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Arai, Masatoshi; Toyama, Takami*; Kajimoto, Ryoichi
JAEA-Review 2007-001, 249 Pages, 2007/03
JAEA-Review-2007-001.pdf:71.25MB
A workshop entitled "Anomalous Electronic States and Physical Properties in High-Temperature Superconductors" was held on November 7-8, 2006 at Institute for Materials Research, Tohoku University. In the workshop, leading scientists in the field of High-
superconductivity, both experimentalists and theorists, gathered in a hall to report the recent progress of the study, clarify the problems to be solved, and discuss the future prospects. The workshop was jointly organized by Specially Promoted Research of MEXT, "Development of the 4D Spaces Access Neutron Spectrometer and Elucidation of the Mechanism of Oxide High- Superconductivity" (repr. by M. Arai, JAEA) and by the Inter-university Cooperative Research Program of the Institute for Materials Research, Tohoku University, "Anomalous Electronic States and Physical Properties in High-Temperature Superconductors" (repr. by T. Toyama, Kyoto University). This report includes abstracts and materials of the presentations in the workshop.
Yamamoto, Junta
JAEA-Review 2007-002, 138 Pages, 2007/03
JAEA-Review-2007-002.pdf:14.75MB
The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2006 until September, 2006.
Bamba, Tsunetaka
JAEA-Review 2007-003, 46 Pages, 2007/03
JAEA-Review-2007-003.pdf:2.84MB
In the case of the direct disposal of spent nuclear fuel in a deep geological formation, the release of radionuclides from the spent fuel matrix will be controlled by the rate at which uranium is released into the environment. In this paper the mechanism and kinetics of nuclear fuel corrosion under waste disposal conditions are reviewed, and the many published observations on fuel corrosion are discussed. The influence of a wide range of parameters on fuel corrosion are discussed: These include the pre-oxidation of the fuel, pH, O
concentration, carbonate concentration, temperature, groundwater species, the effect of water radiolysis, and the formation of corrosion product deposits. The relevance of the data recorded on unirradiated UO to the interpretation of spent fuel behavior is included.
Quantum Beam Science Directorate; Advanced Science Research Center
JAEA-Review 2007-004, 163 Pages, 2007/03
JAEA-Review-2007-004.pdf:14.54MB
This issue summarizes research progress in neutron science at Japan Atomic Energy Agency (JAEA) by utilizing the research reactor JRR-3 during the period between April 1, 2005 and March 31, 2006. This report contains highlights in research by 13 neutron research groups at JAEA and 89 summary articles.
Nakashio, Nobuyuki; Kameo, Yutaka; Hoshi, Akiko; Nakashima, Mikio
JAEA-Review 2007-005, 35 Pages, 2007/02
JAEA-Review-2007-005.pdf:2.28MB
The Nuclear Science Research Institute of the Japan Atomic Energy Agency constructed the Advanced Volume Reduction Facilities (AVRF) in February 2003 for treatment of low-level radioactive miscellaneous solid waste (LLW). The waste volume reduction is carried out by a high-compaction process or melting processes in the AVRF. In advance of operating the melting process in the AVRF, melting tests of simulated LLW with RI tracers (
Co, 
Cs and 
Eu) have been conducted by using the plasma melter in pilot scale. Viscosity of molten waste, chemical composition and physical properties of solidified products and distribution of the tracers in each product were investigated in various melting conditions. In this review, experimental results of the melting tests were discussed in order to contribute to actual treatment of LLW in the AVRF.
Sampei, Shinichi
JAEA-Review 2007-006, 89 Pages, 2007/03
JAEA-Review-2007-006.pdf:5.62MB
This is an annual report in a fiscal year of 2006 that describes activities of the Reactor Fuel Examination Facility (RFEF), the Waste Safety Testing Facility (WASTEF) and the Research Hot Laboratory (RHL) in the Department of Hot laboratories and facilities. In RFEF, destructive and nondestructive examinations of BWR fuel rods and assembly component were carried out as PIEs for a fuel assembly irradiated for 5 cycles in the Fukushima-2 Nuclear Power Station Unit-1. In WASTEF, SSRT and UCLT for detecting the susceptibility to IASCC of nuclear reactor structural materials in high-temperature water were performed. In RHL, instrument withdrawals and decontamination were performed to SE cells and lead cells that would be dismantled in 2006 or later according to the decommissioning plan. After the integration of JAERI and JNC, operations and utilizations of No.1 Plutonium Laboratory and Uranium Enrichment Laboratory, etc. have been started.
Kobayashi, Yasushi; Yamada, Tsutomu; Nakayama, Masashi; Matsui, Hiroya; Matsuda, Takeshi*; Konishi, Kazuhiro*; Iriya, Keishiro*; Noda, Masaru*
JAEA-Review 2007-007, 42 Pages, 2007/03
JAEA-Review-2007-007.pdf:3.12MB
Shotcrete and lining will be used for safety under construction and operational period in HLW repository. Concrete is a kind of composite material which is constituted by aggregate, cement and other mixture. Low alkaline cement has been developed from the viewpoint of long term stability of the barrier systems which would be influenced by high alkaline arising from cement material. HFSC is one of a low alkaline cement. It has been developed in Japan Atomic Energy Agency. JAEA are now implementing the construction of the under ground research laboratory (URL) at Horonobe. This report shows the in situ test plan for shotcrete using HFSC at Horonobe URL with identifying requirements for cement materials to be used in HLW repository, and also reviews major literatures of low alkaline cement. This in situ test plan is aiming to assess the performance of HFSC shotcrete in terms of mechanics, workability, durability, and so on.
Yamada, Tsutomu; Hiramoto, Masayuki; Kobayashi, Yasushi; Yui, Mikazu; Sato, Haruo; Matsui, Hiroya
JAEA-Review 2007-008, 44 Pages, 2007/03
JAEA-Review-2007-008.pdf:4.76MB
Disturbances caused by construction and operation of the ONKALO (the underground rock characterization facility in Olkiluoto) have been studied by POSIVA in Finland. In this study, engineering and stray materials which might influence the long-term system performance were discussed taking account of the results of POSIVA study and materials to used for the construction of the Horonobe URL, and then summarized for the future stage of repository construction.
