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JAEA Reports

Progress report on Nuclear Safety Research Center; JFY 2015 - 2017

Nuclear Safety Research Center, Sector of Nuclear Safety Research and Emergency Preparedness

JAEA-Review 2018-022, 201 Pages, 2019/01

JAEA-Review-2018-022.pdf:20.61MB

Nuclear Safety Research Center (NSRC), Sector of Nuclear Safety Research and Emergency Preparedness, Japan Atomic Energy Agency (JAEA) is conducting technical support to nuclear safety regulation and safety research based on the Mid-Long Term Target determined by Japanese government. This report summarizes the research structure of NSRC and the cooperative research activities with domestic and international organizations as well as the nuclear safety research activities and results in the period from JFY 2015 to 2017 on the nine research fields in NSRC; (1) severe accident analysis, (2) radiation risk analysis, (3) safety of nuclear fuels in light water reactors (LWRs), (4) thermohydraulic behavior under severe accident in LWRs, (5) materials degradation and structural integrity, (6) safety of nuclear fuel cycle facilities, (7) safety management on criticality, (8) safety of radioactive waste management, and (9) nuclear safeguards.

JAEA Reports

A Guide to introducing burnup credit, preliminary version (English translation)

Okuno, Hiroshi; Suyama, Kenya; Ryufuku, Susumu*

JAEA-Review 2017-010, 93 Pages, 2017/06

JAEA-Review-2017-010.pdf:2.47MB

There is an ongoing discussion on the application of burnup credit to the criticality safety controls of facilities that treat spent fuels. With regard to such application of burnup credit in Japan, this document summarizes the current technical status of the prediction of the isotopic composition and criticality of spent fuels, as well as safety evaluation concerns and the current status of legal affairs. This report is an English translation of A Guide to Introducing Burnup Credit, Preliminary Version, originally published in Japanese as JAERI-Tech 2001-055 by the Nuclear Fuel Cycle Facility Safety Research Committee.

JAEA Reports

Solvent extraction and release behavior of ruthenium and europium in fire accident conditions in reprocessing plants (Contract research)

Amano, Yuki; Watanabe, Koji; Masaki, Tomoo; Tashiro, Shinsuke; Abe, Hitoshi

JAEA-Technology 2016-012, 21 Pages, 2016/06

JAEA-Technology-2016-012.pdf:1.81MB

To contribute to safety evaluation of fire accident in fuel reprocessing plants, solvent extraction behavior of ruthenium, which could form volatile species, was investigated. Distribution ratios of ruthenium at fire accident conditions were obtained by extraction experiments with several solvent composition at different temperature as parameters. In order to investigate release behavior of ruthenium and europium at fire accident, release ratios of ruthenium and europium were also obtained by solvent combustion experiments.

JAEA Reports

Investigation of release behavior of volatile ruthenium species from thermal decomposition of ruthenium nitrosylnitrate

Abe, Hitoshi; Masaki, Tomoo; Amano, Yuki; Uchiyama, Gunzo

JAEA-Research 2014-022, 12 Pages, 2014/11

JAEA-Research-2014-022.pdf:1.03MB

To contribute safety evaluation of boiling and drying accident of high active liquid waste (HALW) in fuel reprocessing plant, release behavior of Ru, which was considered as an important nuclide for evaluating public dose from the volatile viewpoint, has been investigated. It has been reported that release of Ru becomes conspicuously after HALW is dried up. In this work, to grasp the release behavior of Ru, release ratio of Ru with thermal decomposition of Ru nitrate, which would be in the dried HALW, was measured and release rate constant of Ru from the nitrate was estimated. It was found that the calculation result of release rate of Ru from the nitrate with rise of temperature by using the constant could well simulate the result acquired from the beaker-scale experiment.

JAEA Reports

Proceedings of the International symposium NUCEF 2005; February 9-10, 2005, Techno Community Square RICOTTI, Tokai-mura, Ibaraki-ken, Japan

International Symposium NUCEF 2005 Working Group

JAERI-Conf 2005-007, 359 Pages, 2005/08

JAERI-Conf-2005-007.pdf:24.79MB

Japan Atomic Energy Research Institute (JAERI) held the international symposium NUCEF2005 at Techno Community Square RICOTTI in Tokai-mura on February 9 and 10, 2005. This symposium was co-organized by Japan Nuclear Cycle Development Institute (JNC), and Nuclear Fuel Cycle Safety Research Committee authorized the program. Two hundred thirty-nine participants from 11 countries presented fifty-nine papers, and discussed recent research activities and its outputs on waste disposal safety, fuel cycle facility safety including criticality safety, and separation process development. The presented papers are compiled in the proceedings.

Journal Articles

Study on safety evaluation for nuclear fuel cycle facility under accident conditions

Abe, Hitoshi; Tashiro, Shinsuke; Morita, Yasuji

JAERI-Conf 2005-007, p.199 - 204, 2005/08

Source term data for estimating release behavior of radioactive nuclides is necessary to evaluate synthetic safety of nuclear fuel cycle facility under accident conditions, such as fire and criticality. In JAERI, the data has been obtained by performing some demonstration tests. In this paper, the data for the criticality accident in fuel solution obtained from the TRACY experiment, will be mainly reviewed. At 4.5 h after the transient criticality, the release ratio of the iodine were about 0.2% for re-insertion of transient rod at just after transient criticality and about 0.9% for not re-insertion. Similarly the release coefficient and release ratio for Xe were estimated. It was proved that the release ratio of Xe-141 from the solution was over 90% in case that the inverse period was over about 100 (1/s). Furthermore, outline of the study on the fire accident as future plan will be also mentioned.

