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JAEA Reports

Performance tests of radiation detectors for inspection of $$^{99}$$Mo/$$^{99m}$$Tc solution, 1

Suzuki, Yumi*; Nakano, Hiroko; Suzuki, Yoshitaka; Ishida, Takuya; Shibata, Akira; Kato, Yoshiaki; Kawamata, Kazuo; Tsuchiya, Kunihiko

JAEA-Technology 2015-031, 58 Pages, 2015/11

JAEA-Technology-2015-031.pdf:14.57MB

Technetium-99m ($$^{99m}$$Tc) is one of the most commonly used radioisotopes in the field of nuclear medicine. In the Japan Atomic Energy Agency (JAEA), the research and development (R&D) have been carried out for production of molybdenum-99 ($$^{99}$$Mo) by (n, $$gamma$$) method, a parent nuclide of $$^{99m}$$Tc, with the Japan Material Testing Reactor (JMTR). On the other hand, the new project as "Domestic Production of Medical Radioisotope (Technetium preparation) in Japan" was adopted in the Tsukuba International Strategic Zone on October, 2013 and the demonstration tests will be planned for the domestic production of $$^{99}$$Mo/$$^{99m}$$Tc with the JMTR. Thus, new facilities and analysis devices were equipped in the JMTR Hot Laboratory in 2014 as the part of this project. As the part of the analytical device equipment, the $$gamma$$-TLC analyzer and the radiation detector connected with the High Performance Liquid Chromatography (HPLC) were installed for quality inspection of the $$^{99}$$Mo/$$^{99m}$$Tc solution and the extracted $$^{99m}$$Tc solution in the JMTR Hot Laboratory. The performance tests of these devices such as detection sensitivity, resolution, linearity and selectivity of energy range were carried out with $$^{137}$$Cs and $$^{152}$$Eu as alternative radionuclides of $$^{99}$$Mo and $$^{99m}$$Tc, respectively. In the results, bright prospects were obtained concerning the quality inspection of the $$^{99}$$Mo/$$^{99m}$$Tc and $$^{99m}$$Tc solutions using these devices. This report describes the results of those performance tests.

Journal Articles

Current post irradiation examination techniques at the JMTR Hot laboratory

Shibata, Akira; Kato, Yoshiaki; Oishi, Makoto; Taguchi, Taketoshi; Ito, Masayasu; Yonekawa, Minoru; Kawamata, Kazuo

KAERI/GP-418/2015, p.151 - 165, 2015/05

The JMTR stopped its operation in 2006 for refurbishment. The reactor facilities have been refurbished from 2007. After refurbishment, JMTR Hot laboratory is expected to perform various post irradiation examinations. In this report, installations of experimental apparatuses and recent experimental method are introduced. (1) A nano-indenter with radius spherical indenter. Inverse analysis using FEM could presume material constants from load-depth curve of indentation. Mechanical properties of oxide layer of zirconium alloy and irradiated stainless steel will be analyzed. (2) Transmission Electron Microscope (TEM). TEM is capable of imaging at a significantly higher resolution than light microscopes or normal SEM. JAEA installed a TEM apparatus (JEOL JEM-2800) in JMTR Hot laboratory. The maximum magnification is 150,000,000 times. It can be operated from a remote location using a computer network. This contributes to the convenience of remote researchers and reducing the amount of exposure.

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.

Journal Articles

Development of post-irradiation test facility for domestic production of $$^{99}$$Mo

Taguchi, Taketoshi; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Nishikata, Kaori; Ishida, Takuya; Kawamata, Kazuo

UTNL-R-0483, p.10_5_1 - 10_5_13, 2013/03

JMTR focus on the activation method. By carrying out the preliminary tests using irradiation facilities existing, and verification tests using the irradiation facility that has developed in the cutting-edge research and development strategic strengthening business, as irradiation tests towards the production of $$^{99}$$Mo, we have been conducting research and development that can contribute to supply about 25% for $$^{99}$$Mo demand in Japan and the stable supply of radiopharmaceutical. This report describes a summary of the status of the preliminary tests for the production of $$^{99}$$Mo: Maintenance of test equipment in the facility in JMTR Hot Laboratory in preparation for research and development for the production of $$^{99}$$Mo in JMTR and using MoO$$_{3}$$ pellet irradiated at Kyoto University Research Reactor Institute (KUR).