Otani, Takayuki; Sasa, Narimasa; Shimizu, Futoshi; Suzuki, Yoshio
JAEA-Review 2007-009, 36 Pages, 2007/03
JAEA-Review-2007-009.pdf:2.74MB
Research on simulation engineering for nuclear applications has been performed at Center for Computational Science & e-Systems, Japan Atomic Energy Agency (CCSE/JAEA). We established the committee which does research evaluation and advice as the help of the research and development. This report describes the result of the evaluation of research on simulation engineering performed at CCSE/JAEA in FY2005.
Japan Atomic Energy Agency; Federation of Electric Power Companies of Japan*
JAEA-Review 2007-010, 26 Pages, 2007/03
JAEA-Review-2007-010.pdf:4.0MB
JAEA-Review-2007-010-appendix(CD-ROM).zip:45.44MB
In order to promote the establishment of a regulatory framework and the implementation of TRU waste disposal, the Federation of Electric Power Companies of Japan (FEPC) and the Japan Nuclear Cycle Development Institute (now JAEA) collaborated and published a progress report in Japanese (hereafter TRU-2) in September 2005. The report here is an English version of TRU-2 and has been published to widely inform overseas researchers and engineers of the contents of TRU-2. In this report, the characteristics of TRU waste generated from the nuclear fuel cycle in Japan and its disposal concept are shown. The design of the TRU waste disposal facility was evaluated and safety assessments were carried out to show that safety could be validated by comparing with regulatory guidelines in overseas performance assessment reports. Alternative technologies were developed to deal with various geological environments and to improve safety margins in addition to evaluating other disposal concepts. Furthermore, optimisation through co-location disposal of TRU waste and high level radioactive waste was investigated, and an example layout of a co-location disposal concept was evaluated. Based on these evaluation results, future issues and outstanding items on research and development for TRU waste disposal are summarised.
Maekawa, Keisuke; Sawada, Atsushi; Ota, Kunio; Kurikami, Hiroshi; Kunimaru, Takanori; Funaki, Hironori; Hama, Katsuhiro; Takeuchi, Shinji; Amano, Kenji; Saegusa, Hiromitsu; et al.
JAEA-Review 2007-011, 8 Pages, 2007/03
JAEA-Review-2007-011.pdf:0.66MB
In the current programme for research and development on the technical aspects of geological disposal, it is of significance to establish techniques for evaluating solute transport with a direct link to surface-based investigations through the processes of data interpretation, modelling and parameter designation within the immediate five years following the H17 Project. This report presents a basic approach to promoting multidisciplinary research activities involving field investigations and relevant solute transport analysis.
Tago, Itaru; Ono, Takayuki; Kawasaki, Satoru
JAEA-Review 2007-012, 13 Pages, 2007/03
JAEA-Review-2007-012.pdf:0.66MB
The Ningyo-toge Environmental Engineering Center of the Japan Atomic Energy Agency performs the environmental monitoring around the Ningyo-toge and the waste rock sites according to the agreements with local governments, Okayama and Tottori prefectures. The prefectural committees on the environmental monitoring evaluate the monitoring data annually. This report summarized the results of the environmental monitoring mentioned above in the fiscal year 2004. The results show that the levels of the radiation and the radioactive concentrations in the environmental samples were within natural variations, and that the waste rock sites have been well maintained. The committees concluded the environmental impacts from the sites were negligible.
Tago, Itaru; Ono, Takayuki; Kawasaki, Satoru
JAEA-Review 2007-013, 13 Pages, 2007/03
JAEA-Review-2007-013.pdf:0.67MB
The Ningyo-toge Environmental Engineering Center of the Japan Atomic Energy Agency performs the environmental monitoring around the Ningyo-toge and the waste rock sites according to the agreements with local governments, Okayama and Tottori prefectures. The prefectural committees on the environmental monitoring evaluate the monitoring data annually. This report summarized the results of the environmental monitoring mentioned above in the fiscal year 2005. The results show that the levels of the radiation and the radioactive concentrations in the environmental samples were within natural variations, and that the waste rock sites have been well maintained. The committees concluded the environmental impacts from the sites were negligible.
Tago, Itaru; Ono, Takayuki; Kawasaki, Satoru
JAEA-Review 2007-014, 40 Pages, 2007/03
JAEA-Review-2007-014.pdf:1.54MB
The Ningyo-toge Environmental Engineering Center of the Japan Atomic Energy Agency performs the environmental monitoring around the Ningyo-toge and the waste rock sites according to the agreements with local governments, Okayama and Tottori prefectures. Environmental monitoring of plutonium has been also performed around the Ningyo-toge regarding the practical application study on the reprocessed uranium conversion, which was carried out from 1994 to 1999 at the Ningyo-toge. The prefectural committees on the environmental monitoring evaluate the monitoring data annually. This report summarized the results of the environmental monitoring mentioned above in the fiscal year 2005. The results show that the levels of the radiation and the radioactive concentrations in the environmental samples were within natural variations, and that the waste rock sites have been well maintained. The committees concluded the environmental impacts from the sites were negligible.
Center for Computational Science & e-Systems
JAEA-Review 2007-015, 50 Pages, 2007/03
JAEA-Review-2007-015.pdf:6.32MB
This report provides an overview of research and development activities in Center for Computational Science and Engineering (CCSE), JAERI in the former half of the fiscal year 2005 (April 1, 2005 - Sep. 30, 2006) and those in Center for Computational Science & e-Systems (CCSE), JAEA, in the latter half of the fiscal year 2005(Oct 1, 2005 - March 31, 2006). One of the main topics of CCSE in the fiscal year 2005 was verification by using structure analysis for real plant executable on the Grid environment. Our research paper on this issue received "honorable mention" in Supercomputing 2005. Other topics studied intensively in materials science and bioinformatics were as follows; a first-principle calculation to examine embrittlement effects of the grain boundaries for more than 10 impurity elements, a semi-first principle simulation to explore non-equilibrium superconducting dynamics after the neutron capture in neutron detector device using MgB2 superconductor, a molecular dynamics simulation of DNA replication/repair protein with DNA to analyze its atomic detail for realizing its function, and so on. The remarkable issue in these research activities was that large-scale simulation technique developments on the Earth Simulator was selected as "Gordon Bell Prize finalist" in the conference "Supercomputing (SC05)".
