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Tsuruta, Tadahiko; Takeda, Masaki; Ueno, Takashi; Daimaru, Shuji; Tokuyasu, Shingo; Onoe, Hironori; Shingu, Shinya; Ishibashi, Masayuki; Takeuchi, Ryuji; Matsuoka, Toshiyuki; et al.
JAEA-Technology 2012-001, 134 Pages, 2012/03
JAEA-Technology-2012-001.pdf:41.2MBJAEA-Technology-2012-001(errata).pdf:0.44MBJAEA-Technology-2012-001-appendix(CD-ROM).pdf:6.37MB
Tono Geoscientific Research Unit of Japan Atomic Energy Agency (JAEA) is performing the Mizunami Underground Research Laboratory (MIU) project in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in fractured crystalline rock. The borehole investigations (two boreholes; 10MI22 borehole and 10MI23 borehole) have been carried out to obtain information on geological, hydrological and hydrochemical characteristics in and around the Main-shaft fault. These investigations provided that features of fracture and alteration on rock mass in and around the Main-shaft fault. Hydrological and hydrochemical properties based on the geological features were also obtained.
Hanaki, Tatsumi; Nagasaki, Yasushi; Suzuki, Hajime
JAEA-Technology 2012-002, 8 Pages, 2012/03
JAEA-Technology-2012-002.pdf:2.35MB
In the "Plan for meeting the midterm goal (Midterm plan, April 1st, 2010 to March 31st, 2015)" by JAEA, it is planned that the closure activities of the Tono Mine will be started during the period of the Midterm plan. The closure activities at the Tono Mine were reviewed and "Plan for Closure Activities of the Tono Mine; Mine Closure Activities under Review" was developed in June 2010. This report presents detailed closure activities of the facilities and equipment of the Tono Mine.
Horiguchi, Hironori; Nakamura, Takemi; Motohashi, Jun; Kashimura, Takanori; Ichimura, Shigeju; Sasajima, Fumio
JAEA-Technology 2012-003, 38 Pages, 2012/03
JAEA-Technology-2012-003.pdf:2.55MB
Clinical trials of boron neutron capture therapy (BNCT) for malignant brain tumors and head and neck cancers have been performed at the research reactor JRR-4. BNCT is a kind of radiation therapy using a nuclear reaction with thermal neutrons and boron (
B) elements administered to a patient. The design specifications of all types of reflector elements were changed due to a trouble of a reflector element in JRR-4. In the production of the new reflector elements, they were designed with the influence for the neutron beam facility by the analytical calculation. After the installation of the new reflector elements, the performance of the neutron beam facility was verified by measurement such as a free air experiment and a water phantom experiment. The calculation error used in the treatment planning for BNCT can be estimated by comparing the results of our calculation with the corresponding experimental data.
Ono, Masato; Tochio, Daisuke; Shinohara, Masanori; Shimazaki, Yosuke; Yanagi, Shunki; Iigaki, Kazuhiko
JAEA-Technology 2012-004, 46 Pages, 2012/03
JAEA-Technology-2012-004.pdf:3.17MB
Tohoku-Pacific Ocean Earthquake occurred on March 11th 2011 and the earthquake intensity of an upper 5 on the Japanese scale was observed in Oarai town. HTTR conducted the confirmation test on cold state in order to ensure the facilities/instruments of reactor building operate normally. In this test, the plant data in the facilities/instruments start up phase and continue steady operation phase were measured and compared with the previous operation data, and the soundness of facilities/instruments is evaluated. As a result, the facilities/instruments operate normally and keep safety and performance of the HTTR were ensured. This paper reports the evaluation of the plant data.
Editorial Committee of Refining and Conversion Facility Decommissioning Results
JAEA-Technology 2012-005, 64 Pages, 2012/04
JAEA-Technology-2012-005.pdf:6.26MB
The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008. Equipments in radiation controlled area (excluding ventilating equipment and liquid waste treatment equipment) will be dismantled by the 2011 fiscal year, and ventilating equipment and liquid waste treatment equipment will be dismantled by the 2014 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in first half year of 2011FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes.
Mo production in JMTRTakita, 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 Mo, which is a parent nuclide of Tc. 
Tc is most commonly used as a radiopharmaceution in the field of nuclear medicine. Currently Mo supply is dependent only on foreign imports, so JAEA is aiming for working on partially manufacturing 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 Mo, the technical study of fabrication technique.
Takahashi, Kiyoshi; Hanawa, Hiroshi; Onuma, Yuichi; Hosokawa, Jinsaku; Kanno, Masaru
JAEA-Technology 2012-007, 31 Pages, 2012/03
JAEA-Technology-2012-007.pdf:4.76MB
The Japan Materials Testing Reactor (JMTR), achieving first criticality in March 1968, has been used in testing the durability and integrity of reactor fuels and components, basic nuclear research, the production of radioisotopes, and other purposes. The JMTR, however, stopped in August 2006 after its 165th operation cycle, and is currently under going partial renewal of reactor facilities and installation of new irradiation facilities, geared toward being restarted in 2012. Now, the installation of two new irradiation facilities under the LWR irradiation environment were finished until 2011FY. One is a power ramping test facility of high-burnup fuel. Another one is a material irradiation facility for IASCC research under the LWR irradiation environment. And another irradiation facility (Hydraulic rabbit irradiation facility) maintenance is carried out on 2011FY. This report is described the installed new irradiation facilities and established irradiation facility until 2011FY in JMTR.