JAEA Reports

Progress of nuclear safety research, 2004

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2005-009, 151 Pages, 2005/03

JAERI-Review-2005-009.pdf:31.04MB

no abstracts in English

JAEA Reports

Progress of nuclear safety research, 2003

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2004-010, 155 Pages, 2004/03

JAERI-Review-2004-010.pdf:16.43MB

JAERl is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERl are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. This report summarizes the nuclear safety research activities of JAERI from April 2001 through March 2003 and utilized facilities.

JAEA Reports

Overview of nuclear safety research 2001-2002

Nuclear Safety Research Center Planning and Analysis Division

JAERI-Review 2003-040, 298 Pages, 2004/01

JAERI-Review-2003-040.pdf:24.14MB

JAERl is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Annual Plan for Nuclear Safety Research issued by the Nuclear Safety Commission. The fields of conducting safety research at JAERl are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. This report summarizes the nuclear safety research activities of JAERI from April 2001 through March 2003.

JAEA Reports

Progress of nuclear safety research; 2002

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2002-030, 143 Pages, 2002/11

JAERI-Review-2002-030.pdf:16.51MB

JAERl is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERl concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002.

Journal Articles

Design of the ITER tritium plant, confinement and detritiation facilities

Yoshida, Hiroshi; Glugla, M.*; Hayashi, Takumi; L$"a$sser, R.*; Murdoch, D.*; Nishi, Masataka; Haange, R.*

Fusion Engineering and Design, 61-62, p.513 - 523, 2002/11

 Times Cited Count:21 Percentile:18.33

ITER tritium plant is composed of tokamak fuel cycle systems, tritium confinement and detritation systems. The tokamak fuel cycle systems, composed of various tritium sumsystems such as vacuum vessel cleaning gas processing, tokamak exhaust processing, hydrogen isotope separation, fuel storage, mixing and delivery, and external tritium receiving and long-term storage, has been designed to meet not only ITER operation scenarios but safety requirements (minimization of equipment tritium inventory and reduction of environmental tritium release at different off-normal events and accident scenarios). Multiple confinement design was employed because tritium easily permeates through metals (at $$>$$ 150 $$^{circ}$$C) and plastics (at ambient temperature) and mixed with moisture in room air. That is, tritium process equipment and piping are designed to be the primary confinement barrier, and the process equipments (tritium inventory $$>$$ 1 g) are surrounded by the secondary confinement barrier such as a glovebox. Tritium process rooms, which contains these facilities, form the tertiary confinement barrier, and equipped with emergency isolation valves in the heating ventillation and air conditioning ducts as well as atmosphere detritiation systems. This confinement approach has been applied to tokamak building, tritium building, and hotcell and radwaste building.

JAEA Reports

Proceedings of the International Symposium NUCEF 2001; Scientific Bases for Criticality Safety, Separation Process and Waste Disposal

NUCEF 2001 Symposium Working Group

JAERI-Conf 2002-004, 714 Pages, 2002/03

JAERI-Conf-2002-004.pdf:69.13MB

This volume contains 94 papers presented at the 3rd NUCEF International Symposium NUCEF 2001 held on October 31 - November 2, 2001, in Tokai, Japan, following the 1st symposium NUCEF'95 (Proceedings: JAERI-Conf 96-003) and the 2nd symposium NUCEF'98 (Proceedings: JAERI-Conf 99-004). The theme of this symposium was " Scientific Basis for Criticality Safety, Separation Process and Waste Disposal". The papers were presented in oral and poster sessions on following research fields: (1) Separation Process, (2) TRU Chemistry, (3) Radioactive Waste Disposal, (4) Criticality Safety.

JAEA Reports

Progress of nuclear safety resarch; 2001

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2001-032, 126 Pages, 2001/10

JAERI-Review-2001-032.pdf:10.42MB

no abstracts in English

JAEA Reports

A Guide introducing burnup credit, preliminary version (Contract research)

Nuclear Fuel Cycle Facility Safety Research Committee

JAERI-Tech 2001-055, 92 Pages, 2001/07

JAERI-Tech-2001-055.pdf:5.39MB

no abstracts in English

JAEA Reports

Status of nuclear safety research, 2000

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2000-028, 106 Pages, 2000/11

JAERI-Review-2000-028.pdf:14.37MB

no abstracts in English

Journal Articles

Effect of long-term storage of LWR spent fuel on Pu-thermal fuel cycle

Kurosawa, Masayoshi; Naito, Yoshitaka; Suyama, Kenya; *; Suzuki, Katsuo*; *

Nippon Genshiryoku Gakkai-Shi, 40(6), p.486 - 494, 1998/00

 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Current status of the NUCEF project

Takeshita, Isao

Genshiryoku Shisutemu Nyusu, 7(4), p.30 - 36, 1997/03

no abstracts in English

Journal Articles

NUCEF program

Proc. of the 3rd Int. Conf. on Nuclear Fuel Reprocessing and Waste Management,Vol. 1, p.189 - 194, 1991/00

no abstracts in English

Journal Articles

Nuclear criticality safety design of STACY and TRACY; Two criticality experiments facilities

Yanagisawa, Hiroshi; Takeshita, Isao; Miyoshi, Yoshinori; Sugikawa, Susumu; Suzaki, Takenori; Tachimori, Shoichi

Proc. of the 91 Int. Conf. on Nuclear Criticality Safety,Vol. 2, p.V-65 - V-72, 1991/00

no abstracts in English

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