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Ooka, Makoto; Maekawa, Yasunari; Tomizuka, Chiaki; Murakami, Tomoyuki*; Katagiri, Genichi*; Ozaki, Hiroshi*; Kawamura, Hiroshi
JAEA-Technology 2015-003, 31 Pages, 2015/03
JAEA-Technology-2015-003.pdf:3.95MB
An action for the decommissioning of the Fukushima Daiichi Nuclear Power Station (Tokyo Electric Power Company) is pushed forward now. For fuel debris Remove, it is necessary to fill the Primary Containment Vessel (PCV) with water. Because a coolant leaks out from the PCV, it becomes the most important problem to seal leak the coolant. Nuclear Plant Decommissioning Safety Research Establishment has examined the method of seal leak using the photocoagulation resin. However, originally the photocoagulation resin is used as coating or the painting, and the applicability to seal leak water is unknown. This report describes the result that examined the applicability to seal leak using photocoagulation resin.
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.
Kimura, Nobuaki; Takemoto, Noriyuki; Ooka, Makoto; Ishitsuka, Etsuo; Nakatsuka, Toru; Ito, Haruhiko; Ishihara, Masahiro
JAEA-Review 2012-055, 40 Pages, 2013/03
JAEA-Review-2012-055.pdf:93.64MB
Training courses using JMTR and related facilities as advanced research infrastructures have been newly organized for domestic students, young researchers and engineers since FY2010 from a viewpoint of nuclear human resource development in order to support global expansion of nuclear power industry. In FY 2012, two courses were carried for foreign as well as Japanese young researchers and engineers in order to carry out effective practical training. For the foreigner course, 16 young researchers and engineers were joined from July 23rd to August 10th. For the Japanese course, total 35 young researchers and engineers were joined two courses from August 20th to August 31st and from September 3rd to September 14th. Lectures of these training courses were consisted from basics of nuclear energy to its application, especially for irradiation tests in Motrin this paper, results of these foreigners and Japanese training courses are reported.
Takemoto, Noriyuki; Kimura, Nobuaki; Ooka, Makoto
UTNL-R-0483, p.10_1_1 - 10_1_10, 2013/03
no abstracts in English
Ishihara, Masahiro; Kimura, Nobuaki; Takemoto, Noriyuki; Ooka, Makoto; Kaminaga, Masanori; Kusunoki, Tsuyoshi; Komori, Yoshihiro; Suzuki, Masahide
Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 7 Pages, 2012/10
The JMTR has been utilized for fuel/material irradiation examinations of LWRs, HTGR, fusion reactor as well as for RI productions. The refurbishment of the JMTR was started from the beginning of JFY 2007, and finished in March 2011 as planned schedule. Unfortunately, at the end of the JFY 2010 on March 11, the Great-Eastern-Japan-Earthquake occurred, and functional tests before the JMTR restart were delayed by the earthquake. Moreover, a detail inspection found some damages such as small cracks in the concrete structure, ground sinking around the reactor building. Consequently, the restart will delay from June 2011. Now, the safety evaluation of the facility after the earthquake disaster is being carried out aiming at the restart of the JMTR. The renewed JMTR will be started from JFY 2012 and operated for a period of about 20 years until around JFY 2030. The usability improvement of the JMTR is also discussed with users as the preparations for re-operation.
Kollryd, T.*; Romas, A.*; Porter-Peden, M.*; Takemoto, Noriyuki; Kimura, Nobuaki; Ooka, Makoto; Kaminaga, Masanori; Ishitsuka, Tatsuo*; Tamura, Kazuo*
Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 9 Pages, 2012/10
A simulator for materials testing reactors has been developed to be utilized for human resource development with an advancement of technology in mind. The simulator is designed based on the JMTR, and the reactor core is modeled with REMARK
, in which a 3-dimensional, 4-energy group, time dependent, diffusion theory model is applied. The thermo-hydraulic properties in the reactor vessel are modeled using RELAP5-HD, which is the real-time version of RELAP5-3D code. REMARK interacts with the RELAP5-HD thermal hydraulic model by providing power to the moderator. The RELAP5-HD model, in return, provides thermal hydraulic feedback to the REMARK model. For the primary and secondary cooling loops, main heat exchangers, purification system and cooling towers, the 2-phase, 6-equation matrix solution modeling tool JTopmeret is used. The high fidelity level of modern simulators is not only a valuable tool for human resource training, but also an analysis tool for safety in normal/transient/accident conditions of materials testing reactors.