Kitamura, Koichi; Rindo, Hiroshi; Hasegawa, Makoto; Shimomura, Atsuhiko; Nuclear Cycle Backend Co-ordination Office
JAEA-Technology 2012-008, 57 Pages, 2011/11
JAEA-Technology-2012-008.pdf:1.47MB
The management plan is intended to summarize the process of Low level Radioactive Waste in JAEA from its generation to its treatment and disposal. Reasonable implementation of treatment and disposal for the radioactive waste on ensuring security was taken into account when the plan was made or updated based on the Framework for Nuclear Energy Policy made by Japan Atomic Energy Commission in 2005, the progress situation of laws and regulations, safety guides. Moreover, the issues to be solved during the process of implementation the plan were summarized, they will be studied in the plan, and then, its solutions will be reflected in the research program and project. JAEA will be carried out practical work for treatment and disposal of the radioactive waste based on the plan. Then, the updating will be made flexibly according to technology advance and progress situation of laws and regulations.
Naito, Hiroyuki; Itagaki, Wataru; Okazaki, Yoshihiro; Imaizumi, Kazuyuki; Ito, Chikara; Nagai, Akinori; Kitamura, Ryoichi; Shamoto, Naoki*; Takeshima, Yoshiyuki*
JAEA-Technology 2012-009, 100 Pages, 2012/05
JAEA-Technology-2012-009.pdf:9.89MB
The radiation characteristics of image fiber and light guide fiber were evaluated to develop a high radiation resistant fiberscope for the fast reactor in-vessel observation. It is known that a pure silica core fiber has a high radiation resistance and radiation resistance is influenced with impurities in silica. Moreover it is necessary to change the clad material of the light guide fiber because that of the current light guide fiber is acrylate, which is weak against radiation. Hence the improved fibers consist of a pure silica core with 1,000 ppm OH and fluorine-doped silica clad. As a result of a 
irradiation test, we confirm that OH inhibits the generation of the precursor by irradiation. About the clad material, we confirmed that the transmission loss of the fluorine-doped silica clad fiber is smaller than that of the acrylate clad fiber. About the mechanical strength of a fiber, we confirmed that there is no weakening the strength of the fiber and no exfoliation of the coating from the glass. In this study, we discovered the fiber which consists of a pure silica core with 1,000 ppm OH and fluorine-doped silica clad has a high radiation resistance and it is possible to observe using this fiber under the 200 
C after 5
10
Gy irradiation.
Shimazaki, Yosuke; Shinohara, Masanori; Ono, Masato; Yanagi, Shunki; Tochio, Daisuke; Iigaki, Kazuhiko
JAEA-Technology 2012-010, 24 Pages, 2012/05
JAEA-Technology-2012-010.pdf:6.92MB
It is necessary to confirm that the temperature of water cooling panel of the vessel cooling system (VCS) is controlled under the allowable working temperature during the safety demonstration test because the water cooling panel temperature rises due to stop of cooling water circulation pumps. Therefore, several temporary thermocouples are relocated to the side cooling panel outlet ring header of VCS and the water cooling panel near the stabilizers of RPV in order to observe the temperature change of VCS. The relocated thermocouples can measure the temperature change with starting of the water circulation pumps of VCS. So it is confirmed that the relocated thermocouples can observe the VCS temperature change in the safety demonstration test.
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.
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.
Mizukoshi, Yasutaka; Yasu, Tetsunori
JAEA-Technology 2012-013, 26 Pages, 2012/06
JAEA-Technology-2012-013.pdf:6.74MB
The Materials Monitoring Facility is equipped with an exhaust stack to emit air from a controlled area (the hot laboratory) into the atmosphere. Cracks and exfoliation have been observed for the surface of the exhaust stack, which is made of reinforced concrete and was constructed on the seacoast about 25 years ago, so exposed to a salt-corrosive condition. In order to get details of the present condition of the exhaust stack, an inspection was carried out using an electromagnetic wave radar method and chloride content method. Cracks and exfoliation were observed for the whole stack surface, especially for high positions. Moreover, salt damage was observed for the outer surface of the exhaust stack, and it was estimated that the infiltration of the chloride content was about 17 mm. Based on this detailed inspection of the exhaust stack, maintenance and repair work were carried out.
Hara, Hironori; Amazawa, Hiroya; Sakai, Akihiro; Nakata, Hisakazu; Sakamoto, Yoshiaki
JAEA-Technology 2012-014, 49 Pages, 2012/06
JAEA-Technology-2012-014.pdf:3.39MB
Low level radioactive waste which is included high concentrated nitrate are planned to be disposed into concrete pit facility. From the point of view of environmental effect by easily soluble nitrate ion into groundwater, the safety assessment will be needed for the concrete pit type disposal facilities. In this study, the nitrate ion concentration in groundwater, lake and stream nearby the concrete pit type disposal facilities was simulated by advective-diffusion analysis. From the results of analysis, the limitation of amount of nitrate in the waste package was estimated from the environmental standard determined by Basic Environment Law.
Uesaka, Takahiro; Kozawa, Masachiyo; Matsumoto, Junko; Endo, Masayuki; Kinoshita, Junichi; Suzuki, Takeshi; Suzuki, Hisao; Morishita, Satoru; Sakamoto, Yu
JAEA-Technology 2012-015, 29 Pages, 2012/06
JAEA-Technology-2012-015.pdf:3.22MB
In Japan Atomic Energy Agency Nuclear Science Research Institute waste treatment building No.2 treat intermediate-level solid waste. Solid wastes are reduced in volume by compaction. They are then canned in stainless can, which are subsequently put in 200-liter concrete-lined drums or 1-m
concrete containers, filled with concrete. To prepare for disposal in future, be able to make fit with the technical standard of waste package, we were asked to change the lid type shielded container. Therefore due to the change of lid type shielded container, we confirmed integrity of it with evaluation of close volt by drop analysis, evaluation of shielding, and drop test with a prototype model.