Sasaki, Yasuo
JAEA-Review 2007-016, 15 Pages, 2007/03
JAEA-Review-2007-016.pdf:0.88MB
Japan Atomic Energy Agency (JAEA) has more than one thousand of short-term visitors to ENTRY and QUALITY of Tokai Research and Development Center in every year to make visitors understand the result of research and development for geological isolation of high level radioactive waste (HLW). The important opinions and questions about geological isolation of HLW from visitors were integrated. Based on them, the information of understanding activities and future needs for research and development of geological isolation were documented.
Department of HTTR
JAEA-Review 2007-017, 78 Pages, 2007/03
JAEA-Review-2007-017.pdf:8.16MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan, which is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal 2005 year, periodical inspection and overhaul of reactivity control system were conducted, and safety demonstration tests were promoted. This report summarizes activities and test results on HTTR operation and maintenance as well as safety demonstration tests and several Research and Developments, which were carried out in the fiscal year of 2005.
Research Reactor Utilization Section
JAEA-Review 2007-018, 174 Pages, 2007/03
JAEA-Review-2007-018.pdf:15.26MB
In the fiscal year 2005, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 37 cycles (daily operation : 137 days). JRR-3 is used for the purposes below; (1) Experimental studies such as neutron scattering, prompt 
-ray analyses, neutron radiography (2) Irradiation for activation analyses, radioisotope (RI) productions, fission tracks (3) Irradiation test of reactor materials etc. JRR-4 is used for the purposes below; (1) Medical irradiation (Boron Neutron Capture Therapy : BNCT) (2) Prompt -ray analyses (3) Sensitivity measurement of radiation detectors (4) Experiment in the nuclear reactor training (5) Practice of Reactor operation (6) Irradiation for activation analyses, RI productions, fission tracks etc. The volume contains 100 activity reports, which are categorized into the fields of neutron scattering (9 subcategories), neutron radiography, neutron activation analyses, RI productions, prompt -ray analyses, and others submitted by the users in JAEA and from other organizations.
Tanaka, Hidetaka; Nagao, Yoshiharu; Osawa, Kenji; Sato, Masashi
JAEA-Review 2007-019, 37 Pages, 2007/03
JAEA-Review-2007-019.pdf:3.2MB
Irradiation tests are increasing in advanced irradiation research for accurate prediction control and evaluation of irradiation parameter such as neutron fluence, etc. by using JMTR. Irradiation capsule internals are therefore structurally complicated recently. This report described the procedure of non destructive tests such as radiographic test, penetrant test, ultrasonic test, etc. for inspection of irradiation capsules in JMTR, and the result of examination of confirmation procedure for internal parts of irradiation capsules.
Intellectual Resources Department
JAEA-Review 2007-020, 265 Pages, 2007/03
JAEA-Review-2007-020.pdf:39.71MB
The workshop on "Nuclear Knowledge Management (NKM): Present Status and Perspective" was held at the Tokyo Institute of Technology (supported by the Japan Atomic Energy Agency), Tokyo, Japan on the 14th and 15th of December 2006. The purpose of the workshop is to introduce NKM activities inside and outside Japan so that concerned parties/professionals could share related information and enhance awareness of the issues on NKM. Participants from various sectors, such as authorities, industry, universities/research institutes, etc, made presentations. Issues on NKM are recognized and discussed. The workshop consisted of 18 oral lectures and panel discussion. The 55 participants attended the workshop. Under permission of the Tokyo Institute of Technology which is the sponsor of the workshop, this report compiles these lecture's presentation materials which got permission of a lecturer and synopses which were submitted after the workshop.
Yamamoto, Kazuya
JAEA-Review 2007-021, 57 Pages, 2007/05
JAEA-Review-2007-021.pdf:9.99MB
The International Atomic Energy Agency (IAEA) carried out a large-scale international emergency response exercise in 2005 under the designated name of ConvEx-3(2005), at Romania. This review report summarizes a study about ConvEx-3(2005) based on several related open literature. The study on the preparation, conduct and evaluation of ConvEx-3(2005) exercise is expected to provide very useful knowledge for development of drills and educational programs conducted by Nuclear Emergency Assistance and Training Center (NEAT). Especially, study on the exercise evaluations is instrumental in improving evaluations of drills planned by the national government and local governments. The lessons learned from this study of ConvEx-3(2005) are summarized in four chapters; methodology of exercises and educational programs, exercise evaluation process, amendments/verification of the emergency response plan of NEAT, and technical issues of systems for emergency response and assistance of NEAT relevant to interface for international emergency communication.
Nuclear Science Research Institute
JAEA-Review 2007-022, 101 Pages, 2007/04
JAEA-Review-2007-022-01.pdf:50.38MBJAEA-Review-2007-022-02.pdf:31.22MB
Japan Atomic Energy Agency (JAEA) was inaugurated on October 1st, 2005. Works for the operation and maintenance of various research facilities as well as safety management, radiation protection, and radioactive wastes management, which have been undertaken by departments in Tokai Research Establishment of Japan Atomic Energy Research Institute (JAERI), were inherited by newly established departments of Nuclear Science Research Institute (NSRI). The NSRI is composed of Planning and Coordination Office and seven departments such as Department of Operational Safety Administration, Department of Radiation Protection, Department of Research Reactor and Tandem Accelerator, Department of Hot Laboratories and Facilities, Department of Criticality and Fuel Cycle Research Facilities, Department of Decommissioning and Waste Management, and Engineering Services Department. This annual report of JFY 2005 summarizes the activities of NSRI and is expected to be referred to and utilized by R&D departments and project promotion sectors at NSRI site for the enhancement of their own research and management activities to attain their goals according to "Middle-term Plan" successfully and effectively.
