Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Tamai, Hiroshi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 64(8), p.465 - 467, 2022/08
Though nuclear safety and nuclear security share the same goal of protecting the public and the environment from the harmful effects of ionizing radiation, their response actions may have differences, especially during transport, where protection could be vulnerable. The interface between them is a major issue. In December 2021, with the aim of complementarily strengthening nuclear safety and nuclear security in the transportation of radioactive materials IAEA published a related technical report and held an international conference. The outline of the technical report and the international conference is introduced.
Tamai, Hiroshi
Nihon Genshiryoku Gakkai-Shi ATOMO, 63(9), p.677 - 678, 2021/09
The International Atomic Energy Agency, IAEA, has issued a technical report on national approaches to the interface between nuclear safety and nuclear security, which is essential for strengthening through mutual complementation. The report aims to provide Member States with insights on good practices, each of which is important in coordinating the interface. Those are states' experiences in (i) legal and regulatory framework, (ii) nuclear installations, (iii) radioactive sources and associated facilities and activities, (iv) management systems and nuclear safety and nuclear security culture, (v) emergency preparedness and response, and common issues in cross-cutting field.
Fukano, Yoshitaka
Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 10 Pages, 2017/07
An evaluation on the consequences of a hypothetical total instantaneous flow blockage at the coolant inlet of an SA (HTIB) using SAS4A code was also performed in the past study. SAS4A code was further developed by implementing analytical model of power control system in this study. An evaluation on the consequences of HTIB in Monju by this developed SAS4A code was performed. It was clarified by the analyses considering power control system that the reactor would be safely shut down by the plant protection system triggered by either of 116 percent over power or delayed neutron detector trip signals. Therefore the conclusion in the past study that the consequences of HTIB event would be much less severe than that of unprotected loss-of-flow event was strongly supported by this study. Furthermore SAS4A code was newly validated using an in-pile experiment which simulated HTIB events. The validity of SAS4A application to safety evaluation on the consequence of HTIB was further enhanced in this study.
Tamai, Hiroshi; Tazaki, Makiko; Kokaji, Lisa; Shimizu, Ryo; Suda, Kazunori
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 7 Pages, 2015/12
In recent years the promotion of nuclear security culture aiming at strengthening nuclear security is extensively mentioned, however, awareness of nuclear security culture seems to be not much high compared to the permeation of nuclear safety culture. As a world's leading country of peaceful nuclear use, permeation of nuclear security culture into each personnel attitude must be one of important issues in Japan. Learning from the TEPCO Fukushima Daiichi Nuclear Power Plant accident, complementarity between nuclear safety and nuclear security in the aspect of both protection measures has been profoundly recognised. Therefore, it will be natural to promote nuclear security culture modelled on the preceding nuclear safety culture. On this standpoint, the paper examines an approach for the promotion of nuclear security culture which, for example, consists of awareness cultivation, attitude progress, permeation assessment, and resulting in the establishment of PDCA Cycle.
Kudo, Tamotsu; Onizawa, Kunio*; Nakamura, Takehiko
JAEA-Evaluation 2015-011, 209 Pages, 2015/11
JAEA-Evaluation-2015-011.pdf:10.36MB
Japan Atomic Energy Agency (JAEA) consulted an assessment committee, "Evaluation Committee of Research and Development (R&D) Activities for Nuclear Safety", for post- and pre-review assessment of R&D on nuclear safety research. In response to JAEA's request, the Committee assessed mainly the progress of the R&D project according to guidelines, which addressed the rationale behind the R&D project, the relevance of the project outcome and the efficiency of the project implementation during the period of the current and next plan. As a result, the Committee concluded that the progress of the R&D project is satisfactory. This report describes the results of evaluation by the Committee. In addition, the appendix of this report contains presentations used for the evaluation, and responses from JAEA on the comments from the member of the Committee.