Imamoto, Nobuo; Koiso, Keiichi
JAEA-Technology 2012-016, 27 Pages, 2012/06
JAEA-Technology-2012-016.pdf:1.49MB
The shaking table tests have been employed to evaluate the seismic fragilities of the machine-electric equipments. Through the shaking table test, in ordinarily it is depending on resonance frequency, repetitive adjustments are needed to search a normal/malfunction boundary. However, a small relay used for the electric panel and the control system, can not be measured the resonance frequency because the acceleration sensor installation affects the vibration characteristic of the test body. And more, the moving parts leading to a relay malfunction is settled in the case, it can not be carried out direct measurement of the vibration. To improve the shaking table test methods, magnetization current perturbation method was invented and developed. Instead the mechanical shaking force, magnetization current perturbation method employs vibrating electromagnet force. Moreover, obtained impedance characteristic curve, the resonance frequency can be obtained by fitting to a theoretical curve. This paper deals with the principle of the magnetization current perturbation method, theoretical derivation of impedance, measurement electronics circuit, and system design and test results.
Goto, Minoru; Seki, Yasuyoshi; Inaba, Yoshitomo; Ohashi, Hirofumi; Sato, Hiroyuki; Fukaya, Yuji; Tachibana, Yukio
JAEA-Technology 2012-017, 29 Pages, 2012/06
JAEA-Technology-2012-017.pdf:1.87MB
Japan Atomic Energy Agency has started a conceptual design of a small-sized HTGR with 50 MW thermal power (HTR50S), which is a first-of-a-kind commercial or demonstration plant of a small-sized HTGR to be deployed in developing countries in the 2020s. The nuclear of the HTR50S was performed by upgrading the proven technology of High Temperature Engineering Test Reactor (HTTR) to reduce cost for the construction. In the nuclear design, reduce the number of fuel enrichment comparing with the HTTR is one of the important subject to be upgraded. The optimization of the power distribution in the core, which is required to suppress the maximum fuel temperature below the limitation, was completed successfully by using only three fuel enrichment and the number of fuel enrichment was reduced significantly compared with the HTTR.
Ijiri, Yuji*; Noda, Masaru*; Sasakura, Takeshi*; Nobuto, Jun*; Matsui, Hiroya; Mikake, Shinichiro; Hashizume, Shigeru
JAEA-Technology 2012-018, 288 Pages, 2012/07
JAEA-Technology-2012-018.pdf:19.13MB
The researches on engineering technology in the Mizunami Underground Research Laboratory plan consists of (1) research on engineering technology at a deep underground, and (2) research on engineering technology as a basis of geological disposal. The former research mainly aimed in this study are categorized in (a) development of design and construction planning technologies, (b) development of construction technology, (c) development of countermeasure technology, (d) development of technology for security. In this study, the researches on engineering technology are proceeded in these four categories by using data measured down to GL-300m during construction as a part of the second phase of the MIU plan.
Inaba, Yoshitomo; Sato, Hiroyuki; Goto, Minoru; Ohashi, Hirofumi; Tachibana, Yukio
JAEA-Technology 2012-019, 142 Pages, 2012/06
JAEA-Technology-2012-019.pdf:4.54MB
JAEA has started the conceptual designs of small-sized HTGR systems, aiming for the deployment in developing countries. The small-sized HTGR systems can provide power generation by steam turbine, high temperature steam for industry process and/or low temperature steam for district heating. As one of the conceptual designs in the first stage, the core thermal and hydraulic design of a power generation and steam supply small-sized HTGR with a thermal power of 50 MW (HTR50S) was carried out. HTR50S in the first stage has the same coated particle fuel as HTTR. The purpose of the design is to make sure that the maximum fuel temperature in normal operation doesn't exceed the design target. Following the design, safety analysis assuming a depressurization accident was carried out. The fuel temperature in the normal operation and the fuel and reactor pressure vessel temperatures in the depressurization accident were evaluated. As a result, it was cleared that the thermal integrity of the fuel and the reactor coolant pressure boundary is not damaged.
Takamatsu, Misao; Kobayashi, Tetsuhiko; Nagai, Akinori
JAEA-Technology 2012-020, 60 Pages, 2012/07
JAEA-Technology-2012-020.pdf:6.03MB
With the incident as an opportunity, repair techniques for upper core structure (UCS) replacement was developed in Joyo. Since UCS of Joyo was designed as an eternal structure and it has high radioactivity due to the irradiation for over 30 years, (1) Prevention of deformation during UCS jack-up and retrieval, (2) Reducing UCS cask weight were mainly discussed in this study as critical tasks. UCS replacement is scheduled in 2014. Achievement of UCS replacement and accumulated experience will be able to provide valuable insights for further improving and verifying repair techniques in SFRs.
Honda, Junichi; Matsui, Hiroki; Harada, Akio; Obata, Hiroki; Tomita, Takeshi
JAEA-Technology 2012-021, 17 Pages, 2012/07
JAEA-Technology-2012-021.pdf:4.17MB
The advanced utilization of Light Water Reactor (LWR) fuel is progressed in Japan to save the power generating cost and the volume of nuclear wastes. The electric power companies have been continued the approach to extend the burnup and to rise up the thermal power of the commercial fuel. The government should be accumulating the detailed information of the newest technologies to make the regulations and guidelines for the safety of the advanced nuclear fuels. The ion milling for post irradiation examination has been developed in Japan Atomic Energy Agency (JAEA) to investigate cladding microstructure. This device has been modified to operate the high radioactive elements remotely and have the performance of earthquake resistant. This paper describes the specification of the device which were specialized for post irradiation examination and the test results of the cold mock-up to confirm their performances and reliabilities.