Tachibana, Yukio; Hino, Ryutaro; Yu, S.*
JAEA-Review 2007-023, 42 Pages, 2007/06
JAEA-Review-2007-023.pdf:45.93MB
The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been growing because the high temperature heat produced by the reactor can be utilized not only for efficient power generation but also for broad process heat applications, especially for thermo-chemical hydrogen production to fuel a prospective hydrogen economy in future. Presently only two HTGR reactors are operational in the world, including the HTTR (High Temperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and the HTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. JAEA and INET have cooperated since 1986 in the field of HTGR development, particularly on the HTTR and HTR-10 projects. This report describes the cooperation with emphasis on HTGR operation and maintenance techniques between JAEA and INET and outlines cooperation activities in 2006.
Ikeda, Kiyoshi; Habara, Tadashi; Ishikawa, Masashi; Itabashi, Keizo; Yonezawa, Minoru
JAEA-Review 2007-024, 51 Pages, 2007/03
JAEA-Review-2007-024.pdf:2.57MB
The Japan Atomic Energy Research Institute (JAERI) Library had contributed 312 papers through the library activities in half-century. We made the bibliography of these papers as well as categorized them into "general", "library functions", "management and promotion of research results" and "international exchange of information" and explained them under the four categories. A subject index, an author index of these papers and chronology of JAERI library activities were also compiled for reference.
Sono, Hiroki
JAEA-Review 2007-025, 141 Pages, 2007/06
JAEA-Review-2007-025.pdf:2.88MB
A new technique for effect assessment of radiation incidents was required for effective implementation of emergency measures in the early phase of unforeseen circumstances such as criticality accidents. In the present study, a new dosimetry technique for neutron and gamma-ray absorbed doses in human bodies was developed using two kinds of tissue-equivalent dosimeters: an alanine dosimeter and a lithium tetra borate dosimeter. The applications of this technique to personal dosimetry under criticality accident conditions and to retrospective assessment of criticality accident situations were also studied. The experiments and analyses using the Transient Experiment Critical Facility (TRACY) demonstrated that the dosimetry technique and its applications could estimate the magnitude and radiological consequence of criticality accidents precisely enough to plan emergency measures.
Itabashi, Keizo
JAEA-Review 2007-026, 264 Pages, 2007/07
JAEA-Review-2007-026-01.pdf:12.23MBJAEA-Review-2007-026-02.pdf:70.83MBJAEA-Review-2007-026-03.pdf:91.41MBJAEA-Review-2007-026-04.pdf:45.06MBJAEA-Review-2007-026-05.pdf:44.9MB
The research and technical reports system of the JAERI was abolished, upon the Japan Atomic Energy Research Institute being abolished on 30th September 2005. Its short history and its retrieval tools are described briefly. In addition, the entire publication list is attached.
Research Cooperation Section
JAEA-Review 2007-027, 105 Pages, 2007/08
JAEA-Review-2007-027.pdf:18.03MB
This report includes a summary of the results of the research on fourteen themes performed by JAEA Postdoctoral Fellows in the fiscal year 2006.
Research Cooperation Section
JAEA-Review 2007-028, 193 Pages, 2007/09
JAEA-Review-2007-028.pdf:16.27MB
This report includes a summary of the results of the research carried out in fiscal year 2006 on 34 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological.
Nuclear Technology and Education Center
JAEA-Review 2007-029, 232 Pages, 2007/09
JAEA-Review-2007-029-01.pdf:32.47MBJAEA-Review-2007-029-02.pdf:43.43MBJAEA-Review-2007-029-03.pdf:45.37MBJAEA-Review-2007-029-04.pdf:32.86MBJAEA-Review-2007-029-05.pdf:34.27MB
In 1999, the Project for Human Resources Development was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. The FNCA 2006 Workshop on HRD Project was held on July 31- August 4, 2006, in China. The Workshop was sponsored by the China Atomic Energy Authority (CAEA) and the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan. The China Atomic Energy Authority(CAEA) and the Japan Atomic Energy Agency (JAEA) acted as the hosts. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. The activities of HRD Project was presented in the Eighth Coordinators Meeting of FNCA held on February 7-9, 2007, in Tokyo, Japan. This report consists of presentation papers and materials at the FNCA 2006 Workshop, a review document of HRD Project for the Coordinators Meeting of FNCA as Outside-Workshop Activity.
Shamoto, Shinichi; Fujii, Yasuhiko
JAEA-Review 2007-030, 196 Pages, 2007/10
JAEA-Review-2007-030.pdf:31.34MB
The 1st workshop of the Cooperative Research Program on Quantum Beam Technology among RIKEN, NIMS, and JAEA entitled "Quantum Complex Phenomena" was held on June 14, 2007 at Center for Computational Science & e-Systems, Japan Atomic Energy Agency. This workshop is aimed to reveal the mechanism of quantum complex phenomena for the developments of next generation functional materials on the basis of the Cooperative Research Program on Quantum Beam Technology among RIKEN, NIMS, and JAEA. This Cooperative Research Program was concluded on December 20, 2006, in order to lead the research and development of Quantum Beam Technology by the cooperation among RIKEN, NIMS, and JAEA. Along this meaning, this workshop is aimed to introduce own research characteristics for mutual understandings and to discuss starting cooperative research activity for intimate research collaborations. This report includes abstracts and materials of the presentations in the workshop.
CsOshita, Hironori; Ozawa, Masaki; Ishikawa, Makoto; Koyama, Shinichi; Akatsuka, Hiroshi*
JAEA-Review 2007-031, 41 Pages, 2007/09
JAEA-Review-2007-031.pdf:3.73MB
Recently establishment of self consistent nuclear fuel cycle has been required with respect to economical efficiency, safety and reduction of the load to the environment. Especially Cs included in spent fuel of nuclear power plants has extremely long half life (3.0
10
y) and its water solubility leads to the anxiety of exudation into ground water in geologic disposal. Recent technology development of laser has come to make it possible in principle to excite a specific isotope and separate it making use of the intrinsic physical and chemical properties of the excited state. This document reports the review of the isotope separation principle and its application to Cs separation.
