of the sublimation method are easier operation and reusability of the used MoO$$_{3}$$ comparing with the wet method. On the other hand, disadvantageous point is that the $$^{99m}$$Tc recovery rate decreases with the increase of treating amount of MoO$$_{3}$$.

JAEA Reports

Refurbishment and safety management of JMTR in extended showdown

Ide, Hiroshi; Hori, Naohiko; Gorai, Shigeru; Kusunoki, Tsuyoshi

JAEA-Review 2011-019, 24 Pages, 2011/06

JAEA-Review-2011-019.pdf:3.39MB

Japan Materials Testing Reactor (JMTR) is a testing reactor dedicated to the irradiation tests of materials and fuels. The reactor type of the JMTR is light water moderated and cooled tank type. It achieved first criticality in 1968. Operation was started in 1970. The JMTR had been being operated for 38 years from first criticality to the JMTR No.165 cycle finished. The restart of the JMTR has been strongly requested from various users as the only irradiation testing reactor in Japan. Finally, Japan Atomic Energy Agency (JAEA) decided the refurbishment and restart of the JMTR in December 2006, and the refurbishment works was started from FY 2007. This report summarized JMTR refurbishment and safety management during reactor shutdown.

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:3 Percentile:66.23(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.

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

Development of $$^{rm 99m}$$Tc extraction techniques from $$^{99}$$Mo by (n,$$gamma$$) reaction

Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Yuichi*

JAEA-Review 2010-053, 23 Pages, 2010/11

JAEA-Review-2010-053.pdf:2.52MB

Production techniques of $$^{99}$$Mo, parent nuclide of $$^{rm 99m}$$Tc, have been developed for the industrial utilization as medical diagnosis medicine after the JMTR refurbishment. The (n,$$gamma$$) method is proposed in JMTR because of low-amount radioactive wastes and easy $$^{rm 99m}$$Tc production process. In this study, the production of the high-density MoO$$_{3}$$ pellet and concentration techniques of $$^{rm 99m}$$Tc solution were developed. As the trial test, the MoO$$_{3}$$ pellets with high density were produced by the SPS (Spark Plasma Sintering) method. On the other hands, it was possible to concentrate $$^{rm 99m}$$Tc solution by the solvent extraction using Methyl Ethyl Ketone (MEK). From the result, the $$^{rm 99m}$$Tc concentrating device with more than 80% concentration efficiency, was performed successfully.

JAEA Reports

Review on technical evaluation of aging of JMTR reactor facility

Ide, Hiroshi; Tobita, Kenji; Endo, Yasuichi; Hori, Naohiko

JAEA-Review 2010-043, 80 Pages, 2010/10

JAEA-Review-2010-043.pdf:34.97MB

"Regulations Concerning the Installment, Operation, etc. of Research Reactors" was revised in February 2004. Based on the regulations, the reactor owner must perform the technical evaluation on aging if reactor operation is over 30 years. Moreover, based on the evaluation, the reactor owner must make the 10 years maintenance program concerning the action to maintain the reactor facility. Result of the technical evaluation on aging and the maintenance plan of JMTR reactor facility were reported to the MEXT in March 2005. In response to the report, the advisor meeting was held by the MEXT to evaluate the result of technical evaluation on aging and the maintenance plan. Corresponding to the meeting, we reviewed the technical evaluation result on aging and the maintenance program of JMTR reactor facility. This report summarized the review on the technical evaluation of aging of JMTR reactor facility and so on corresponding to the advisor meeting.

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.

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