Ono, Kiyoshi; Ohtaki, Akira; Chikazawa, Yoshitaka; Nakagiri, Toshio; ; Sekine, Takashi;
JNC TN9410 2004-013, 76 Pages, 2004/06
JNC-TN9410-2004-013.pdf:7.23MB
This report describes the features of technology, the schedule and the organization for the research and development regarding the hydrogen production technology using FBR thermal energy. Now, the hydrogen production system is proposed as one of new business models for FBR deployment. This system is the production of hydrogen either thermal energy at approximately 500deg-C or electricity produced by a sodium cooled FBR. Hydrogen is expected to be one of the future dean secondary energies without carbon-dioxide emission. Meanwhile the global energy demand will increase, especially in Asian countries, and the energy supply by fossil fuels is not the best choice considering the green house effect and the stability of energy supply. The development of the hydrogen technology using FBR that satisfies "sustainable energy development" and "utilization of energies free from environmental pollution" will be one of the promising options. Based on the above mentioned recognition, we propose the direction of the development, the issues to be solved, the time schedule, the budget, and the organization for R&D of three hydrogen production technologies, the thermochemical hybrid process, the low temperature steam reforming process, and the high temperature steam electrolysis process in JNC.
Kono, Naomi; Aoyama, Takafumi; Sekine, Takashi; Ooka, Makoto; Maeda, Shigetaka; Takamatsu, Misao
JNC TN9200 2003-003, 103 Pages, 2004/03
JNC-TN9200-2003-003.pdf:19.5MB
None
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JNC TN9400 99-048, 493 Pages, 1999/05
When a vibrating cantilever beam collides with another structure, its dynamic characteristics may be affected and changed by the collision. In order to study the effect of collision on the vibration of the beam, mainly from a view point of failure prevention, vibration experiments and dynamic analyses were made. From the vibration experiment, it was found that; (1)Due to the collision, the vibration characteristics show typical non-linear behavior such as excitaion level dependency and jump phenomena. (2)Larger resonant response were seen with a simple cantilever beam without collision and pinned supported beam than with the cases with collision. (3)Vibration mode is affected by the collision and hence the axial distribution of bending strain is also affected. However, the maximum strain along the beam axis of the simple cantilever case is larger than other cases. Non-linear dynamic response analysis with beam and gap elements is capable of reproducing the experiment results with sufficient accuracy.
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JNC TN9400 99-060, 364 Pages, 1999/04
A structure concept of vertical seismic isolation system which uses a common deck and a set of large dish springs was created in past studies. In this report, a series of dynamic tests on a small scale model of a common deck isolation structure were performed. The model was excited by random and seismic waves in the horizontal direction and 2-D excitation, horizontal and vertical, in order to identify the characteristics of isolation effect. The tests results are summarized as below. (1)This structure has three vibration mode. The second mode is rocking. (2)Rocking frequency depends on the excitation, for this structure has dish spring which contact with cylinders. Rocking damping varies from 2 to 8%. (3)Each mode's response peak frequency to 2-D (horizontal and vertical) excitation is almost the same the some to horizontal excitation. Vertical mode damping to 2-D excitation is about three times to horizontal excitation. (4)Isolation effect depends on a characteristics of frequency of input motion. The minimum response is to the Monju design seismic wave, soil shear wave: Vs=2000m/sec, natural frequency of horizontal isolation in vertical direction: fv=20Hz. A relative displacement is controlled. (5)A rocking angular displacement to 2-D excitation is about 2 times to 1-D excitation (vertical). However, it is about l.2E-4(rad), sufficiently small for a practical plant.
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PNC TN9410 98-093, 551 Pages, 1998/08
Seismic safety of three-piled container system used in Tokai reprocessing center eas confirmed by seismic test and computational analysis. Two types of container were evaluated, for low level noninflamable radioactive solid wastes, and for used filters wrapped by large plastic bags. Seismic integrity of three-piled containers was confirmed by evaluating response characteristics such as acceleration and displacement under the design earthquake condition S1, which is the maximum earthquake expected at the stored site during the storage time. Computational dynamic analysis was also performed, and several conclusions described below were made. (1)Response characteristics of the bottom board and the side board were different. The number of pile did not affect the response characteristics of the bottom board of each container, They behaved as a rigid body. (2)The response of the side board was larger than that of the bottom board. (3)The response depended on the direction in each board, either side or bottom. The response acceleration became larger to the seismic wave perpendicular to the plane which has the entrance for fork lift and the radioactive warning mark. (4)The maximum horizontal response displacement under the S1 seismic wave was approximately 10mm. It is so small that it does not affect the seismic safety. (5)The stoppers to prevent fall down had no influence to the response acceleration. (6)There was no fall down to the S1 seismic wave and 2 times of S1 seismic wave, which was the maximum input condition of the test. (7)The response of the bottom board of the containers, which are main elements of fall down, had good agreements both in the test and in the computational analysis.