Honda, Junichi; Matsui, Hiroki; Harada, Akio; Obata, Hiroki; Tomita, Takeshi
JAEA-Technology 2012-022, 35 Pages, 2012/07
JAEA-Technology-2012-022.pdf:3.58MB
The advanced utilization of Light Water Reactor (LWR) fuel is progressed in Japan to save the power generating cost and the volume of nuclear wastes. The electric power companies have been continued the approach to extend the burnup and to rise up the thermal power of the commercial fuel. The government should be accumulating the detailed information of the newest technologies to make the regulations and guidelines for the safety of the advanced nuclear fuels. The remote controlled Electron Prove Micro Analyzer attached with crystal orientation analyzer (EPMA) has been developed in Japan Atomic Energy Agency (JAEA) to evaluate the fuel behavior effected by the cladding microstructure under the accident condition. The device was modified to the airtight and earthquake resistant structure for the examination of high radioactive elements. This paper describes the specification of EPMA and the test results of the cold mock-up to confirm their performances and reliabilities.
Zaima, Naoki; Nakashima, Shinichi; Nakatsuka, Yoshiaki; Kado, Kazumi
JAEA-Technology 2012-023, 36 Pages, 2012/08
JAEA-Technology-2012-023.pdf:1.54MB
We developed uranium mass assay systems for 200-litter wastes drums applied neutron and measurements by NDA method. In this report we will describe measurement experiences followed by the previous report. The systems are composed of the 16 pieces of helium-3 (He) proportional counters for neutron detection. The neutron measurement methodology is consist of 
U (
,n)F reaction and spontaneous fission of 
U. The extensive test trials using the known amount of uranium with different enrichment and some kinds of matrices in drums were performed. By using this NWAS we tried to determine uranium mass in the actual uranium wastes drums stored in the URCP at Ningyo-toge. The actual uranium wastes drums are of great variety, in the point of matrix, bulk density, packing condition and total uranium mass. Therefore we have tried some challenging methods which eliminate problems, and established the applicability to almost all kinds of wastes drums.
reflector and proton beam windowTeshigawara, Makoto; Kinoshita, Hidetaka; Wakui, Takashi; Meigo, Shinichiro; Seki, Masakazu; Harada, Masahide; Ito, Manabu; Suzuki, Toru; Ikezaki, Kiyomi; Maekawa, Fujio; et al.
JAEA-Technology 2012-024, 303 Pages, 2012/07
JAEA-Technology-2012-024.pdf:46.04MB
3 GeV Protons with 1 MW beam power are irradiated to mercury target of spallation neutron source in Materials and Life science Facility (MLF), which is one of facilities of J-PARC. Irradiated components, such as target container, moderator, reflector and proton beam window, are needed to replace periodically due to irradiation damage of high energy protons and neutrons. These used components are replaced remotely because of highly activated. Maintenance scenario was settled so as to handle these components. Required remote handling machines were designed and installed in hot cell and other room of the MLF. We performed remote handling tests by using actual components to confirm the design. We report results, such as replacement procedure, trouble and its solution, etc., for moderator, reflector and proton beam window in order to provide the handling of actual used components.
Shinohara, Masanori; Sawahata, Hiroaki; Kawamoto, Taiki; Motegi, Toshihiro; Saito, Kenji; Takada, Shoji; Yoshida, Naoaki; Isozaki, Ryosuke; Katsuyama, Kozo
JAEA-Technology 2012-025, 31 Pages, 2012/08
JAEA-Technology-2012-025.pdf:4.69MB
An event, in which one of WRMs were disabled to detect the neutron flux in the reactor core, occurred during the period of reactor shut down of HTTR in March, 2010. The actual life time of WRM was unexpectedly shorter than the past developed life time. Investigation of the cause of the outage of WRM toward the recovery of the life time up to the developed life is one of the issues to develop the technology basis of High Temperature Gas cooled Reactor (HTGR). Then, a post irradiation examination was planned to specify the damaged part causing the event in the WRM was also planned. For the investigation, the X-ray computed tomography scanner in Fuels Monitoring Facility (FMF). This report describes the preliminary investigation on the cause of outage of the WRM. The results of study for transportation method of the irradiated WRM from HTTR to FMF is also reported with the record to complete the transport operation.
Shinohara, Masanori; Motegi, Toshihiro; Saito, Kenji; Takada, Shoji; Ishimi, Akihiro; Katsuyama, Kozo
JAEA-Technology 2012-026, 21 Pages, 2012/08
JAEA-Technology-2012-026.pdf:2.31MB
An event, in which one of WRMs were disabled to detect the neutron flux in the reactor core, occurred during the period of reactor shut down of HTTR in March, 2010. The actual life time of WRM was unexpectedly shorter than the past developed life time. Investigation of the cause of the outage of WRM toward the recovery of the life time up to the past developed life is one of the issues to develop the technology basis of HTGR. Then, two experimental investigations were carried out to reveal the cause of the outage by specifying the damaged part causing the event in the WRM. The one is a post irradiation examination using the X-ray computed tomography scanner in Fuels Monitoring Facility (FMF) to specify the damaged part in the WRM. The other is an experiment using a mock-up simulating the WRM fabricated by the fabricator. This report summarized the results of the PIE and the experimental investigation using the mock-up to reveal the cause of outage of WRM.
