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JAEA Reports

Feasibility study on dismantling and removal of hydraulic rabbit No.1 irradiation facility

Magome, Hirokatsu; Iimura, Koichi; Matsui, Yoshinori

JAEA-Testing 2020-008, 52 Pages, 2021/02

JAEA-Testing-2020-008.pdf:5.46MB

As to the removal of the hydraulic rabbit No.1 irradiation facility related to the decommissioning of JMTR, points to be noted for considering a removal plan and maintenance methods after the removal were studied based on the past experiences of removing the hydraulic rabbit No.2 irradiation facility. As results, it became clear that it was necessary to (1) add a shutoff valve and a closing flange to piping for preventing cooling water leakage, (2) prepare a drawing jig for inner tube, and (3) shorten the remaining piping to withstand earthquakes. In addition, regarding the management of equipment to be maintained after removal, the necessary management items for the removal methods of the three patterns of ground equipments were listed.

JAEA Reports

Seismic evaluation of canal underwater equipment for hydraulic rabbit No. 1 irradiation facility

Magome, Hirokatsu; Iimura, Koichi; Matsui, Yoshinori

JAEA-Technology 2020-022, 32 Pages, 2021/02

JAEA-Technology-2020-022.pdf:4.04MB

Among the canal underwater equipment of HR-1, seismic evaluations of the canal side wall parts and the canal bottom surface parts were carried out for the insertion device, take-out device and decay tank. As a result, it was confirmed that the equipments have sufficient seismic resistances because the maximum stress of the canal side wall joint, the bolt portion of the canal bottom joint, and the fillet weld are within the allowable stress.

Journal Articles

Conceptual study on parasitic low-energy RI beam production with in-flight separator BigRIPS and the first stopping examination for high-energy RI beams in the parasitic gas cell

Sonoda, Tetsu*; Katayama, Ichiro*; Wada, Michiharu*; Iimura, Hideki; Sonnenschein, V.*; Iimura, Shun*; Takamine, Aiko*; Rosenbusch, M.*; Kojima, Takao*; Ahn, D. S.*; et al.

Progress of Theoretical and Experimental Physics (Internet), 2019(11), p.113D02_1 - 113D02_12, 2019/11

AA2019-0315.pdf:1.37MB

 Times Cited Count:0 Percentile:0.01(Physics, Multidisciplinary)

An in-flight separator, BigRIPS, at RIBF in RIKEN provides each experiment with specific nuclides separated from many nuclides produced by projectile fragmentation or in-flight fission. In this process, nuclides other than separated ones are discarded on the slits in BigRIPS, although they include many nuclides interested from the view point of nuclear structure. In order to extract these nuclides for parasitic experiments, we are developing a method using laser ion-source (PALIS). A test experiment with $$^{78}$$Se beam from RIBF has been performed by using a gas cell set in BigRIPS. Unstable nuclides around $$^{67}$$Se were stopped in the gas cell in accordance with a calculation using LISE code. The stopping efficiency has been estimated to be about 30%. As a next step, we will establish the technique for extracting reaction products from the gas cell.

Journal Articles

Status of JMTR decommissioning plan formulation, 2

Otsuka, Kaoru; Ide, Hiroshi; Nagata, Hiroshi; Omori, Takazumi; Seki, Misaki; Hanakawa, Hiroki; Nemoto, Hiroyoshi; Watanabe, Masao; Iimura, Koichi; Tsuchiya, Kunihiko; et al.

UTNL-R-0499, p.12_1 - 12_8, 2019/03

no abstracts in English

Journal Articles

Present status of J-PARC linac

Oguri, Hidetomo; Hasegawa, Kazuo; Ito, Takashi; Chishiro, Etsuji; Hirano, Koichiro; Morishita, Takatoshi; Shinozaki, Shinichi; Ao, Hiroyuki; Okoshi, Kiyonori; Kondo, Yasuhiro; et al.

Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.389 - 393, 2014/10

no abstracts in English

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

Fabrication study of new irradiation facility for $$^{99}$$Mo production in JMTR

Takita, Kenji; Iimura, Koichi; Tomita, Kenji; Endo, Yasuichi; Kanno, Masaru

JAEA-Technology 2012-006, 41 Pages, 2012/03

JAEA-Technology-2012-006.pdf:6.8MB

At JAEA Oarai Research and Developnment Establishment (JAEA Oarai), JAEA Oarai was proceeding a plan to repair JMTR, which is to re-operate in fiscal 2012. Additionally, as an effective utilizati of JMTR, JAEA Oarai is planning to manufacture $$^{99}$$Mo, which is a parent nuclide of $$^{99}$$Tc. $$^{99m}$$Tc is most commonly used as a radiopharmaceution in the field of nuclear medicine. Currently $$^{99}$$Mo supply is dependent only on foreign imports, so JAEA is aiming for working on partially manufacturing $$^{99}$$Mo domestically with industrial circles in Japan. In this article, this report described the choice and fabric of irradiathion facility named Hydraulic Rabbit Facility for manufacturing $$^{99}$$Mo, the technical study of fabrication technique.