Takemoto, Noriyuki; Kimura, Nobuaki; Ooka, Makoto; Ishitsuka, Etsuo; Kaminaga, Masanori; Ishihara, Masahiro; Suzuki, Masahide
no journal, ,
In order to support global expansion of nuclear power industry, the nuclear Human Resource Development (HRD) is addressed one of urgent issues because of the lack of nuclear engineers. In this situation, the training course for foreign young researchers and engineers was held at JMTR in JFY 2012, and 16 trainees from Indonesia, Kazakhstan, Malaysia, Thailand and Poland had studied for 3 weeks. The training course contains basic lecture and practice on the neutronic and thermal calculations for irradiation tests in the JMTR, training of reactor operation by a simulator for materials testing reactors, lecture for Fukushima Dai-ichi NPP accident, etc. The nuclear HRD initiative program sponsored by the MEXT, the training course using the JMTR and the related facilities, has also been carried out in every year since JFY 2010 for domestic students and engineers. The 4th training course with 20 trainees and the 5th training course with 15 trainees were held in JFY 2012.
Takemoto, Noriyuki; Kimura, Nobuaki; Ooka, Makoto; Kaminaga, Masanori; Hotta, Koji*; Tamura, Kazuo*
no journal, ,
A simulator for materials testing reactors was developed in order to utilize for a nuclear human resource development and to promote the partnership with developing countries which have a plan to introduce nuclear power plant and/or experimental research reactor. The simulator is designed based on JMTR, and simulates normal, transient and accident conditions, and also irradiation tests such as material testing under BWR condition. The simulator is composed of a computer system, control panels with large-size displays for reactor control, process control, irradiation facility control and an instruction. In the simulation, the reactor is operated with cooling system for 30 days a cycle at 50 MWth same as the JMTR. Outputs, such as neutron flux, temperature and flow rate in the core are shown in real time in collaboration with Excel.
Kaminaga, Masanori; Tanimoto, Masataka; Ooka, Makoto; Ishihara, Masahiro; Kusunoki, Tsuyoshi; Komori, Yoshihiro; Suzuki, Masahide
no journal, ,
The Japan Materials Testing Reactor (JMTR) in Japan Atomic Energy Agency (JAEA) is a light water cooled tank type reactor with 50 MW thermal power. From its first criticality in March 1968, the JMTR has been utilized for fuel/material irradiation examinations of LWRs, HTGR, fusion reactor as well as for RI productions. In August 2006, the JMTR operation was once stopped in order to have a check & review for the reoperation which was discussed by internal as well as external committees. As a result of the national discussion, the JMTR was determined, finally, to restart after necessary refurbishment works. The refurbishment was started from the beginning of JFY 2007, and replaced were motors of primary and secondary cooling pumps, nuclear instrumentation system, process control system, safety protection system and so on. The refurbishment was finished in March 2011 taking four years as planned schedule. Unfortunately, at the end of the JFY 2010 on March 11, the Great-Eastern-Japan-Earthquake occurred, and functional tests before the JMTR restart, such as cooling system, reactor control system and so on, were delayed by the earthquake. Moreover, a detail inspection found some damages such as small cracks in the concrete structure. Consequently, the restart of the JMTR will delay from June 2011 to this year. Now, the safety evaluation after the earthquake disaster is being carried out aiming at the restart of the JMTR. The renewed JMTR will be started from JFY 2012 and operated for a period of about 20 years until around JFY 2030. Expected utilization fields after reoperation will be a safety research of LWRs for materials/fuels, basic research for nuclear engineering such as HTGR fuels/materials, fusion reactor materials, industrial use such as production of Mo-99 for medical use, and education & training of nuclear scientists and engineers.