Imaizumi, Kazuyuki; Saito, Takakazu; Tobita, Shigeharu; Nagai, Akinori; Kitamura, Ryoichi; Okazaki, Yoshihiro
JAEA-Technology 2012-027, 49 Pages, 2012/08
JAEA-Technology-2012-027.pdf:7.07MB
In-Vessel Observations (IVO) techniques for Sodium cooled Fast Reactors (SFRs) are important in confirming its safety and integrity. In order to secure the reliability of IVO techniques, it was necessary to demonstrate the performance under the actual reactor environment with high temperature, high radiation dose and remained sodium. During the investigation of an incident occurred in Joyo, the following observation systems were specifically developed for Joyo. And the following two observations were conducted. (1) Simple overhead observation using a standard video camera for the top of the sub-assemblies and the in-vessel storage rack (2) Narrow space observation using remote handling device equipped with radiation-resistant fiberscope for the bottom face of the upper core structure. As a result, the observations under the actual reactor environment were successfully made even in the narrow space in the reactor vessel and the results provided useful information on incident investigations and planning of restoration work.
Policy Planning and Administration Department; Nuclear Cycle Backend Directorate
JAEA-Technology 2012-028, 71 Pages, 2012/07
JAEA-Technology-2012-028.pdf:9.75MB
In the second medium term (2010-2015) plans of JAEA, effective and reasonable medium and long term plan for decommissioning of nuclear facility and treatment and disposal of low level radioactive waste in JAEA, based on the premise of safety assurance, is to be formulated by the end of March, 2012. This medium and long term plan is the plan targeting the period over next ten years based on the prospect of the long term waste management from waste generation to waste disposal, and is mainly referred to decommissioning, clearance, waste treatment, waste storage and R&D works. JAEA will be carried out practical work for treatment and disposal of the radioactive waste based on this plan, and also the updating of this plan will be made flexibly according to consideration situation of new framework for nuclear energy policy by the Atomic Energy Commission, technology advance and progress situation of laws and regulations.
Kanazawa, Yusaku; Abiko, Shosuke; Terada, Hideyuki; Kawasaki, Ichio; Isozaki, Norio; Matsumoto, Takenari
JAEA-Technology 2012-029, 82 Pages, 2012/09
JAEA-Technology-2012-029.pdf:7.79MB
Water Supply Facility (WSF) is the facility that products and feed water for Tokai Reprocessing Plant (TRP), Plutonium Fuel Production Facility (PFPF), etc. The kinds of feeding water are drinking water and industrial water that are used for life and operation of TRP, etc. WSF had been constructed in 1958, then it has been operated to 2008. It was received the water from AKOGI pond, then the water was conditioned and fed for many facilities. But it needed high cost for trouble and maintenance because of long-term use. Then new WSF was designed and constructed. The new design is that WSF accepts drinking water and industrial water from local governments; each receiving tank is constructed for new. And operating system and remote monitoring system are installed in WSF that is able to monitor from TUC. This report describes about various activities of the backgrounds, the design, the construction and a future action.
Kawahara, Hirotaka; Yamamoto, Masaya; Tomita, Etsuo; Takamatsu, Misao
JAEA-Technology 2012-030, 50 Pages, 2012/09
JAEA-Technology-2012-030.pdf:6.16MB
JAEA-Technology-2012-030-appendix(CD-ROM).zip:21.06MB
In the experimental fast reactor Joyo, in-vessel observation results showed that 6 pins which were connected between the handling head and the wrapper tube joint of the instrumented test subassembly (MARICO-2) were disconnected. Therefore, in order to confirm whether the disconnected 6 pins will influence reactor's safety or not, loose parts behavior in the reactor vessel was evaluated.
Amazawa, Hiroya; Sakai, Akihiro; Nakata, Hisakazu; Hara, Hironori; Kurosawa, Ryohei; Yamamoto, Masayuki*; Kawata, Yosuke*; Sakamoto, Yoshiaki
JAEA-Technology 2012-031, 338 Pages, 2012/10
JAEA-Technology-2012-031.pdf:19.43MB
JAEA is responsible for siting a proper location to establish new disposal facilities with siting criterion and procedure, in consideration of transparency and impartial for the siting process, based on Plan Concerning the Disposal Business Execution. As a part of the study to draw up siting criterion and procedure, Sensitivity analysis of the disposal facilities from the viewpoint of dose evaluation and cost estimation under various siting condition will be carried out. Therefore, Conceptual design of disposal facilities as a reference case is necessary. The basic condition of the design conforms to the property, quantity, radioactivity of waste packages, technical standards and likely siting condition. This report summarizes the results of the reasonable design of our disposal facilities and the layout of the place of activity where the disposal facilities and associated facilities to be installed.
Shinohara, Masanori; Motegi, Toshihiro; Saito, Kenji; Haga, Hiroyuki; Sasaki, Shinji; Katsuyama, Kozo; Takada, Kiyoshi*; Higashimura, Keisuke*; Fujii, Junichi*; Ukai, Takayuki*; et al.
JAEA-Technology 2012-032, 29 Pages, 2012/11
JAEA-Technology-2012-032.pdf:6.57MB
An event, in which one of WRMs were disabled to detect the neutron flux in the reactor core, occurred during the period of reactor shut down of HTTR in March, 2010. The actual life time of WRM was unexpectedly shorter than the past developed life time. Investigation of the cause of the outage of WRM toward the recovery of the life time up to the past developed life is one of the issues to develop the technology basis of HTGR. Then, two experimental investigations were carried out to reveal the cause of the malfunction by specifying the damaged part causing the event in the WRM. One is an experiment using a mock-up sample test which strength degradation on assembly accuracy and heat cycle to specify the damaged part in the WRM. The other is a destructive test in FMF to specify the damaged part in the WRM. This report summarized the results of the destructive test and the experimental investigation using the mock-up to reveal the cause of malfunction of WRM.