Journal Articles

Development of remote welding techniques for in-pile IASCC capsules and evaluation of material integrity on capsules for long irradiation period

Shibata, Akira; Nakano, Junichi; Omi, Masao; Kawamata, Kazuo; Nakagawa, Tetsuya; Tsukada, Takashi

Journal of Nuclear Materials, 422(1-3), p.14 - 19, 2012/03

 Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)

To simulate Irradiation assisted stress corrosion cracking (IASCC) behavior by in-pile experiments, it is necessary to irradiate specimens up to a neutron fluence that is higher than the IASCC threshold fluence. Pre-irradiated specimens must be relocated from pre-irradiation capsules to in-pile capsules. Hence, a remote welding machine has been developed. And the integrity of capsule housing for a long term irradiation was evaluated by tensile tests in air and slow strain rate tests in water. Two type specimens were prepared. Specimens were obtained from the outer tubes of capsule irradiated to 1.0-3.9 $$times$$ 10$$^{26}$$ n/m$$^{2}$$ (E$$>$$ 1 MeV). And specimens were irradiated in a leaky capsule to 0.03-1.0 $$times$$ 10$$^{26}$$ n/m$$^{2}$$. Elongation more than 15% in tensile test at 423 K was confirmed and no IGSCC fraction was shown in SSRT at 423 K which was estimated as temperature at the outer tubes of the capsule under irradiation.

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.

JAEA Reports

Neutron shielding reinforcement in the JMTR Hot Laboratory

Ito, Masayasu; Kawamata, Kazuo; Tayama, Yoshinobu; Kanazawa, Yoshiharu; Yonekawa, Minoru; Nakagawa, Tetsuya; Omi, Masao; Iwamatsu, Shigemi

JAEA-Technology 2011-022, 44 Pages, 2011/07

JAEA-Technology-2011-022.pdf:3.29MB

Hot laboratory are facilities that execute the post irradiation examination of sample irradiated in material testing reactors etc. The handling of high burn-up fuel is scheduled in the JMTR (Japan Materials Testing Reactor) Hot Laboratory with JMTR re-operate in FY 2011. This report describes evaluation, production and installation of shielding of the hot cells in the JMTR Hot Laboratory.

JAEA Reports

Investigation for methods of micro-structural observation of beryllium metals by TEM

Ito, Masayasu; Kawamata, Kazuo; Sozawa, Shizuo; Shibata, Akira; Tsuchiya, Kunihiko; Kitsunai, Yuji*; Kodama, Mitsuhiro*

JAEA-Testing 2011-003, 22 Pages, 2011/06

JAEA-Testing-2011-003.pdf:9.16MB

In JMTR, beryllium metal is used for neutron reflector. However, the periodical exchange of the neutron reflector is necessary due to degradation of strength and swelling under neutron irradiation. So it is required to select the material that bears long term from the viewpoint of the utilization rate improvement and the radioactive waste decrease in JMTR. It is important to evaluate the characteristics of beryllium metals precisely. This report describes the preparation method of the sample and observation results by the transmission electron microscope that is being examined as a evaluation method of the beryllium metal.

Journal Articles

Human resource development program using JMTR

Ishitsuka, Etsuo; Kitagishi, Shigeru; Aoyama, Masashi; Kawamata, Kazuo; Nagao, Yoshiharu; Ishihara, Masahiro; Kawamura, Hiroshi

Proceedings of 1st Asian Symposium on Material Testing Reactors (ASMTR 2011), p.111 - 115, 2011/02

Journal Articles

Status of PIE technology development in JAEA-Oarai

Tanaka, Kosuke; Kawamata, Kazuo; Yoshimochi, Hiroshi; Sozawa, Shizuo; Onose, Shoji; Niimi, Motoji; Asaka, Takeo

Proceedings of 1st Asian Symposium on Material Testing Reactors (ASMTR 2011), p.71 - 76, 2011/02

Post irradiation examination (PIE) facilities have been operated for about 40 years at the Oarai Research and Development Center of the Japan Atomic Energy Agency to investigate the performance and soundness of irradiated fuels and materials. The JMTR Hot Laboratory (JMTR-HL) was founded in 1971 mainly to examine the objects irradiated in the Japan Material Testing Reactor (JMTR). The Alpha-Gamma Facility (AGF) was constructed as the first laboratory to perform PIE of plutonium-bearing fuels for Japanese fast reactor development programs. This facility started hot operation in 1971 and has performed physical, metallurgical, and chemical examinations of irradiated fuels including uranium plutonium mixed oxide fuels. A renewal plan for the JMTR-HL and AGF is now in progress, associated with re-operation of the JMTR.

