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Journal Articles

Variation of internal doses caused by differences in physical characteristics between the average Japanese and the ICRP's reference man which is based on the standard data of Caucasians in the dosimetric methodology in conformity to the 2007 Recommendations

Manabe, Kentaro; Sato, Kaoru; Takahashi, Fumiaki

Journal of Nuclear Science and Technology, 59(5), p.656 - 664, 2022/05

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

It is known that internal doses depend on the physical characteristics of an evaluation subject. Internal dose coefficients provided by the International Commission on Radiological Protection (ICRP) are evaluated using the characteristics of the standard Caucasian. It is important to grasp the variations of doses due to the differences in characteristics between Japanese and Caucasian when the dose coefficients of ICRP are applied to Japanese. This study evaluated dose coefficients using specific absorbed fraction (SAF) data based on the average adult Japanese physique which was developed by modification of the existing Japanese SAF data with additional calculations to make the existing data fit to the current dosimetric methodology of ICRP and compared them to those provided by ICRP. As a result, the discrepancies in dose coefficients were smaller than plus or minus 10% in most intake conditions. However, some intake conditions indicated varieties over 40% due to the differences in organ masses, amount of adipose tissues around the thoracic cavity, and so on. This information is useful in application of ICRP's dose coefficients to population of which physical characteristics are different from those of Caucasian. Further, the Japanese SAF data is published as an appendix of this paper.

JAEA Reports

Report on activities of "Technical Committee on Mine Closure Activities of the Tono Mine"

Tsurudome, Koji; Suzuki, Hajime; Aoki, Katsunori

JAEA-Review 2021-031, 186 Pages, 2021/12

JAEA-Review-2021-031.pdf:11.79MB

Tono Geoscience Center, Japan Atomic Energy Agency has been conducting mine closure activities at Tono Mine based on "Plan for closure activities of the Tono Mine" since FY2010. The closure activities of the Tono Mine are carried out in accordance with the Mining Act, the Mine Safety Act and the Industrial Safety and Health Act. In particular, in order to examine the technologies applied to the closure activities of the Tono mine, also the surrounding environmental monitoring, "Technical Committee on Mine Closure Activities of the Tono Mine" was organized at Tono Geoscience Center in FY2013 and the results in the previous fiscal year and the plan for the current fiscal year have been reported and discussed at the annual meeting. As a result, it has been confirmed that the closure activities are making progress as planned and that the environment around the mine meets the legally required standards from the monitoring results. This document is a compilation of meeting materials of all eight committee meetings held between FY2013 and FY2019.

Journal Articles

The Efforts for engineer ethics education at the Atomic Energy Society of Japan

Oba, Kyoko

Kogaku Kyoiku, 69(5), p.95 - 98, 2021/09

This paper introduces the recent topics of the Atomic Energy Society of Japan Ethics Committee. In addition, referring to the topics, the abilities and sensibilities that engineers should have in the future will be described.

JAEA Reports

Document collection of the 37th Technical Special Committee on Fugen Decommissioning

Nakamura, Yasuyuki; Koda, Yuya; Yamamoto, Kosuke; Soejima, Goro; Iguchi, Yukihiro

JAEA-Review 2020-002, 40 Pages, 2020/05

JAEA-Review-2020-002.pdf:8.78MB

Fugen Decommissioning Engineering Center, in planning and carrying out our decommissioning technical development, has been establishing "Technical special committee on Fugen decommissioning" which consists of the members well-informed, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials "The Current Situation of Fugen Decommissioning", "Development of Dismantling Mon-hours Estimated system by Achieved Data in Fugen", "Future Plan Based on the Operational Status of Clearance System" and "The Result and Future Plan of the Sampling work from Core Internal of Fugen", presented in the 37th Technical special committee on Fugen decommissioning which was held on December 2, 2019.