Yoshida, Eiichi; Hirakawa, Yasushi; Yatabe, Toshio
JAEA-Technology 2012-033, 177 Pages, 2012/11
JAEA-Technology-2012-033.pdf:17.98MB
In JAEA, lots of tests using sodium had been carried out on the development of sodium component systems and sodium technologies for the experimental reactor JOYO and prototype reactor MONJU. When research and development has come to the end of the first stage for these reactors, those sodium test facilities has dismantled and attached sodium has been cleaned. Lots of experiences and knowledge of sodium cleaning treatment technologies has accumulated. In order to use those experiences and knowledge effectively for future sodium technology and research on the next generation fast reactors, experiences and knowledge of sodium technologies for typical systems and components has been evaluated and knowledge related important topics has been rearranged. Based on those evaluation and rearrangement, technical guidelines of sodium cleaning treatment technologies has been proposed for the purpose of effective reference of the past experiences and knowledge.
Sakatani, Keiichi; Nakatani, Takayoshi; Funabashi, Hideyuki
JAEA-Technology 2012-034, 20 Pages, 2012/12
JAEA-Technology-2012-034.pdf:10.22MB
We planned the gas-accumulating type corrosion test on Zr-2.5wt%Nb alloy which is used in the pressure tube of Fugen (ATR) in order to obtain long-term corrosion rate data under the low oxygen and alkaline conditions assuming the disposal environment. Before starting the test, we examined the specimen machining method and confirmed the corrosion test conditions.
Muraguchi, Yoshinori; Kanayama, Fumihiko; Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo
JAEA-Technology 2012-035, 69 Pages, 2012/12
JAEA-Technology-2012-035.pdf:4.96MB
Dismantling activities of equipment in JAEA's Reprocessing Test Facility (JRTF) used for wet reprocessing test started from 1996. Glove boxes and hoods installed in the main building were dismantled preferentially for securing temporary place of dismantled waste and dismantling tools by dismantling activities. Of these, 8 glove boxes (glove box group) were installed in room 232 of the main building. The glove box group was dismantled by setting up a large plastic enclosure (greenhouse) for work efficiency. In this report, dismantling procedure and actual data obtained from dismantling activity were arranged about dismantling activity of glove box group of room 232 in 1996. About dismantling activity of glove box group, manpower of the basic work items extracted by classifying into common work items and independent work items were analyzed. In addition, calculation equation was examined concerning dismantling of glove boxes.
Torii, Tatsuo; Sanada, Yukihisa; Sugita, Takeshi; Kondo, Atsuya*; Shikaze, Yoshiaki; Takahashi, Masaki; Ishida, Mutsushi; Nishizawa, Yukiyasu; Urabe, Yoshimi
JAEA-Technology 2012-036, 182 Pages, 2012/12
JAEA-Technology-2012-036.pdf:41.89MB
We carried out aerial radiation monitoring (ARM) of all Japan area in order to investigate the influence of the radio cesium which was emitted into the atmosphere by disaster of the Fukushima Dai-ichi Nuclear Power Plant of Tokyo Electric Power Co., Inc.. AMS can measure a ray quickly by flight from 300 m height above the ground. Moreover, ARM has an advantage which can grasp self-possessed quantity distribution of an air dose rate and radioactive cesium in "field", and is visually intelligible. Although there were apparatus and the technique of ARM in our country, sufficient preparations for wide area monitoring were not made. Therefore, it fixed based on the method of the U.S. Department of Energy (DOE) about the method of the conversion to all radiation dose, and the conversion method to radiocesium deposition and the method of mapping. It is possible to discriminate from a background (cosmic-ray, self-contamination and natural nuclides) at the time of western-part-of-Japan measurement by improving of the method in parallel to data acquisition. By this monitoring, it was able to check about the distribution situation of the air dose rate of the Japanese whole region, or the radioactive cesium deposition. Here, the measurement technique and a result are described.
Kubo, Shinji; Yoshino, Koji*; Takemoto, Jumpei*; Kasahara, Seiji; Imai, Yoshiyuki; Onuki, Kaoru
JAEA-Technology 2012-037, 20 Pages, 2013/01
JAEA-Technology-2012-037.pdf:17.29MB
Densities of Bunsen reaction solutions in the iodine-sulfur process were measured with an oscillating U-tube density meter. Two types of the solutions were prepared to simulate sulfuric acid solutions and hydriodic acid solutions of the Bunsen reaction step. The former solution ranged in concentration from 0 to 45 wt% of sulfuric acid containing HI and I
of 0-2 mole%; the latter solution contained 0-17 mole% I, 1-15 mole% HI and 0-2 mole% HSO
. The temperature of the measured solution were 10-60 C. It was found that, in both solutions, the effect of HI and I concentration on the density could well be represented by using a kind of mole fraction of iodine atom. Based on the finding, a set of correlation equations between the densities and the compositions were derived. Additionally, viscosities of ploy-hydriodic acid were measured using an oscillating viscosity meter in temperature range of 5-40 C, and in the composition range of 0-17 mole% I and 1-15 mole% HI; a empirical equation to calculate viscosity from the composition and the temperature are obtained.
Shibahara, Yuji; Ishigami, Tsutomu; Morishita, Yoshitsugu; Yanagihara, Satoshi*; Arita, Yuji*
JAEA-Technology 2012-038, 72 Pages, 2013/01
JAEA-Technology-2012-038.pdf:3.68MB
To implement a decommissioning project reasonably, it is necessary and important to beforehand evaluate project management data as well as to select an optimum dismantling scenario among various scenarios postulated. Little study on the subject of selecting an optimum scenario has been carried out, and it is one of the most important subjects in terms of decision making. In FY 2009, Japan Atomic Energy Agency and University of Fukui launched the joint research of a decision making method which is important to determine a decommissioning plan. The purpose of this research is to construct a methodology for selecting an optimum dismantling scenario among various scenarios postulated based on calculated results of project management data for FUGEN. Project management data for several dismantling scenarios postulated at FUGEN were evaluated based on actual dismantling work for feedwater heater at FUGEN, and an optimum scenario was discussed using the AHP, one of Multi-Criteria Decision Analysis Method. This report describes the results of the joint research in FY 2010.
