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Journal Articles

Promotion for establishing and maintaining appropriate responses in the safeguards activities, 2; Case study activities

Shirafuji, Masaya; Hasegawa, Rie; Akutsu, Narumi*; Maruyama, Hajime; Miyaji, Noriko

Dai-44-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2023/11

To maintain transparency in the use of nuclear materials in Japan, it is important for operators to appropriately respond to safeguards activities conducted by the IAEA/Japan. Failure to appropriately respond to these activities could have significant impacts, such as raising suspicion from the international community about the misuse of nuclear materials by not only the operators but also Japan. To appropriately respond to safeguards activities, JAEA has conducted some activities such as education on safeguards for all employees and case study activities for the employees engaged in responding to safeguards activities. This paper focused on case study activities that started in FY2022. In FY2022, we created documents based on scenarios with problems in safeguards responses in order to promote understanding among participants. We also conducted a questionnaire survey for participants, and we evaluated the result of the questionnaire. The evaluation results showed that the case study activities contributed to raising awareness of safeguards responses, although there were improvements. After making improvements, we are conducting these activities again in FY2023. Since case study activities are expected to be effective if carried out continuously, we plan to continue them in combination with other activities.

Journal Articles

Experience on implementation of the Integrated Safeguards approach for the MOX facility from the operator's point of view

Nomi, Takayoshi; Nagatani, Taketeru; Ninagawa, Junichi; Nakajima, Shinji; Maruyama, Hajime; Asano, Takashi; Fujiwara, Shigeo

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2011/11

The IS approach for the JNC-1 site was implemented in August 2008, and this was the first experience in the world. This IS approach aimed not only to improve efficiency and effectiveness of safeguards but also to reduce burden of the plant operation by improvement of efficiency of the inspection activity. It was planned to review effectiveness of this new approach after three years from implementation. And JAEA also evaluated effects by application of the IS approach for two MOX fuel facilities in the JNC-1 site based on the three years experiences from the operator's view point. As the result of evaluation, it was confirmed that there were some difference of benefits by application of the IS approach depending on features of the facility, automation level of equipment and advance level of safeguards systems.

Journal Articles

Selection of design solutions and fabrication methods and supporting R&D for procurement of ITER vessel and FW/blanket

Ioki, Kimihiro*; Elio, F.*; Maruyama, So; Morimoto, Masaaki*; Rozov, V.*; Tivey, R.*; Utin, Y.*

Fusion Engineering and Design, 74(1-4), p.185 - 190, 2005/11

 Times Cited Count:5 Percentile:35.8(Nuclear Science & Technology)

The ITER project has started preparation of Procurement Specification Documents for the vacuum vessel (VV). The design of the VV and FW/Blanket has progressed in many aspects, such as an double curvature pressing instead of facet shape welding for inner and outer shells in the upper and lower inboard regions to improve the fabrication and NDT process. The plasma facing surface of the FW has been defined to avoid protruding the leading edges, especially in the inboard area. Separate FW panels are supported with a central beam, and selection of a race-track shape cross-section for the central beam provides a more robust structure against halo current EM loads and also leads to a new cooling configuration in the shield block, where the pressure drop is significantly reduced to $$sim$$0.05 MPa. A UT R&D program is also going on to achieve acceptable S/N ratio for small-angle launching waves (20-30 deg.) to a weld. Hydraulic testing has been performed to demonstrate natural convection cooling in the transient condition.

Journal Articles

ITER nuclear components, preparing for the construction and R&D results

Ioki, Kimihiro*; Akiba, Masato; Barabaschi, P.*; Barabash, V.*; Chiocchio, S.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Ezato, Koichiro; Federici, G.*; et al.

Journal of Nuclear Materials, 329-333(1), p.31 - 38, 2004/08

 Times Cited Count:14 Percentile:66.09(Materials Science, Multidisciplinary)

The preparation of the procurement specifications is being progressed for key components. Progress has been made in the preparation of the procurement specifications for key nuclear components of ITER. Detailed design of the vacuum vessel (VV) and in-vessel components is being performed to consider fabrication methods and non-destructive tests (NDT). R&D activities are being carried out on vacuum vessel UT inspection with waves launched at an angle of 20 or 30 degree, on flow distribution tests of a two-channel model, on fabrication and testing of FW mockups and panels, on the blanket flexible support as a complete system including the housing, on the blanket co-axial pipe connection with guard vacuum for leak detection, and on divertor vertical target prototypes. The results give confidence in the validity of the design and identify possibilities of attractive alternate fabrication methods.