Journal Articles

Status of the design and investigation for hydraulic rabbit irradiation facility

Takita, Kenji; Iimura, Koichi; Tomita, Kenji; Endo, Yasuichi; Kanno, Masaru

UTNL-R-0480, p.7_4_1 - 7_4_6, 2012/03

no abstracts in English

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

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

Development of measuring instruments for material irradiation tests

Kitagishi, Shigeru; Tanimoto, Masataka; Iimura, Koichi; Inoue, Shuichi; Saito, Takashi; Omi, Masao; Tsuchiya, Kunihiko

JAEA-Review 2010-046, 19 Pages, 2010/11

JAEA-Review-2010-046.pdf:2.51MB

The Japan Materials Testing Reactor (JMTR) has been utilized for the various neutron irradiation tests of fuels and materials, as well as for radioisotope production since achieving the first criticality in March 1968. The operation of JMTR was halted for the refurbishment in August 2006. The new JMTR is expected to contribute to many fields: the lifetime extension of LWRs and the expansion of industry use. To meet a wide range of users' needs, the development of new irradiation technologies has been carried out for the new JMTR. This report summarizes the present conditions of the development of FP gas pressure gauges, multi-paired thermocouples, ECP and ceramics sensors.

JAEA Reports

Design of fuel transient test facility system

Hosokawa, Jinsaku; Iimura, Koichi; Ogawa, Mitsuhiro; Tomita, Kenji; Yamaura, Takayuki

JAEA-Technology 2010-018, 269 Pages, 2010/08

JAEA-Technology-2010-018.pdf:5.75MB

At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) advances the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in fiscal 2011. Fuel Transient Test Facility is scheduled to be set up as neutron irradiation test equipment of the light-water reactor fuel that uses JMTR after it operates again. The abnormal transition examination device is the irradiation facilities where the output sudden rise examination that makes the light-water reactor fuel an irradiation sample is done to use it to develop the safety evaluation technology and the damage influence evaluation technology of the light-water reactor fuel that reaches high burn-up. In this report, as for the system design, it is a summary to JMTR among detailed designs of the abnormal transition examination device of the installation schedule.

JAEA Reports

Design examination of the high-duty irradiation loop

Ogawa, Mitsuhiro; Iimura, Koichi; Hosokawa, Jinsaku; Kanno, Masaru

JAEA-Technology 2010-019, 178 Pages, 2010/07

JAEA-Technology-2010-019.pdf:20.16MB

JMTR is making preparations of the irradiation examinations towards the re-operation from the 2011 fiscal year now. Design examination of the high-duty irradiation loop is in one of these irradiation examinations of the irradiation plan. The examination is the plan to carry out the irradiation examination of the light water reactor fuel (uranium fuel and mixed oxide fuel) which reached the high burnup, under the irradiation environment nearer to the light water reactor plant. In the 2009 fiscal year, we carried out (1) System design and (2) Earthquake-proof calculation of in-pile tube of the high-duty irradiation loop. And, for the fuel action between covering pipe and pellets of fuel rod which reached the high burnup, we carried out (3) System design of the lift-off test facility. Moreover, we carried out (4) Examination about detection system of fuel breakage when a fuel sample is damaged, and (5) Examination about system composition of effluent treatment system.

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

Seismic analysis for shroud facility in-pile tube and saturated temperature capsules

Iimura, Koichi; Yamaura, Takayuki; Ogawa, Mitsuhiro

JAEA-Technology 2009-033, 45 Pages, 2009/07

JAEA-Technology-2009-033.pdf:5.01MB

At Oarai Research and development center, Japan Atomic Energy Agency (JAEA), the plan of repairing and refurbishing Japan Materials Testing Reactor (JMTR) has progressed in order to restart JMTR operation in the fiscal 2011. By using Oarari Shroud Facility and fuel irradiation facility with the He-3 gas control system for power lamping test using boiling water capsules. By using saturated temperature capsules and the water environment control system, the material irradiation tests under the water chemistry condition of LWL will be carried out to clarify the mechanism of IASCC. The detailed design for renewal or remodeling was carried out based on the new design condition in order to be correspondent to the irradiation test plan after restart JMTR operation. Stress calculation and evaluation were carried out by fem piping analysis code SAP and structure analysis code ABAQUS. It was proven by the analysis that these facilities maintain the structural integrity under earthquake condition.

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.