Park, C.; Tanimoto, Masataka; Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Kaminaga, Masanori
JAEA-Technology 2012-039, 87 Pages, 2013/01
JAEA-Technology-2012-039.pdf:3.55MB
Preliminary accident analysis has been carried out for a LOFA (Loss of Flow Accident) and RIAs (Reactivity Insertion Accidents) of the conceptual 10 MW MRR (multi-purpose research reactor) under design study by using the RELAP5/MOD3 code in order to provide the preliminary evaluation of safety margin as well as the intuitions to the design of the MRR. Input and modeling for the RELAP5/MOD3 simulations have also been described. The analysis results indicate that the concept of the MRR is feasible with practical safety margins. The same events have been also analyzed by using the PARET/ANL and the EUREKA-2/RR codes to compare the codes suitability, which have been widely used for the analysis of research reactors. Same geometric and modeling data used for the RELAP5/MOD3 have been used as long as they correspond to each code's input requirements. The three codes show the same or similar overall trends for the events analyzed, but show a small difference in a specific condition.
Sasaki, Shunichi; Kojima, Atsushi; Shimizu, Tatsuo; Kawai, Mikito*; Hanada, Masaya
JAEA-Technology 2012-040, 26 Pages, 2013/01
JAEA-Technology-2012-040.pdf:5.6MB
Breakdowns occur in the JT-60U 500 kV negative ion accelerator with a high probability during the high voltage conditioning. The breakdown in the accelerator is the same phenomena as a short circuit for the power supply. Surge noise generated by the short circuit causes malfunctions of components in the NBI system and other systems. To evaluate the surge noise characteristics, the breakdown noise has been measured using a test circuit with a spark gap which is the protection gap for the accelerator and it considered to be a source of noise. Further, reduction of the surge noise at the spark gap and countermeasure of the malfunction due to the noise have been studied quantitatively at the side of the system where the malfunction occurs. As a result, it has been observed that the noise propagates through space or grounding lines and gives malfunctions for other systems. To reduce the noise, resistors have been connected in the ground potential side of the gap. It was confirmed that the resistor is effective to reduce the noise and probability of the malfunction has been reduced from 100% to 15%. In addition, by placing the ferrite core in the grounded line and by using an isolation amplifier, the malfunction was further reduced to 10%.
Kokusen, Junya; Sumiya, Masato; Seki, Masakazu; Kobayashi, Fuyumi; Ishii, Junichi; Umeda, Miki
JAEA-Technology 2012-041, 32 Pages, 2013/02
JAEA-Technology-2012-041.pdf:1.6MB
Uranyl nitrate solution fuel used in the STACY and the TRACY is adjusted in the Fuel Treatment System, in which such parameters are varied as concentration of uranium, free nitric acid, soluble neutron poison, and so on. Operations for concentration and denitration of the solution fuel were carried out with an evaporator from JFY 2004 to JFY 2008 in order to adjust the fuel to the experimental condition of the STACY and the TRACY. In parallel, the solution fuel in which some kinds of soluble neutron poison were doped was also adjusted in JFY 2005 and JFY 2006 for the purpose of the STACY experiments to determine neutron absorption effects brought by fission products, etc. After these experiments in the STACY, a part of the solution fuel including the soluble neutron poison was purified by the solvent extraction method with mixer-settlers in JFY 2006 and JFY 2007. This report summarizes operation data of the Fuel Treatment System from JFY 2004 to JFY 2008.
Ono, Takanori; Hatanaka, Nobuhiro; Okita, Takatoshi; Aono, Shigenori
JAEA-Technology 2012-042, 96 Pages, 2013/02
JAEA-Technology-2012-042.pdf:2.6MB
In January of 1993, plutonium dioxide powder was received from the reprocessing plant "La Hague" of COGEMA in France to Plutonium Fuel Production Facility (PFPF) of JAEA to use as feed powder of MOX fuel for FBR prototype "Monju". Since the plutonium dioxide powder was contained in COGEMA type canisters, the powder had to be rebottled from CCGEMA type canisters to JAEA type canisters which can be handled in the PFPF. Therefore feed powder rebottling equipment and temporary feed storage equipment were developed and installed in the PFPF. Rebottling work with their equipments was started from March of 1993 and completed in March of 2006. This report summarizes operating and maintenance experiences on feed powder rebottling equipment and temporary feed storage equipment. It's important to reflect the operating and maintenance experiences of the rebottling equipment into design of a new rebottling equipment for uranium-plutonium mixed oxide powder.
Kubo, Shinji; Tanaka, Nobuyuki; Noguchi, Hiroki; Iwatsuki, Jin; Onuki, Kaoru; Inagaki, Yoshiyuki
JAEA-Technology 2012-043, 41 Pages, 2013/02
JAEA-Technology-2012-043.pdf:7.74MB
Providing safety measures for workers and external environments are indispensable in R&D activities of the iodine sulfur water-splitting hydrogen production process, since this process uses toxic chemicals as sulfur dioxide, sulfuric acid, iodine and hydriodic acid. One of the R&D subjects is proof of manufacturability of chemical reactors made of practical structural materials and confirmation of the reactors' sound performance in the harsh process conditions. In order to examine the task, test apparatuses of the process are being constructed; the apparatus for a Bunsen reactor has been built and assembled. Capacities of vessels of the apparatus are about 50-150 liter; normal operating pressure will be 0.5 MPa [abs], and that of temperature will be 90 degrees centigrade. Safety measures for the test apparatus, operations, and in abnormal situations were considered prior to the start of the operation. This report summarizes the results of the considerations.