Yanagisawa, Kazuaki
JAEA-Review 2007-032, 23 Pages, 2007/09
JAEA-Review-2007-032.pdf:8.96MB
From a viewpoint of ex-post evaluation, research papers published from nine resembled nuclear research institutes located in Japan, the U. S. A. Germany and France were compared by a bibliometric method. A research database used was the Energy Citation Database (ECD) owned by USDOE. For institutional comparison, the following results are obtained; (1)ECD shows that a total number of research papers published during 25 years (1978-2002) was of the order of the ORNL (34,149 papers)
SNLANLBNLIdaho (KarlsruheJAERIJeulichCadarache). Where, INIS shows it as ORNLJAERI. (2)ECD founds that research papers at a five-year period varied those numbers. At past (10), thus 1988-1992, paper reduction occurred sharply at most US-institutes.
Yanagisawa, Kazuaki; Nagasawa, Naotsugu; Sasagawa, Sumiko*; Nakano, Koji*
JAEA-Review 2007-033, 171 Pages, 2007/09
JAEA-Review-2007-033-01.pdf:32.89MBJAEA-Review-2007-033-02.pdf:29.9MBJAEA-Review-2007-033-03.pdf:27.2MBJAEA-Review-2007-033-04.pdf:12.21MB
The Fujioka Technical High School applied to the Science Partnership Project (SPP-2006) and asked an intellectual linkage with Japan Atomic Energy Agency (JAEA) and Institute for Environmental Sciences. Adding to normal lectures, the authors made several educational evaluations. For example, a change of student's interests through lectures on nuclear is evaluated. Direct comparison of intellectual ability between the students and 5 specialists are also made. Resultantly, if one teaches correctly the basic concept of nuclear energy and radiation application as learning inputs, an understanding ability of student increased 3 times than his previous background level. A comprehensive faculty of the students to the 5 specialists is 1/5 before making lecture but increased markedly to 1/2 after the lecture. A majority of students understand well the reprocessing, reactor accidents and food irradiation but showed poor understanding on the location and name of the commercial nuclear power plant and the basic mechanism of those.
Terunuma, Naohiro; Nagao, Yoshiharu; Yokouchi, Iichiro; Sato, Masashi
JAEA-Review 2007-034, 60 Pages, 2007/10
JAEA-Review-2007-034.pdf:36.36MB
Concentrations of radioactive elements in primary cooling water were measured by regular sampling on reactor operation of the JMTR. The JMTR core was converted to low enriched uranium core at the 108th operation cycle, and the refurbishment of the JMTR has been started after the 165th operation cycle. Measured results of concentrations of -ray release elements, radioactive iodine and tritium in primary cooling water were summarized during 108 - 165th operation cycles.
Yamamoto, Kazuya
JAEA-Review 2007-035, 63 Pages, 2007/10
JAEA-Review-2007-035.pdf:6.6MB
The International Atomic Energy Agency has introduced new concept of precautionary action zone (PAZ) in preparedness and response for nuclear emergency. Open literature based research was made to reveal problems on evacuation planning and the preparedness for nuclear emergencies arising from introduce of PAZ in Japan. The principal issue is implementation of evacuation of precautionary decided area within several hours. Evacuation planning for a nuclear emergency and the methods of advance public education and information in the U.S. are effective for even prompt evacuation to the outside of the EPZ. As concerns evacuation planning in Japan, several important issues to be considered were found, that is, the location and the unique correspondence of the public reception centers, public information of detailed evacuation plan in advance, and necessity of evacuation time estimates.
Division of Fusion Energy Technology
JAEA-Review 2007-036, 98 Pages, 2007/11
JAEA-Review-2007-036.pdf:32.22MB
The Division of Fusion Energy Technology of the Fusion Research and Development Directorate is carrying out cooperating researches with universities, research institutes and industries using five fusion engineering facilities; Caisson Assembly for Tritium Safety Study (CATS), Fusion Neutronics Source (FNS), MeV Test Facility (MTF), JAEA Electron Beam Irradiation System (JEBIS), RF Test Stand (RFTS). In the fiscal year 2006 (from April 1, 2006 to March 31, 2007), 23 activities were carried out as the cooperating researches. This report reviews the results of 7 activities which were completed in the fiscal year 2006.
Nishio, Kazuhisa; Mizuno, Takashi; Oyama, Takuya; Nakama, Shigeo; Saegusa, Hiromitsu; Takeuchi, Ryuji; Amano, Kenji; Tsuruta, Tadahiko; Hama, Katsuhiro; Iyatomi, Yosuke; et al.
JAEA-Review 2007-037, 29 Pages, 2007/12
JAEA-Review-2007-037.pdf:13.06MB
Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is developing a geoscientific research project named Mizunami Underground Research Laboratory (MIU) in crystalline rock environment in order to establish scientific and technological basis for geological disposal of HLW. Geoscientific research at MIU is planned to be carried out in three Phases over a period of 20 years; Surface-based Investigation Phase (Phase 1), Construction Phase (Phase 2) and Operation Phase (Phase 3). Currently, the Project is under the Construction Phase. This document presents the following 2006 fiscal year plan of the Construction Phase based on the MIU Master Plan updated in 2002, (1)Investigation Plan at the MIU Construction Site, (2)Construction Plan at the MIU Construction Site, (3)Research Collaboration Plan.
Nishio, Kazuhisa; Mizuno, Takashi; Oyama, Takuya; Nakama, Shigeo; Saegusa, Hiromitsu; Takeuchi, Ryuji; Amano, Kenji; Tsuruta, Tadahiko; Hama, Katsuhiro; Iyatomi, Yosuke; et al.