JAEA Reports

Evaluation report of research and development on "Geological Disposal of High-level Radioactive Waste" (Interim report)

Geological Disposal Research and Development Department

JAEA-Evaluation 2019-010, 69 Pages, 2020/01

JAEA-Evaluation-2019-010.pdf:2.54MB
JAEA-Evaluation-2019-010-appendix(CD-ROM).zip:13.88MB

Japan Atomic Energy Agency (JAEA) consulted the advisory committee, "Evaluation Committee on Research and Development (R&D) Activities for Geological Disposal of High-Level Radioactive Waste", for an interim review of R&D activities on high-level radioactive waste disposal in accordance with "General Guideline for the Evaluation of Government Research and Development (R&D) Activities" by the Cabinet Office, Government of Japan, "Guideline for Evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology" and JAEA's "Regulation on Conduct for Evaluation of R&D Activities". In response to JAEA's request, the Committee reviewed mainly the progress of the R&D project on geological disposal, the relevance of the project outcome during the period of FY2015-2018. This report summarizes the results of the assessment by the Committee with the Committee report attached.

JAEA Reports

Assessment report on research and development activities; Activity "Research and development on fast reactor cycle technologies" (Interim report)

Sector of Fast Reactor and Advanced Reactor Research and Development

JAEA-Evaluation 2019-004, 47 Pages, 2019/06

JAEA-Evaluation-2019-004.pdf:2.32MB
JAEA-Evaluation-2019-004-appendix(CD-ROM).zip:14.87MB

Japan Atomic Energy Agency (hereafter referred to as "JAEA") consulted with the "Evaluation Committee of Research and Development Activities for Fast Reactor Cycle" (hereinafter referred to as "Committee"), which consists of specialists in the fields of the evaluation subjects of fast reactor cycle technologies, for interim assessment of R&D activities of fast reactor cycle in the 3rd Mid- and Long-Term Plan (from April 2015 to March 2022) in accordance with "General Guideline for the Evaluation of Government Research and Development (R&D) Activities" by Cabinet Office, Government of Japan, "Guideline for Evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology" and Regulation on Conduct for Evaluation of R&D Activities" by JAEA. In response to the JAEA's request, the Committee assessed the R&D program of fast reactor cycle technologies during the period of four years from April 2015 to March 2018. The Committee evaluated the management and R&D activities based on the explanatory documents and oral presentations by JAEA. The results of the evaluation were compiled in assessment report that was organized including the reasons for evaluation and the opinions and recommendations. This report is issued for the purpose of actively disseminate evaluation information to the people of Japan (based on General Guideline), which lists the members of the Committee and outlines the assessment items and the review process for procedure of the assessment. The assessment report which was issued by the Committee is attached.

Journal Articles

Estimating internal dose coefficients of short-lived radionuclides in accordance with ICRP 2007 Recommendations

Manabe, Kentaro; Sato, Kaoru; Takahashi, Fumiaki

Journal of Nuclear Science and Technology, 56(5), p.385 - 393, 2019/05

 Times Cited Count:3 Percentile:31.89(Nuclear Science & Technology)

At high energy accelerator facilities, various radionuclides are produced by nuclear reactions of high energy particles with structure and/or ambient air of the facilities. Consequently, the radionuclides are potential sources of internal exposure for works of the facilities. However, the International Commission on Radiological Protection (ICRP) do not provide dose coefficients, which are committed effective doses per intake, for the short-lived radionuclides whose half-lives are shorter than 10 minutes in accordance with the ICRP 2007 Recommendations. Then, we estimated the dose coefficients for inhalation and ingestion of these short-lived radionuclides in accordance with the ICRP 2007 Recommendations. In addition, we compared the dose coefficients with those in accordance with the ICRP 1990 Recommendations. As a result, a decreasing tendency was shown in the dose coefficients for inhalation cases; an increasing tendency was observed in those for ingestion cases. It was found that these changes in dose coefficients were mainly caused by the revision of the dose calculation procedures, alimentary tract models. The result of this study will be useful for planning of radiation protection at the high energy facilities.

Journal Articles

In middle Heisei period

Nozawa, Takashi

Senmon Toshokan, (295), p.18 - 19, 2019/05

no abstracts in English

Journal Articles

Let's aim at AESJ without Ethics Committee

Oba, Kyoko

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 61(4), p.347 - 348, 2019/04

This article is published in a special feature in commemoration of the 60th anniversary of the Atomic Energy Society of Japan. The article is the contents that "I look back on this, and surveys the future", by chairwoman of Ethics Committee.