Aihara, Jun; Ueta, Shohei; Ohashi, Hirofumi; Tachibana, Yukio
JAEA-Technology 2012-044, 9 Pages, 2013/02
JAEA-Technology-2012-044.pdf:1.22MB
Evaluation of integrity of coated fuel particles of GTHTR300 has already been carried out. On the other hand, new knowledge on pressure vessel failure, one of the causes of failure of coated fuel particles under irradiation, was obtained by preliminary irradiation experiment of coated fuel particles for HTTR up to official burnup of 7% FIMA. Then in this report, extrapolative evaluation of volume averaged pressure vessel failure probability was carried out based on method which is already published. Considering evaluated pressure vessel failure probability, in addition to corrosion behavior of SiC layer and fuel kernel migration of GTHTR300 coated fuel particles, already analyzed in past paper, volume averaged failure probability of coated fuel particles of GTHTR300 at refueling is small in view of public dose by accident, if initial failure probabilities of coated fuel particles are same as those of HTTR first loading fuel.
Tsuji, Tomoyuki; Kameo, Yutaka; Sakai, Akihiro; Hoshi, Akiko; Takahashi, Kuniaki
JAEA-Technology 2012-045, 37 Pages, 2013/02
JAEA-Technology-2012-045.pdf:2.43MB
It is necessary to establish practical evaluation methods to determine radioactivity concentrations of the important nuclides for safety assessment on disposal of radioactive wastes in order to dispose of low-level radioactive wastes generated from various nuclear facilities in JAEA. In this report, the practical evaluation methods such as the scaling factor method for JPDR facilities have been studied for disposal of the low-level radioactive wastes generated from nuclear reactor facilities in JAEA.
Oyamatsu, Yasuko*; Someya, Hiroyuki
JAEA-Technology 2012-046, 80 Pages, 2013/02
JAEA-Technology-2012-046.pdf:5.43MB
In the experimental fast reactor Joyo, there were many tests using the irradiation rigs that it was possible to be set irradiation conditions for each compartment independently. In case of no alternative fuel element to irradiate after unloading the irradiated compartments, the irradiation test was restarted with the dummy compartment which the fuel elements was not mounted. If the material specimens are mounted in this space, it is possible to realize effective utilization of the irradiation space. For these reasons, the irradiation rig (hybrid rig) consolidated with fuel elements and material specimens are developed. Fuel elements and material specimens differ greatly with heat generation, so that the point for developing of hybrid rig is being able to distribute appropriately the coolant flow which satisfies irradiation conditions. The following is described by this report. (1) It was confirmed that the flow distribution of loading the same irradiation rig with the compartment from which a flow demand differs could be satisfied. (2) It was confirmed that temperature setting capability equivalent to the former was securable. (3) By standardizing the coolant entrance structure of the compartment lower part, the prospect which can perform easily recombination of the compartment from which a kind differs between irradiation rigs was acquired.
Ashida, Takashi; Miyamoto, Kazuyuki; Okazaki, Yoshihiro*; Ito, Hideaki
JAEA-Technology 2012-047, 106 Pages, 2013/06
JAEA-Technology-2012-047.pdf:11.09MBJAEA-Technology-2012-047-appendix(CD-ROM).zip:15.46MB
In the experimental fast reactor Joyo, failure of disconnecting the irradiation test subassembly MARICO-2 (Material Testing Irradiation Rig with Temperature Control) was occurred and top of the MARICO-2 test subassembly was bent onto the in-vessel storage rack. As a result of this incident, the operation area of rotating plug for the fuel exchange in Joyo is limited. The replacement of the damaged UCS and retrieving the bent MARICO-2 are required to Joyo restoration. This report describes about investigations and some tests to know the status of MARICO-2 test subassembly and the optimized detail design of retrieval device reflecting those results.
Ohara, Yoshiyuki; Naganuma, Masaki; Nohiro, Tetsuya*; Yoshida, Kimikazu*; Makita, Akinori*; Sakate, Mitsuo*; Irisawa, Takumi*; Murashita, Tatsuya*
JAEA-Technology 2012-048, 39 Pages, 2013/03
JAEA-Technology-2012-048.pdf:5.1MB
In Japan Atomic Energy Agency Ningyo-Toge Environmental Engineering Center, exploration for uranium and technical development of uranium refining, conversion and enrichment which are the front end of a nuclear fuel cycle have been performed since 1955. By these research and development, about 15000 radioactive waste (200 liter drum) has occurred by now. The analytical and measurement technique of the amount of uranium which are included in radioactive waste drum were very an inexperienced in those days. Therefore, measurement strict till 2002 was not able to be started. Such a situation as this, we introduced "Q2 low-level-waste drum measuring system" which is a bulk measuring method of the passive ray using a NaI scintillation detector in 2002. As a result, the total amount of uranium in a waste drum was estimated as about 20 tons.
Yamawaki, Hiroyuki; Torikai, Kazuyoshi; Arimoto, Yosuke*
JAEA-Technology 2012-049, 64 Pages, 2013/03
JAEA-Technology-2012-049.pdf:8.28MB
An agreement was concluded among MEXT (Ministry of Education, Culture, Sports, Science and Technology), Tottori Prefecture, Misasa Town and JAEA (Japan Atomic Energy Agency) on May 31st, 2006, aiming at resolving the problem due to the waste soil deposited at JAEA's Katamo Waste Soil Yards. Based on the agreement, a plant was constructed in the land JAEA rented form the Misasa Town to manufacture bricks from the micture of the waste soil and additives such as cement. The plant manufactured about 1.45 million bricks during the period of operation between April 28th, 2008, and December 13th, 2010. This report summarizes the outline of the brick manufacturing plant, the results of trial and pilot operations and the performance of full-scale operation.