JAEA-Review 2007-038, 31 Pages, 2007/12
JAEA-Review-2007-038.pdf:11.5MB
Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is developing a geoscientific research project named Mizunami Underground Research Laboratory (MIU) in crystalline rock environment in order to establish scientific and technological basis for geological disposal of HLW. Geoscientific research at MIU is planned to be carried out in three Phases over a period of 20 years; Surface-based Investigation Phase (Phase 1), Construction Phase (Phase 2) and Operation Phase (Phase 3). Currently, the Project is under the Construction Phase. This document presents the following 2007 fiscal year plan of the Construction Phase based on the MIU Master Plan updated in 2002, (1)Investigation Plan at the MIU Construction Site, (2)Construction Plan at the MIU Construction Site, (3)Research Collaboration Plan.
Editorial Committee of R&D Results
JAEA-Review 2007-039, 60 Pages, 2007/11
JAEA-Review-2007-039.pdf:29.74MB
It is one of important issues for Japan Atomic Energy Agency to take measure against the matters on decommissioning of retired nuclear facilities and management of low-level radioactive waste arising from research activities. Various kinds of technology will be necessary to take measure the matters with rational way by ensuring the safety. The technology development program is therefore under way in Nuclear Cycle Backend Directorate taking account of these matters. The technology development items are selected from the viewpoint of cost reduction; these include the development of computer systems for planning and evaluation of decommissioning programs, rapid and simplified radiation measurement, evaluation of radioactive characteristics of waste and so on. This report describes outline and progress of the technology development program conducted so far by the research and development unit.
Department of Research Reactor and Tandem Accelerator
JAEA-Review 2007-040, 232 Pages, 2007/12
JAEA-Review-2007-040.pdf:6.9MB
The Department of Research Reactors and Tandem Accelerator is charge of the operation, utilization and technical development of JRR-3, JRR-4, NSRR and Tandem Accelerator. This review is the publishing report of working results achieved in Japanese Fiscal Year 2006.
Takeishi, Minoru; Miyagawa, Naoto; Nakano, Masanao; Mizutani, Tomoko; Kono, Takahiko; Hiyama, Yoshinori*; Fujii, Jun*; Kikuchi, Masaaki*; Sagawa, Fumiaki*; Otani, Kazunori*
JAEA-Review 2007-041, 130 Pages, 2007/12
JAEA-Review-2007-041.pdf:25.46MB
Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear reguratory acts, and the local agreement concerning with security and environment conservation around nuclear facilities, the water pollution control law, and byelaw of Ibaraki prefecture), this report describes the effluent control results of low level liquid waste discharged from the JAEA's Nuclear Fuel Cycle Engineering Laboratories in the fiscal year 2006, from 1st April 2006 to 31st March 2007. In this period, the concentrations and the quantities of the discharged radioactive materials from the reprocessing plant, the plutonium fuel fabrication facilities, and the other facilities were much lower than the authorized limits of the above regulations.
Yamaguchi, Takenori
JAEA-Review 2007-042, 161 Pages, 2007/12
JAEA-Review-2007-042.pdf:35.05MB
This annual report describes the activities of Radiation Protection Sector in Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute and Operation Safety Administration Section in Aomori research and Development Center in the fiscal year 2006. The report covers environmental monitoring around the facilities, radiation protection of workplace and workers, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection technologies, which were performed at the Radiation Protection Sector.
Watanabe, Norio
JAEA-Review 2007-043, 132 Pages, 2007/12
JAEA-Review-2007-043.pdf:5.28MB
Since the beginning of 1980's, in the United States, there have been many reports involving setpoint drift of the safety or safety/relief valves. The United States Nuclear Regulatory Commission (NRC) has issued the generic communications on this issue and the industry has made their efforts to identify the causes and to take corrective actions. However, the NRC staff found that from 2001 through August 2006, over 70 licensee event reports (LERs) involved instances where safety or safety/relief valves failed to meet the allowed lift setpoint tolerance and issued the Information Notice 2006-24 in 2006 to alert licensees of operating experience insights associated with the safety and safety/relief valves exceeding the lift setpoint tolerance. This report provides the description on the historical NRC's responses to safety and safety/relief valve issues including setpoint drift and analyzes the trends of the ninety-four events, reported as LERs, involving setpoint drift at U. S. nuclear power plants during the years from 2000 to 2006.
Takeishi, Minoru; Miyagawa, Naoto; Nakano, Masanao; Takeyasu, Masanori; Isozaki, Hisaaki; Isozaki, Tokuju; Morisawa, Masato; Fujita, Hiroki; Kokubun, Yuji; Kato, Chiaki; et al.
JAEA-Review 2007-044, 155 Pages, 2008/02
JAEA-Review-2007-044.pdf:2.58MBJAEA-Review-2007-044(errata).pdf:0.13MB
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of JAEA, Chapter 4; Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged to the atmosphere and the sea during April 2006 to March 2007. Appendices present comprehensive information, such as monitoring program, monitoring methods, monitoring results and its trends, meteorological data and discharged radioactive wastes.
Nakatsuka, Noboru; Nohara, Tsuyoshi; Umeda, Koji; Sasao, Eiji; Yasue, Kenichi
JAEA-Review 2007-045, 19 Pages, 2008/01
JAEA-Review-2007-045.pdf:2.97MB
The Japanese islands are located in the tectonically active Circum-Pacific Mobile Belt. As a result, Japan has a high frequency of earthquakes and eruptions. Special consideration is given to the long-term stability of the geological environment. Development of research/prediction technologies for geotectonic events has been carried out to evaluate the long-term stability of the geological environment in Japan. During fiscal year 2007, development of the research/prediction techniques about the following items will be carried out. Concerning active fault and seismic activity, case study for research of an activity history and distribution of an active fault (movement, extension, a development process of a deformation zone) will be carried out. For volcanological and geothermal studies, we are planning to provide an integrated approach for detecting crustal magma and/or geothermal fluid in deep underground using geophysical and geochemical data, and models assessing the likelihood of future volcanism and its influence on geological environment. Concerning uplift, denudation, climatic change and sea-level change, development of techniques that researches paleo-topography and paleo-environment and that simulates of landforms will be carried out. In addition, maintenance of development of analytical methods to perform the data acquisition that is necessary for these studies will be carried out.