Journal Articles

The ICRU proposal for new operational quantities for external radiation

Otto, T.*; Hertel, N. E.*; Bartlett, D. T.*; Behrens, R.*; Bordy, J.-M.*; Dietze, G.*; Endo, Akira; Gualdrini, G.*; Pelliccioni, M.*

Radiation Protection Dosimetry, 180(1-4), p.10 - 16, 2018/08

 Times Cited Count:19 Percentile:89.32(Environmental Sciences)

Report Committee 26 of the ICRU proposes a set of operational quantities for radiation protection for external radiation, directly based on effective dose and for an extended range of particles and energies. It is accompanied by new quantities for estimating deterministic effects to the eye lens and the local skin. The operational quantities are designed to overcome the conceptual and technical shortcomings of those presently in use. This paper describes the proposed operational quantities, and highlights the improvements with respect to the present legal monitoring quantities.

Journal Articles

Recent discussion on protection quantities and operational quantities by ICRP and ICRU

Endo, Akira

Hoken Butsuri, 52(1), p.39 - 41, 2017/03

Radiological protection requires the quantification of the extent of exposure of the human body to ionizing radiation. To this end, the International Commission on Radiological Protection (ICRP) and the International Commission on Radiation Units and Measurements (ICRU) developed a dosimetry system consisting of protection quantities and operational quantities. The existing dosimetry system has been successfully used in radiological protection practice and regulations. Nevertheless, the system has some limitations and needs further improvements to consider changes in the fields of radiological protection. ICRP and ICRU have been discussing the issues to propose an alternative system of radiation dosimetry. This presentation overviews recent discussion on the protection quantities and operational quantities by ICRP and ICRU and the proposed dosimetry system for radiological protection.

Journal Articles

Re-structuring of the NEA Data Bank Management Committee; New Management Committee MBDAV

Suyama, Kenya

Kaku Deta Nyusu (Internet), (115), p.61 - 69, 2016/10

In recent years, discussion on the reform of the governing body of OECD/NEA Data Bank has been carried out. This document explains its background and outline.

JAEA Reports

Evaluation report of research and development on "Geological Disposal of High-Level Radioactive Waste" (Interim report)

Geological Disposal Research and Development Department

JAEA-Evaluation 2015-014, 33 Pages, 2016/02

JAEA-Evaluation-2015-014.pdf:1.06MB
JAEA-Evaluation-2015-014-appendix1(CD-ROM).zip:97.48MB

The Committee reviewed mainly the progress of the R&D project on geological disposal, the relevance of the project outcome during the period of the second midterm plan (FY2010-2014) and the prospect of the next term in light of requirements and effectiveness for R&D activities. As a result, the Committee concluded that the progress of the R&D project was satisfactorily made from the viewpoint of improvements of reliability and practicality for implementation. In addition, the Committee provided a couple of advises to be addressed in the project in next term in light of transfer of techniques and the knowledge taking account of the long-term implementation of the repository program.

Journal Articles

ICRP Publication 116 "Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures"; Summary

Endo, Akira

Isotope News, (736), p.34 - 37, 2015/08

Japanese translation of ICRP Publication 116 entitled "Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures" was published by the Japan Radioisotope Association in March 2015. The book gives fluence to dose conversion coefficients for both effective dose and organ absorbed doses for various types of external exposures, consistent with the 2007 Recommendations of the ICRP. A complete set of conversion coefficients is provided in an accompanying CD in ASCII format and Microsoft Excel software. This article overviews ICRP Publication 116 and its impact to practice of radiation protection.

