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Journal Articles

Development of the training tools for nuclear security; Physical Protection Exercise Field (PPEF) and Virtual Reality (VR) training system

Kawata, Norio; Wakabayashi, Shuji; Hanai, Tasuku; Yamaguchi, Yasuo; Nonaka, Nobuyuki; Scharmer, C.*

Proceedings of International Conference on Nuclear Security; Enhancing Global Efforts (CD-ROM), 10 Pages, 2014/03

The ISCN of the JAEA provides effective trainings in order to strengthen nuclear security for emerging nuclear power countries in Asia to realize Japan's National Statement at the Washington Nuclear Security Summit in April 2010. As a part of these activities, the ISCN has developed the PPEF and the VR training system, which are training tools to implement experience-oriented and interactive lessons. These two facilities are mutually complemented and contribute to deeper understandings through actual practices in addition to the classroom lesson. The ISCN initiated its full-scale training from 2012 JFY, and these two facilities received more than 450 trainees or vistors from Japan and over-sea countries. This paper provides the basic concepts and outlines of these two facilities and the training programs that use them for teaching the nuclear security.

Journal Articles

Virtual-reality training system for nuclear security

Nonaka, Nobuyuki

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 7 Pages, 2012/10

At the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency, the virtual reality (VR) training system is under development for providing a practical training environment to implement experience-oriented and interactive lessons on nuclear security for wide range of participants in human resource development assistance program mainly to Asian emerging nuclear-power countries. This system electrically recreates and visualizes nuclear facilities and training conditions in stereoscopic (3D) view on a large-scale display (CAVE system) as virtual reality training facility (VR facility) and it provides training participants with effective environments to learn installation and layout of security equipment in the facility testing and verifying visually the protection performances under various situations such as changes in day-night lighting and weather conditions, which may lead to practical exercise in the design and evaluation of the physical protection system. This paper introduces basic concept of the system and outline of training programs as well as featured aspects in using the VR technology for the nuclear security.

Journal Articles

Development of regional training course for physical protection of nuclear material and facilities at Integrated Support Center for Nuclear Nonproliferation and Nuclear Security

Naoi, Yosuke; Kobayashi, Naoki; Hamada, Kazuko; Noro, Naoko; Matsuzawa, Reina; Wakabayashi, Shuji; Nonaka, Nobuyuki; Senzaki, Masao; Scharmer, C.*; Duggan, R.*; et al.

Proceedings of INMM 53rd Annual Meeting (CD-ROM), 10 Pages, 2012/07

At the 2010 Washington Nuclear Security Summit, Japan committed to establish a regional center for the strengthening of nuclear security, mainly in Asia, through capacity building support including human resources training and infrastructure development assistance. In accordance with this statement, the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) was inaugurated in December 2010 in Japan Atomic Energy Agency (JAEA). This paper describes the ISCN training activities and introduces the developing new training course on physical protection.

JAEA Reports

Analysis of ULOF accident in Monju reflecting the knowledge from CABRI in-pile experiments and others

Sato, Ikken; Tobita, Yoshiharu; Suzuki, Toru; Kawada, Kenichi; Fukano, Yoshitaka; Fujita, Satoshi; Kamiyama, Kenji; Nonaka, Nobuyuki; Ishikawa, Makoto; Usami, Shin

JAEA-Research 2007-055, 84 Pages, 2007/05

JAEA-Research-2007-055.pdf:16.66MB

In the first licensing procedure of the prototype FBR "Monju", the event sequence of ULOF (Unprotected Loss of Flow) was analyzed and the estimated mechanical energy was about 380 MJ as an isentropic expansion potential to atmospheric pressure. The prototype FBR has been stopped for more than 10 years since the sodium leakage accident in the secondary loop in 1995. The neutronic characteristics of reactor core changed as a consequence of radioactive decay of fissile Plutonium during this shutdown period. In order to assess the effect of this neutronic characteristics change to the mechanical energy release in ULOF, the event sequence of ULOF was analyzed reflecting the current knowledge, which was obtained by safety studies after the first licensing of the prototype reactor. It was shown that the evaluated mechanical energy release became smaller than 380 MJ, even with the change of neutronic characteristics.

Journal Articles

EVALUATION OF CDA ENERGETICS IN THE PROTOTYPE LMFBR WITH LASTEST KNOWLEDGE AND TOOLS

; ; ;

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

JAEA Reports

An evaluation study on ULOF event sequences in the prototype FBR; An evaluation of CDA reflecting the latest knowledge