Department of Research Reactor and Tandem Accelerator
JAEA-Review 2007-046, 149 Pages, 2008/01
JAEA-Review-2007-046.pdf:8.85MB
This annual report describes a summary of each research activity, which has been carried out using the JAEA-Tokai tandem accelerator with the energy booster from April 1, 2006 to March 31, 2007. Approximately, the fifty summary reports were categorized into seven research/development fields, i.e., (1)accelerator operation and development, (2)nuclear structure, (3)nuclear reaction, (4)nuclear chemistry, (5)nuclear theory, (6)atomic physics and solid state physics, and (7)radiation effects in materials, in addition, lists of publications, personnel and cooperative researches with universities are contained.
Nakatsuka, Noboru; Nohara, Tsuyoshi; Umeda, Koji; Sasao, Eiji; Saito, Tatsuo; Yasue, Kenichi
JAEA-Review 2007-047, 19 Pages, 2008/01
JAEA-Review-2007-047.pdf:2.94MB
The Japanese islands are located in the tectonically active Circum-Pacific Mobile Belt. As a result, Japan has a high frequency of earthquakes and eruptions. Special consideration is given to the long-term stability of the geological environment, taking into account volcanism, faulting, uplift, denudation, climatic change and sea-level change in Japan. Development of research/prediction technologies for geotectonic events has been carried out to evaluate the long-term stability of the geological environment in Japan. During fiscal year 2006, to confirm existence of the phenomena that have a influence on geological disposal system (e.g. active fault or magma) and to confirm that there was not the trace that the phenomena occurred in the past and to predict/evaluate possibility of the phenomena, development of the research/prediction techniques will be carried out. Concerning active fault and seismic activity, information maintenance for research of an activity history and distribution of an active fault (movement, extension, development process of a deformation zone) will be carried out. For volcanological and geothermal studies, we are planning to examine a technique for detecting crustal magma and/or geothermal fluid in deep underground using geophysical and geochemical data, and models assessing the likelihood of future volcanism and its influence on geological environment. Concerning uplift, denudation, climatic change and sea-level change, making of concept model for landform development will be carried out.
Hayashi, Naomi
JAEA-Review 2007-048, 182 Pages, 2008/01
JAEA-Review-2007-048.pdf:6.17MB
The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since October, 2006 until March, 2007.
Ikezoe, Hiroshi
JAEA-Review 2007-049, 44 Pages, 2008/02
JAEA-Review-2007-049.pdf:6.09MB
This is a report on the 8 research projects conducted through the JAEA's Reimei Research Program for the fiscal year of 2006. The results of the projects are to be published to assist the promotion of the basic research in nuclear science.
Umeda, Koji; Oi, Takao; Osawa, Hideaki; Oyama, Takuya; Oda, Chie; Kamei, Gento; Kuji, Masayoshi*; Kurosawa, Hideki; Kobayashi, Yasushi; Sasaki, Yasuo; et al.
JAEA-Review 2007-050, 82 Pages, 2007/12
JAEA-Review-2007-050.pdf:28.56MB
This report shows the annual report which shows the summarized results and topic outline of each project on geological disposal technology in the fiscal year of 2006.
Radiation Protection Department
JAEA-Review 2007-051, 142 Pages, 2008/02
JAEA-Review-2007-051.pdf:3.45MB
This annual report summarizes the various activities on radiation control at the nuclear fuel cycle facilities in Nuclear Fuel Cycle Engineering Laboratories, which were undertaken by the Radiation Protection Department in fiscal 2006.
Tago, Itaru; Ono, Takayuki; Ishimori, Yuu; Kawasaki, Satoru
JAEA-Review 2007-052, 13 Pages, 2008/03
JAEA-Review-2007-052.pdf:1.45MB
The Ningyo-toge Environmental Engineering Center of the Japan Atomic Energy Agency performs the environmental monitoring around the Ningyo-toge and the waste rock sites according to the agreements with local governments, Okayama and Tottori prefectures. The prefectural committees on the environmental monitoring evaluate the monitoring data annually. This report summarized the results of the environmental monitoring in Tottori prefecture in the fiscal year 2006. The results show that the levels of the radiation and the radioactive concentrations in the environmental samples were within natural variations, and the waste rock sites have been well maintained. The committees concluded the environmental impacts from the sites were negligible.
Tago, Itaru; Ono, Takayuki; Ishimori, Yuu; Kawasaki, Satoru
JAEA-Review 2007-053, 43 Pages, 2008/03
JAEA-Review-2007-053.pdf:2.26MB
The Ningyo-toge Environmental Engineering Center of the Japan Atomic Energy Agency (JAEA Ningyo-toge) performs the environmental monitoring around the Ningyo-toge and the waste rock sites according to the agreements with local governments, Okayama and Tottori prefectures. Environmental monitoring of plutonium has been also performed around the Ningyo-toge regarding the practical application study on the reprocessed uranium conversion, which was carried out from 1994 to 1999 at the Ningyo-toge. Each prefectural committee on the environmental monitoring evaluate the monitoring data annually. This report summarized the results of the environmental monitoring in Okayama prefecture in the fiscal year 2006. The results show that the levels of the radiation and the radioactive concentrations in the environment were within natural variations, and the committee concluded the environmental impacts from the sites were negligible.
Center for Computational Science & e-Systems
JAEA-Review 2007-054, 46 Pages, 2008/02
JAEA-Review-2007-054.pdf:3.56MB
Research on simulation engineering for nuclear applications, based on "the plan for meeting the mid-term goal of the Japan Atomic Energy Agency", has been performed at Center for Computational Science & e-Systems, Japan Atomic Energy Agency (CCSE/JAEA). We established the committee consisting outside experts and authorities which does research evaluation and advices for the assistance of the research and development. This report summarizes the result of the evaluation by the committee on the research on simulation engineering performed at CCSE/JAEA in FY2006.