JAEA Reports

Dose evaluation for fuel transient test

Iimura, Koichi; Ogawa, Mitsuhiro; Tomita, Kenji; Tobita, Masahiro

JAEA-Technology 2009-021, 71 Pages, 2009/05

JAEA-Technology-2009-021.pdf:4.34MB

The preparation of a fuel transient test using the JMTR is advanced to conduct its irradiation test from 2011 F.Y. after re-operation of the JMTR. The fuel behavior for high burn-up BWR's under power ramping condition will be evaluated in simulating the BWR environmental condition using the shroud irradiation facility (Oarai Shroud Facility No.1) and $$^{3}$$He power-control type BOCA (Boiling Water Capsule) irradiation facility, which is composed of the capsule control device, $$^{3}$$He power-control device and boiling water capsule. In order to change the fuel irradiation conditions so as to treat high burn-up fuels (from 50 GWD/t-UO$$_{2}$$ to 110 GWD/t-U), it is necessary to revaluate the dose for the safety evaluation at the test fuel failure. In this report, evaluations for equivalent dose rate of each device and exposure dose of handling operators when all fission products released in the coolant of the capsule control device and the BOCA at fuel failure in the fuel transient test are summarized.

JAEA Reports

Dose evaluation of external exposure by direct and skyshine gamma rays of nuclear fuel handling facilities at JMTR

Ogawa, Mitsuhiro; Iimura, Koichi; Tomita, Kenji; Tobita, Masahiro

JAEA-Technology 2009-017, 254 Pages, 2009/05

JAEA-Technology-2009-017.pdf:15.04MB

In JMTR, upgrade of irradiation facilities is advanced to re-operate from 2011 F.Y. In order to irradiate test fuels of high-burnup, external exposure reassessment by direct and skyshine gamma rays of the nuclear fuel handling facility at JMTR was performed. In evaluation method, radiation source of maximum use of the nuclear fuel was calculated by using ORIGEN2 code. Dose equivalent rate for supervised area boundary was calculated by modeling reactor building at using shielding calculation codes QAD-CGGP2 and G33-GP2. As a result of evaluation, it was confirmed that the effective dose equivalent during year was low enough at supervised area boundary of the JMTR site.

JAEA Reports

Study on $$^{99}$$Mo production by solution irradiation method, 2; Characterization of aqueous molybdate solutions under $$gamma$$-ray irradiation

Inaba, Yoshitomo; Ishikawa, Koji*; Iimura, Koichi; Tatenuma, Katsuyoshi*; Ishitsuka, Etsuo

JAEA-Technology 2009-013, 72 Pages, 2009/05

JAEA-Technology-2009-013.pdf:32.51MB

In the present study, using two kinds of aqueous molybdate solutions (an aqueous ammonium molybdate solution and an aqueous potassium molybdate solution) selected as candidates for the irradiation target of the solution irradiation method for $$^{99}$$Mo production, the compatibility between the solutions and structural materials, the chemical stability, circulation characteristics, radiolysis and $$gamma$$ heating of the solutions were investigated under $$gamma$$-ray irradiation. In addition, the integrity of PZC was investigated under $$gamma$$-ray irradiation. As a result, the following were found: (1) the compatibility between the solutions and stainless steel is very well, (2) the solutions are chemically stable and have a smooth circulation, (3) the ratios of hydrogen in the gases generated by the radiolysis of the solutions are higher than that of pure water, (4) the effect of $$gamma$$ heating on the solutions is the same level as that on pure water, and (5) the integrity of PZC is maintained.

JAEA Reports

Study on $$^{99}$$Mo production by solution irradiation method, 1; Characterization of aqueous molybdate solutions under unirradiation

Inaba, Yoshitomo; Ishikawa, Koji*; Iimura, Koichi; Tatenuma, Katsuyoshi*; Ishitsuka, Etsuo

JAEA-Technology 2009-012, 80 Pages, 2009/05

JAEA-Technology-2009-012.pdf:37.29MB

In the present study, the schematic structure of the $$^{99}$$Mo production system with the solution irradiation method was investigated, and two kinds of aqueous molybdate solutions (an aqueous ammonium molybdate solution and an aqueous potassium molybdate solution) were selected as candidates for the irradiation target of the solution irradiation method, and then the molybdenum adsorption performance of PZC with the solutions, the properties of the molybdates to be materials of the solutions, the compatibility between the solutions and structural materials, and the chemical stability of the solutions were investigated under unirradiation. As a result, it was found that the aqueous potassium molybdate solution is promising as the target in terms of the molybdenum content, the compatibility with the structural materials, and the chemical stability and that the aqueous ammonium molybdate solution with suitable pH adjustment has an aptitude for the target. In addition, it became clear that stainless steel having good compatibility with the solutions has a potential as the structural material of capsules, pipes and so on.

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