Noda, Kenji; Yokota, Wataru
Denki Hyoron, 88(2), p.55 - 63, 2003/02
no abstracts in English
Sakai, Akihiro; Okoshi, Minoru
Radiation Risk Assessment Workshop Proceedings, p.175 - 186, 2003/00
To establish the clearance levels, the Nuclear Safety Commission (NSC) has been discussing the clearance levels since May 1997. The NSC derived the unconditional clearance levels for the solid materials, namely concrete and metal, arising from the operation and dismantling of nuclear reactors and post irradiation examination (PIE) facilities. Two destinations of the cleared materials, namely disposal and recycle/reuse, were considered. Deterministic calculation models were established to assess individual doses resulting from 73 exposure pathways, and realistic parameter values were selected considering the Japanese natural and social conditions. The clearance levels for 21 radionuclides of nuclear reactors and for 49 of PIE facilities were derived as radioactivity concentration equivalent to the individual doses of 10 
Sv/y. Most of calculated clearance levels were nearly the same as those shown in IAEA-TECDOC-855. Some, however, were different. It is considered that the major reasons depend on differences of fixed scenarios and of selected values of parameters.
Ikuta, Yuko; Shitomi, Hajimu*; Saeki, Masakatsu
Radioisotopes, 51(11), p.509 - 521, 2002/11
no abstracts in English
Ikuta, Yuko; Shitomi, Hajimu*; Saeki, Masakatsu
Nihon Genshiryoku Gakkai-Shi, 44(10), p.744 - 745, 2002/10
no abstracts in English
Kobayashi, Hideo
Genshiryoku Nenkan 2001/2002-Nen Ban, p.103 - 105, 2001/11
no abstracts in English
JNC TN1400 2001-015, 509 Pages, 2001/10
JNC-TN1400-2001-015.pdf:25.67MB
no abstracts in English
; ; ; Takeda, Seiichiro
JNC TN8420 2001-008, 134 Pages, 2001/07
This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decomissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decomissioning of the nuclear facilities are as follows. (1)Tokai works. The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2)Ningyo-toge Environmental Engineering Center. The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton.
Nuclear Safety Research Center
JAERI-Conf 2001-008, 392 Pages, 2001/07
JAERI-Conf-2001-008.pdf:20.07MB
no abstracts in English
JNC TN1400 2000-012, 250 Pages, 2000/11
JNC-TN1400-2000-012.pdf:10.18MB
no abstracts in English
Nishiza, Masahiro
Genshiryoku Nenkan 2000/2001-Nen Ban, p.104 - 106, 2000/10
no abstracts in English
; Washiya, Tadahiro;
JNC TN8420 2001-009, 48 Pages, 2000/04
JNC-TN8420-2001-009.pdf:0.58MB
ICONE(International Conference on Nuclear Engineering) is an international conference on nuclear chemical engineering held among the United States, Japan and Europe, and ICONE8 (the 8th time of the conference) was held at Baltimore, USA on April 2 to 6, 2000. The authors of this paper reported the latest information on the reprocessing technology in the following session of the conference and audited the panel discussion and the technical report of the dry reprocessing technology etc. in the conference. (1)Investigation of Safety Evaluation Method and Application to Tokai Reprocessing Plant (TRP) in session of Track-5 "Non-reactor Safety and Reliability" (Nakamura) (2)Structural Improvement on the continuous rotary dissolver in session of Track-9 "Spent Nuclear Fuel and Waste Processing" (Washiya) (3)Development of Evaporators Made of Ti-5% Ta Alloy and Zr - Endurance Test By Mock-Up unit" in session of Track-2 "Aging and Modeling of Component Aging, Including corrosion of Metals and Welds.. passivation, and passive films" (Takata) At the conference, about 650 people participated from the United States, Japan, France, Canada and others, about700 research announcements, 7 keynote lecture and 8 panel discussion were done, flourishing with many participants. Moreover, as the conference was held in the year of 2000, the evaluation of this century and the direction of the next century of nuclear energy were discussed. After the conference, authors visited Argonne National Laboratory (ANL-E, ANL-W) and exchanged information concerning dry process with researchers of ANL-E and ANL-W, visiting ANL facilities. It was very significant to be able to acquire the information on the dry process developed in ANL and realize the device scale and the development environment, etc. and acquire technical information in detail which would not be able to obtain by engineering data, exchanging information with ANL engineers directly. It is suggested to be very valuable that the ...