Journal Articles

News from Broader Approach activities, 52

Ishii, Yasutomo; Matsunaga, Go; Okumura, Yoshikazu

Purazuma, Kaku Yugo Gakkai-Shi, 90(12), p.827 - 828, 2014/12

Holding of the 15th BA Steering Committee, the 14th IFMIF/EVADA business meeting, the 15th IFERC business meeting and the progress of the Satellite Tokamak (JT-60SA) plan were reported. There were participation of 3 committee members and 8 specialists from EU side and also 30 people which is 4 committees, 7 specialists, each project leaders and project committee chair persons, for the 15th BA Steering Committee and approved for the 2015 Work Plan of IFMIF/EVADA project, the IFERC project and the Satellite Tokamak.6 committees (3 EU side, 3 Japan side), 12 specialists (5 EU, 7 JP) and 8 members of IFMIF/EVADA team, for the 14th IFMIF/EVADA meeting and progress of the each activities were reported.6 committees (3 EU, 3 JP), 16 specialists (9 EU, 7 JP) and 9 members of IFERC team, for the 15th IFERC meeting and reported on progress and discussed about the 2015 Work Plan. In the progress of the JT-60SA plan, assembly work of vacuum chamber is proceeding smoothly in the JT-60 main body room.

JAEA Reports

Summative report of the public competition for incunabula research on advanced science and technology in the fiscal year 1996 through 2005

Office of Planning; Advanced Science Research Center

JAERI-Review 2005-040, 119 Pages, 2005/09

JAERI-Review-2005-040.pdf:7.44MB

Japan Atomic Energy Research Institute started the public competition for incunabula research on advanced science and technology in 1996, and continues it up to now. This report describes the system of the competition research, application situations, research subjects adopted, evaluation findings, outputs produced, achievements and problems, as a summative report of practice of the system for six years.

JAEA Reports

Summative report of the public competition research and development on nuclear science and technology in the fiscal year 1998 through 2003

Office of Planning

JAERI-Review 2005-039, 91 Pages, 2005/09

JAERI-Review-2005-039.pdf:5.42MB

Japan Atomic Energy Research Institute started the public competition research and development on nuclear science and technology in 1998, and closed it in 2003. This report describes the system of the competition research and development, application situations, R & D subjects adopted, evaluation findings, outputs produced, achievements and problems, as a summative report of practice of the system for six years.

JAEA Reports

Summative report of the public competition research and development on software for computational science and engineering in the fiscal year 1997 through 2002

Office of Planning; Center for Promotion of Computational Science and Engineering

JAERI-Review 2005-038, 68 Pages, 2005/09

JAERI-Review-2005-038.pdf:3.85MB

Japan Atomic Energy Research Institute started the public competition research and development on software for computational science and engineering in 1997, and closed it in 2002. This report describes the system of the competition research and development, application situations, R & D subjects adopted, evaluation findings, outputs produced, achievements and problems, as a summative report of practice of the system for six years.

JAEA Reports

Report of investigation on malfunction of safety rod (occurred on June 17, 2004) in TRACY

Ad-hoc Committee for Investigation on Malfunction of Safety Rod in

JAERI-Review 2005-006, 60 Pages, 2005/03

JAERI-Review-2005-006.pdf:5.09MB

A trouble, malfunction of a safety rod, occurred during transient operation of the Transient Experiment Critical Facility (TRACY) in Japan Atomic Energy Research Institute (JAERI) on June 17, 2004. JAERI organized its specialists into the ad-hoc committee for investigation on malfunction of a safety rod of TRACY on June 23, 2004, to understand the cause of the trouble and take countermeasures to prevent the issue. The ad-hoc committee held 11 meetings and had discussions on the trouble inquiring the situations of the TRACY operation and the results of examination from the division relevant to the TRACY. As the result of investigation the cause of the trouble was attributed to the following reason: The holding capability of the safety rod was temporarily depressed by a small piece of polyethylene sheet put between the electromagnet and armature of the safety rod, the polyethylene sheet which had been used in overhaul activities of the rod. In the present report, the detailed results of investigation and the countermeasures to prevent the trouble are described.

Journal Articles

Present status and prospect of diagnostics and control technologies for fusion plasmas

Kurihara, Kenichi; Kasugai, Atsushi; Technical Committee for Diagnostics and Control of Fusion Plasmas

Heisei-17-Nen Denki Gakkai Zenkoku Taikai Koen Rombunshu, p.S17_32 - S17_35, 2005/03

no abstracts in English

162 (Records 1-20 displayed on this page)