JAEA Reports

Evaluation of characteristics of the surface displacement measurement device by laser method

Ito, Masayasu; Kawamata, Kazuo; Ishitsuka, Etsuo

JAEA-Testing 2009-007, 16 Pages, 2010/03

JAEA-Testing-2009-007.pdf:10.26MB

Surface state of material is measured by the surface displacement measurement device with laser displacement sensor. It is important to know the characteristic of a device that considers environment to use this device in the cell. Therefore, this report described about evaluation of characteristics of the device by laser method.

JAEA Reports

Renewal plan of the JMTR Hot Laboratory for the irradiation test of high burn-up fuels in FY2008

Sozawa, Shizuo; Nakagawa, Tetsuya; Iwamatsu, Shigemi; Hayashi, Koji; Tayama, Yoshinobu; Kawamata, Kazuo; Yonekawa, Minoru; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Omi, Masao

JAEA-Technology 2009-070, 27 Pages, 2010/03

JAEA-Technology-2009-070.pdf:7.46MB

Refurbishment of the Japan Materials Testing Reactor (JMTR), which is recognized as one of important facilities in Japan for safety research, is in progress by the JAEA. In Extensive safety research of light-water reactor (LWR) fuels and materials under a contract with the Nuclear and Industrial Safety Agency of Ministry of Economy, Trade and Industry of Japan, the irradiation tests are planned in order to examine integrity of the LWR fuels and structure materials. For the irradiation tests of high burnup fuels and irradiated materials in the JMTR, modification of the hot laboratory facilities are needed, which are (1) making of application books for strengthening JMTR hot-lab. cell-shielding, (2) the capsule assembling device of detailed design, (3) safety analysis for domestic transportation cask and (4) confirmatory testing of diamond drill of fuel-rod center-hole processing device.

JAEA Reports

Renewal plan of the JMTR Hot Laboratory for the Irradiation test of high burn-up fuels in FY2007

Sozawa, Shizuo; Nakagawa, Tetsuya; Omi, Masao; Hayashi, Koji; Iwamatsu, Shigemi; Kawamata, Kazuo; Kato, Yoshiaki; Kanazawa, Yoshiharu

JAEA-Technology 2009-069, 32 Pages, 2010/03

JAEA-Technology-2009-069.pdf:7.33MB

Refurbishment of the Japan Materials Testing Reactor (JMTR), which is recognized as one of important facilities in Japan for safety research, is in progress by the JAEA. In Extensive safety research of light-water reactor (LWR) fuels and materials under a contract with the Nuclear and Industrial Safety Agency of Ministry of Economy, Trade and Industry of Japan, the irradiation tests are planned in order to examine integrity of the LWR fuels and structure materials. For the irradiation tests of high burnup fuels and irradiated materials in the JMTR, modification of the hot laboratory facilities are needed, which are (1) strengthening JMTR hot-lab. cell-shielding, (2) the capsule assembling device, (3) domestic transportation cask, (4) fuel-rod center-hole processing device, (5) master-slave manipulators, (6) power manipulator, and (7) scanning electron microscope.

JAEA Reports

Development on crack growth and crack initiation test units for stress corrosion cracking examinations in high-temperature water environments under neutron irradiation, 1 (Contract research)

Izumo, Hironobu; Chimi, Yasuhiro; Ishida, Takuya; Kawamata, Kazuo; Inoue, Shuichi; Ide, Hiroshi; Saito, Takashi; Ise, Hideo; Miwa, Yukio; Ugachi, Hirokazu; et al.