Tobita, Yoshiharu; Morita, Koji; Kawada, Kenichi; Niwa, Hajime; Nonaka, Nobuyuki

PNC TN9410 97-079, 106 Pages, 1997/09

PNC-TN9410-97-079.pdf:3.9MB

The sequences of ULOF (unprotected loss-of-flow) event in the prototype FBR has been evaluated, as a part of the research and development (R&D) in the reactor safety research, reflecting the latest experimental and analytical knowledge on CDA (core disruptive accident) which has been accumulated at O-arai Engineering Center. In the R&D activity on the FBR reactor safety subject, we have accumulated the experimental knowledge of mitigation mechanism in the energy generating process in CDA, utilizing international in-pile safety experimental programs such as CABRI program, as well as the out-of-pile experiments in Japan and foreign countries. This knowledge has been reflected to the development and validation of the SAS and SIMMER code. The objectives of this study are to apply these new assessment techniques to the prototype FBR and to clarify quantitatively in detail the energy generation process of CDA. In this study, an emphasis is placed on the event sequence of the melt progression phase ("transition phase") which has been recognized as one of the important issues of CDA analysis. The major parameters to be considered in this phase are the change of the mobile molten fuel mass and the history of the fuel motion, and also the relation between these parameters and energy generation mechanism. The following methods and approaches have been taken into account in this evaluation study. (a)The SAS4A code is used for the analysis of the transient behavior in the first Phase driven by core voiding ("initiating phase"), and the SIMMER-III code is used for the latter phases with melt-progression (tansition phase) and also the energy conversion process from the thermal one to the mechanical one. These codes have been developed and validated under the collaboration among PNC, CEA and FZK. (b)The uncertainty band of the void reactivity worth and Doppler coeficient has been reduced through the re-evaluation of the critical experimental data in the neutron physics area. ...

Journal Articles

SIMMER-III Applications to Key Phenomena of CDAs in LMFR

Morita, Koji; Tobita, Yoshiharu; ;

Proceedings of 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), Vo.3, p.1332 - 1339, 1997/00

None

Journal Articles

Study of In-Pile Test Facility for Fast Reactor Safety Research: Performance Requirements and Design Features

; ; ; ;

Proceedings of ENS Class 1 Topical Meeting; Research Facilities for the Future of Nuclear Energy, p.512 - 52, 1996/00

None

Journal Articles

Characterization of LMFBR Severe accidents progression

Miyake, Osamu; ;

Nuclear Technology, 0 Pages, 1995/01

A general framework to represent and characterize dominant in-vessel and ex-vessel sequences ofan LMFBR severe accident is presented with emphasis on the role of physical barriers and relevant mitigation features against major loading mechanisms.An assessment of ULOF-initiated accident spectra for a model plant identified the risk-dominant seaquences and their

Journal Articles

None

Ninokata, Hisashi; ;

International Conference on Design and Safety of Advanced Nuclear Power Plants (ANP '92), 3, 29.3-1 Pages, 1992/10

None

Journal Articles

None

; Sato, Ikkenn;

Donen Giho, (82), p.38 - 55, 1992/06

None

Journal Articles

Improvement of Evaluation Method for Initiating-Phase Energetics Based on CABRI-1 In-Pile Experiments

; Sato, Ikkenn

Nuclear Technology, 98(1), p.54 - 69, 1991/00

 Times Cited Count:22 Percentile:86.37(Nuclear Science & Technology)

None

JAEA Reports

Self-Limiting Mechanisms for CDA Energetics Based on In-Pile Experiment Analysis and Improved Reactor Evaluation Method

*

PNC TN9410 90-154, 50 Pages, 1990/10

PNC-TN9410-90-154.pdf:1.21MB

The present report discusses the current understanding and improved evaluation method of key phenomena in the initiating-phase energetics of ULOF whole-core accidents in LMFBRs. Three phenomena, i.e. axial fuel expansion, fuel failure and post-failure fuel motion, have been examined through the CABRI-1 in-pile tests and analyses with special emphasis on the mechanisms for self-limiting the energetics potential. Major important mechanisms, identified in this study, are: (1) fuel expansion effective to delay the ULOF-induced power burst; (2) fuel-dispersal potential activated under low energy condition in voided channels, and enhanced fuel mobility with increased heating rate; (3) above-midplane failure and failure extension effective particularly in partially voided channels. The improved knowledge validated through the CABRI-1 analyses has been implemented to the revised SAS3D code as an improved evaluation method of CDAs, and the importance and effectiveness of the mechanisms were confirmed by the reactor application study.

JAEA Reports

In-pile experiment analyses relevant to initiating-phase energetics

*; *; *; F.Kasah*

PNC TN9410 88-151, 35 Pages, 1988/11

PNC-TN9410-88-151.pdf:1.9MB

For the safety assessment of LMFBRs, much effort has been devoted to the analyses of LOF accident sequences with an emphasis on initiating-phase (IP) energetics (LOF-d-TOP event). Important knowledge and experiences on the IP energetics have been accumulated through reactor studies and in-pile experiment analyses, typically for the CABRI experiments. The present paper summarises the current understanding of key phenomenology relevant to the IP energetics based on the CABRl experiment analyses and the validation study for the PAPAS-2S, SAS3D and SAS4A codes.

JAEA Reports

None

*; *; *

PNC TN951 84-04, , 1984/07

PNC-TN951-84-04.pdf:3.61MB
PNC-TN951-84-04REV1.pdf:2.98MB

no abstracts in English

Journal Articles

None

1990 International Fast Reactor Safety Meeting, , 

None

Journal Articles

None

1990 International Fast Reactor Safety Meeting, , 

None

Journal Articles

None

1990 International Fast Reactor Safety Meeting, , 

None

Journal Articles

None

International Conference on Fast Reactor Core and, , 

None

Journal Articles

None

*; *; *; *

International Meeting on the Science and Technolog of Fast Reactor Safety, , 

None

21 (Records 1-20 displayed on this page)