Information Technology Systems' Management and Operating Office
JAEA-Review 2007-055, 188 Pages, 2008/02
JAEA-Review-2007-055.pdf:25.64MB
Center for Promotion of Computational Science and Engineering (CCSE) of Japan Atomic Energy Agency (JAEA) installed large computer systems including super-computers in order to support research and development activities in JAEA. CCSE operates and manages the computer system and network system. This report presents usage records of the JAEA computer system and the big users' research and development activities by using the computer system in FY2006 (April 1, 2006 - March 31, 2007).
Department of Decommissioning and Waste Management
JAEA-Review 2007-056, 179 Pages, 2008/03
JAEA-Review-2007-056.pdf:26.77MB
This reports described activities of Department of Decommissioning and Waste Management (DDWM) in Nuclear Science Research Institute (NSRI) from October 1, 2006 to March 31, 2007. The report covers outline of facilities, treatment and management of radioactive wastes, decommissioning activities, and related R&D activities. In FY2006 radioactive wastes generated mainly from R&D activities in NSRI were treated safely. They were 393m
of combustible solid wastes, 152m of noncombustible solid wastes and 493m of liquid wastes. 1,596 waste packages (in 200L-drum equivalent) were generated and totally 134,466 drums were stored as of the end of FY2006. Decommissioning activities were carried out for the JAEA's Reprocessing Test Facility and the Ceramic Fuel Laboratory. As for the R&D activities, studies were conducted on radiochemical waste analyses, clearance, decommissioning technologies and waste management.
Inaba, Yoshitomo
JAEA-Review 2007-057, 176 Pages, 2008/03
JAEA-Review-2007-057.pdf:11.1MB
Aiming at the realization of the nuclear heat application system with a High Temperature Gas-cooled Reactor (HTGR), research and development on the whole evaluation of the system, the connection technology between the HTGR and a chemical plant such as the safety evaluation against the fire and explosion and the control technology, and the vessel cooling system of the HTGR were carried out. In the whole evaluation of the nuclear heat application system, an ammonia production system using nuclear heat was examined, and the technical subjects caused by the connection of the chemical plant to the HTGR were distilled. After distilling the subjects, the safety evaluation method against the fire and explosion to the reactor, the mitigation technology of thermal disturbance to the reactor, and the reactor core cooling by the vessel cooling system were discussed. These subjects are very important in terms of safety. About the fire and explosion, the safety evaluation method was established by developing the process and the numerical analysis code system. About the mitigation technology of the thermal disturbance, it was demonstrated that the steam generator, which was installed at the downstream of the chemical reactor in the chemical plant, could mitigate the thermal disturbance to the reactor. In order to enhance the safety of the reactor in accidents, the heat transfer characteristic of the passive indirect core cooling system was investigated, and the heat transfer equation considering both thermal radiation and natural convection was developed for the system design. As a result, some technical subjects related to safety in the nuclear heat application system were solved.
Division of Advanced Plasma Research
JAEA-Review 2007-058, 65 Pages, 2008/02
JAEA-Review-2007-058.pdf:31.64MB
Fusion Energy Conference has been held aiming to report and exchange the information concerning the nuclear fusion research every two years since 1961 by IAEA. The conference has authorities most in the field of the fusion research. The 21st Fusion Energy Conference was held at Chengdu in China on October 16th through 21st in 2006, and 800 researchers or more participated in the conference from 50 countries. This report is a summary of the conference that the JAEA researchers who participated in this conference (36 persons in total) have seen presentations of each contributed papers at the conference room and have understood from each point of view. The contents of this report are very comprehensible, because those are written from the viewpoint of each researchers of JAEA. The purpose of this report is to provide the information which is useful for many researchers to understand the latest study results over a wide field of fusion research.
Sampei, Shinichi; Department of Hot Laboratories and Facilities
JAEA-Review 2007-059, 111 Pages, 2008/02
JAEA-Review-2007-059.pdf:33.33MB
This is an annual report in a fiscal year 2006 that describes activities of the RFEF, the WASTEF, the RHL and the other research hot facilities in the Department of Hot laboratories and facilities. In RFEF, destructive examinations of BWR fuel rods and re-assembly were carried out as PIEs for a fuel assembly irradiated for 5 cycles. Mechanical property measurement of high burn-up fuel rods were performed as spent fuel integrity test for long term dry storage. In WASTEF, SSRT and UCLT of in-core materials in pressurized high-temperature water condition, SCC tests for high-performance fuel cladding material and calorific value measurement of pulse irradiated fuel in NSRR were carried out. In RHL, equipment un-installations and decontamination were performed to lead cells. And modification of fuel storage room were started in order to utilize the facility for un-irradiated fuel storage. In addition, management of the other research hot facilities were carried out.
Tanaka, Shigeru
JAEA-Review 2007-060, 243 Pages, 2008/03
JAEA-Review-2007-060.pdf:54.09MB
JAEA Takasaki annual report 2006 describes research and development activities performed from April 1, 2006 to March 31, 2007 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/-ray irradiation facilities (an electron accelerator and three Co -ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: (1) space, nuclear and energy engineering, (2) environmental conservation and resource security, (3) biotechnology and medical application, and (4) advanced materials, analysis and novel technology. This annual report contains 186 reports consisting of 178 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, related press-releases, TV programs, patents, and the type of research collaborations as Appendices.
Yamada, Fumitaka; Sonobe, Hitoshi; Igarashi, Hiroshi
JAEA-Review 2007-061, 67 Pages, 2008/02
JAEA-Review-2007-061.pdf:8.39MB
In JAEA, various systems associated with the collaboration with industries and universities are enacted. These systems have been operated considering the needs of JAEA's program, industry and academia, resultantly contributed, for example, to basic research and the project development. Activities under these systems contain personal exchanges, the publication of the accomplishments and utilization of those, in R&D concerning geological disposal technology of HLW. These activities have progressed in PNC and JNC, through JAEA. The accomplishments from these systems have contributed to the advancement of the national program on the geological disposal of HLW. In this report, the progress of the R&D under these systems was investigated from the beginning of their operation. The contribution to the R&D on geological disposal technology of HLW was also studied. On the basis of these studies, the future utilization of the systems of the collaboration was also discussed.