JAEA-Technology 2009-011, 31 Pages, 2009/04

JAEA-Technology-2009-011.pdf:4.38MB

Regarding Irradiation Assisted Stress Corrosion Cracking (IASCC) for austenitic stainless steel of the light water reactor (LWR), a lot of data that concerns the post irradiation evaluation (PIE) is acquired. However, IASCC occurs in LWR condition. Therefore, it is necessary to confirm adequacy of the PIE data comparing the experiment data under the simulated LWR condition. Bigger specimen is needed to acquire the effective data for the destruction dynamics in the study of stress corrosion cracking under neutron irradiation condition. Therefore, development of a new crack growth unit which can load to bigger is necessary to the neutron irradiation test. As a result, a prospect was provided in the unit that could load to specimen by changing load mechanism to the lever type from the linear type. And also, in the development of crack propagation unit, some technical issues were extracted from the discussion of the unit structure adopting the LVDT (Linear Variable Differential Transformer).

Journal Articles

Current status and future plan of JMTR Hot Laboratory

Kawamata, Kazuo; Nakagawa, Tetsuya; Omi, Masao; Hayashi, Koji; Shibata, Akira; Saito, Junichi; Niimi, Motoji

JAEA-Conf 2008-011, p.78 - 86, 2009/01

The JMTR-HL was founded to examine the objects mainly irradiated in the JMTR in 1971. The JMTR-HL has an advantage that the hot cell is connected with the reactor vessel of the JMTR by a canal. Hence it is easy to transport irradiated radioactive capsules and specimens through the canal. Since 1971, about 2,400 irradiated capsules have been treated in the JMTR-HL and various PIEs have been widely performed there. In recent years, several new techniques, e.g., an in-cell IASCC test, a scanning-electron microscope (SEM) / electron-back scattering-diffraction pattern (EBSD) observation, were added to the conventional PIEs. In addition, the JMTR-HL had contributed to realize an in-pile IASCC test program at the JMTR through the development of a TIG welding technique by remote-handling with manipulators in the hot cell for re-assembling of capsules. A modification of the facility to treat high burn-up fuels, up to about 100 GWD/t, is planned at the JMTR-HL now.

Journal Articles

Joining techniques development for neutron irradiation tests and post irradiation examinations in JMTR-HL

Taguchi, Taketoshi; Inaba, Yoshitomo; Kawamata, Kazuo; Nakagawa, Tetsuya; Tsuchiya, Kunihiko

JAEA-Conf 2008-010, p.193 - 202, 2008/12

The JMTR-HL is directly connected with reactor core by a water canal. Hence irradiated radioactive capsules are efficiently transported under water through the canal in a short time. As the part of PIE technology development, several kinds of welding techniques have been systematically developed. These techniques are as follows; (1) re-instrumentation of FP gas pressure gauge and thermocouple to an irradiated fuel rod, (2) welding procedure development for re-capsuling of irradiated materials, (3) joining technique and PIEs development of different materials with friction welding for new typed irradiation capsules and (4) rewelding with irradiated and un-irradiated materials and fabrication of test specimen with the rewelding for fusion reactor development. These welding techniques have been very indispensable for supporting the irradiation tests and post-irradiation examinations and were introduced in this seminar.

Journal Articles

In-core SCC growth behavior of type 304 stainless steel in BWR simulated high-temperature water at JMTR

Kaji, Yoshiyuki; Ugachi, Hirokazu; Tsukada, Takashi; Nakano, Junichi; Matsui, Yoshinori; Kawamata, Kazuo; Shibata, Akira; Omi, Masao; Nagata, Nobuaki*; Dozaki, Koji*; et al.

Journal of Nuclear Science and Technology, 45(8), p.725 - 734, 2008/08

 Times Cited Count:7 Percentile:44.69(Nuclear Science & Technology)

Irradiation assisted stress corrosion cracking (IASCC) is one of the critical concerns when stainless steel components have been in service in light water reactors for a long period. In-core IASCC growth tests have been carried out using the compact tension type specimens of type 304 stainless steel that had been pre-irradiated up to a neutron fluence level around 1$$times$$10$$^{25}$$n/m$$^{2}$$ in pure water simulated boiling water reactor (BWR) coolant condition at the Japan Materials Testing Reactor (JMTR). In order to investigate the effect of synergy of neutron/$$gamma$$ radiation and stress/water environment on IASCC growth rate, we performed ex-core IASCC tests on irradiated specimens at several dissolved oxygen contents environments under the same electrochemical potential condition. In this paper, results of the in-core SCC growth tests will be discussed and compared with the result obtained by ex-core tests from a viewpoint of the synergistic effects on IASCC.