Kaminaga, Masanori; Ooka, Makoto; Ishihara, Masahiro; Kusunoki, Tsuyoshi; Araki, Masanori
no journal, ,
JMTR is a light water cooled tank type reactor with 50 MW. From its first criticality in March 1968, the JMTR has been utilized for fuel/material irradiation examinations of LWRs, HTGR and fusion reactor as well as for RI productions. In August 2006, the JMTR operation was once stopped in order to have a check & review for the reoperation. As a result of the national discussion, the JMTR was determined, finally, to restart after necessary refurbishment works. The refurbishment works were started from the beginning of JFY 2007, and replaced were motors of primary and secondary cooling pumps, nuclear instrumentation system and so on. The refurbishment works were finished in March 2011. Unfortunately, at the end of JFY 2010 on March 11, the Great-Eastern-Japan-Earthquake occurred, and functional tests before the JMTR restart, such as cooling system, reactor control system and so on, were delayed by the earthquake. Moreover, a detail inspection found some damages such as small cracks in the concrete structure. Consequently, the restart of the JMTR was delayed from June 2011 to this year. A seismic influence evaluation after the earthquake disaster was carried out. The seismic influence evaluation results has been reported to the regulatory agency. Validity of the seismic influence evaluation results will be evaluated by the Nuclear Regulation Authority (NRA). JMTR will be re-started after the validation evaluation by the NRA. JMTR will be operated for 20 years. Expected utilization fields will be a safety research of LWRs for materials/fuels, basic research for nuclear engineering such as HTGR fuels/materials, fusion reactor materials, industrial use such as production of Mo-99 for medical use, and education & training of nuclear scientists and engineers.
Kaminaga, Masanori; Tanimoto, Masataka; Ooka, Makoto; Ishihara, Masahiro; Kusunoki, Tsuyoshi; Naito, Akinori; Araki, Masanori
no journal, ,
JMTR in JAEA is a light water cooled tank type reactor with 50MW thermal power. From its first criticality in March 1968, the JMTR has been utilized for fuel/material irradiation examinations of LWRs, HTGR and fusion reactor as well as for RI productions under its transportation advantage that the JMTR and hot laboratory is connected by a canal. In August 2006, the JMTR operation was once stopped in order to have a check & review for the reoperation which was discussed by internal as well as external committees. As a result of the national discussion, the JMTR was determined, finally, to restart after necessary refurbishment works. The refurbishment was started from the beginning of JFY 2007, and replaced were motors of primary and secondary cooling pumps, nuclear instrumentation system, and so on. The refurbishment was finished in March 2011 as planned. Unfortunately, at the end of the JFY 2010 on March 11, the Great-Eastern-Japan-Earthquake occurred, and functional tests before the JMTR restart were delayed by the earthquake. Seismic influence evaluation for the JMTR because of the 3.11 earthquake was carried out with directions of the government. As a result, integrity of the JMTR reactor facilities has been evaluated and verified for re-operation. Seismic influence evaluation results were reported to the regulatory agency on Sep.7, 2012. Validation evaluation of the seismic influence evaluation results is still underway by the NRA. On the other hand, new regulatory requirements for research and test reactors will be established on Dec.18, 2013 by the NRA. JMTR will be re-started after the completion of validation evaluation of the seismic influence evaluation results and confirmation of suitability against the new regulatory requirements for research and test reactors by the NRA. The renewed JMTR will be operated for a period of about 20 years until around JFY 2030.
Usami, Hiroshi; Kawamura, Hiroshi; Ooka, Makoto; Miura, Kuniaki*; Onizawa, Tatsuya*
no journal, ,
no abstracts in English
Shimada, Kozue; Ooka, Makoto; Maekawa, Yasunari; Tomizuka, Chiaki; Murakami, Tomoyuki*; Katagiri, Genichi*; Ozaki, Hiroshi*; Aoyagi, Katsuhiro*; Kawamura, Hiroshi
no journal, ,
no abstracts in English
Shimada, Kozue; Ooka, Makoto; Maekawa, Yasunari*; Tomizuka, Chiaki; Katagiri, Genichi*; Aoyagi, Katsuhiro*; Shibata, Takuya; Koyama, Shinichi
no journal, ,
Shimada, Kozue; Tomizuka, Chiaki; Shibata, Takuya; Ooka, Makoto; Maekawa, Yasunari*; Aoyagi, Katsuhiro*; Shinoki, Masatoshi*; Katagiri, Genichi*; Ozaki, Hiroshi*; Koyama, Shinichi
no journal, ,
no abstracts in English