Journal Articles

Technical development for IASCC irradiation experiments at the JMTR

Shibata, Akira; Nakano, Junichi; Omi, Masao; Kawamata, Kazuo; Saito, Takashi; Hayashi, Koji; Saito, Junichi; Nakagawa, Tetsuya; Tsukada, Takashi

Proceedings of 16th International Conference on Nuclear Engineering (ICONE-16) (CD-ROM), 8 Pages, 2008/05

Irradiation assisted stress corrosion cracking (IASCC) is considered to be one of the key issues in the aged Light Water Reactors. To simulate IASCC behavior by the in-pile or post-irradiation experiment, it is necessary to irradiate specimens up to a neutron fluence that is higher than the so-called IASCC threshold fluence. There are, however, some technical hurdles to be overcome for the experiments. The techniques assembling pre-irradiated specimens into a in-pile test capsule in a hot cell and the eveluation of material integrity of the capsule during a long term irradiation are necessary. To evaluate material integrity on capsules during a long term irradiation, tensile test and SSRT using specimens which was previously irradiated to 1.0$$sim$$3.9$$times$$10$$^{26}$$ n/m$$^{2}$$ were performed. In this paper, technical developments required for IASCC test, e.g. the development of assembling techniques for IASCC capsules and the evaluation of stainless steels which dosed high-fluence neutron were described.

JAEA Reports

Development of welding techniques for assembling of IASCC Test Capsule

Shibata, Akira; Kawamata, Kazuo; Taguchi, Taketoshi; Kaji, Yoshiyuki; Shimizu, Michio*; Kanazawa, Yoshiharu; Matsui, Yoshinori; Iwamatsu, Shigemi; Sozawa, Shizuo; Tayama, Yoshinobu; et al.

JAEA-Technology 2008-029, 40 Pages, 2008/03

JAEA-Technology-2008-029.pdf:25.78MB

Irradiation assisted stress corrosion cracking (IASCC) is considered to be one of the key issues from a viewpoint of the life management of core components in the aged Light Water Reactors. The in-situ crack extension examination and the in-situ constant load tensile test in the reactor are required for the study of IASCC. There are, however, some technical hurdles to be overcome for the experiments. For this in-situ IASCC test, techniques for assembling pre-irradiated specimens into an capsule in a hot cell by remote handling are necessary. In this report, I describe the establishment of those remote assembling techniques and development of new welding apparatus and the TIG upset welding for stainless tube of 3 mm in thickness. Already IASCC capsules having pre-irradiated CT specimens were remotely assembled using these techniques in the hot cell for performing crack growth tests under irradiation in JMTR. And eight in-situ IASCC capsules have been finished successfully in JMTR.

JAEA Reports

Fabrication of irradiation capsule for IASCC irradiation tests, 2; Irradiation capsule for crack propagation test (Joint research)

Ide, Hiroshi; Matsui, Yoshinori; Kawamata, Kazuo; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Onuma, Yuichi; Watanabe, Hiroyuki; Inoue, Shuichi; Izumo, Hironobu; Ishida, Takuya; et al.

JAEA-Technology 2008-012, 36 Pages, 2008/03

JAEA-Technology-2008-012.pdf:10.09MB

It is known that Irradiation Assisted Stress Corrosion Cracking (IASCC) occurs when austenitic stainless steel components used for light water reactor (LWR) are irradiated for a long period. In order to evaluate the high aging of the nuclear power plant, the study of IASCC becomes the important problem. The specimens irradiated in the reactor were evaluated by post irradiation examination in the past study. For the appropriate evaluation of IASCC, It is necessary to test it under the simulated LWR conditions; temperature, water chemistry and irradiation conditions. In order to perform in-pile SCC test, saturated temperature capsule (SATCAP) was developed. There are crack growth test, crack propagation test and so on for in-pile SCC test. In this report, SATCAP for crack propagation test is reported.

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