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Field Trial Experiences of Remote Monitoring System for Unattended Mode Nondestructive Assay(NDA) in PFPF

; ; ;

Dai-43-Kai Kaku Busshitsu Kanri Gakkai Nenji Taikai (INMM), 0 Pages, 2002/00

None

Journal Articles

None

; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 43(6), 0 Pages, 2001/06

None

Journal Articles

None

; Takahashi, Saburo;

Saikuru Kiko Giho, (11), p.51 - 58, 2001/06

None

Journal Articles

None

Ninagawa, Junichi; Takahashi, Saburo; Asano, Takashi; Maruyama, Hajime; Kobayashi, Shigeru*

P.149, (105), p.21 - 25, 1998/03

None

Journal Articles

ITER heat removal system; System and process control design

*; *; *; *; *; Okawa, Yoshinao; Maruyama, So; *; V.Tanchuk*; R.Haange*; et al.

Fusion Technology 1998, 2, 4 Pages, 1998/00

no abstracts in English

Journal Articles

Initial and operational experience for MOX scrap measurement using PSMC

; ; H.Menlove*

INMM, 0 Pages, 1997/00

None

Journal Articles

Development of improved hold-up measurement system at plutonium fuel production facility

Asano, Takashi; Kobayashi, Hideo; ; ; Ninagawa, Junichi

Proceedings of INMM 38th Annual Meeting, 0 Pages, 1997/00

None

Journal Articles

Development of visual inspection technology for HTTR core support graphite structure

Maruyama, So; Iyoku, Tatsuo; Inagaki, Yoshiyuki; Shiozawa, Shusaku; *; *

Nihon Genshiryoku Gakkai-Shi, 38(7), p.601 - 608, 1996/00

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

no abstracts in English

Journal Articles

Nuclear design of the high-temperature engineering test reactor (HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; Fujimoto, Nozomu; Takeda, Takeshi

Nuclear Science and Engineering, 122, p.212 - 228, 1996/00

 Times Cited Count:23 Percentile:85.72(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of multiphase flow to improvement of nuclear power plant safety

Tanaka, Toshiyuki; Maruyama, So

JAERI-Conf 95-011, 0, p.94 - 99, 1995/06

no abstracts in English

JAEA Reports

Demonstration tests for HTGR fuel elements and core components with test sections in HENDEL

; Hino, Ryutaro; Inagaki, Yoshiyuki; Takase, Kazuyuki; Ioka, Ikuo; Takada, Shoji; Suzuki, Kunihiro; Kunitomi, Kazuhiko; Maruyama, So;

JAERI 1333, 196 Pages, 1995/03

JAERI-1333.pdf:8.65MB

no abstracts in English

Journal Articles

Assembly test of HTTR reactor internals

Maruyama, So; Saikusa, Akio; Iyoku, Tatsuo; Shiozawa, Shusaku; *

Transactions of the 13th Int. Conf. on Structural Mechanics in Reactor Technology (SMiRT),Vol. I, 0, p.581 - 586, 1995/00

no abstracts in English

JAEA Reports

Design of High Temperature Engineering Test Reactor (HTTR)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shindo, Masami; Shiozawa, Shusaku; Mogi, Haruyoshi; Okubo, Minoru; Ito, Noboru; Shindo, Ryuichi; et al.

JAERI 1332, 247 Pages, 1994/09

JAERI-1332.pdf:11.53MB

no abstracts in English

Journal Articles

Evaluation of local power distribution with fine-mesh core model for High Temperature Engineering Test Reactor(HTTR)

Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Shindo, Ryuichi; Fujimoto, Nozomu; Sudo, Yukio; Nakata, Tetsuo*

Journal of Nuclear Science and Technology, 31(1), p.62 - 72, 1994/01

 Times Cited Count:3 Percentile:35.79(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Structural design of pressure vessel of High Temperature Engineering Test Reactor

Kurihara, Ryoichi; Tachibana, Yukio; Nishihara, Tetsuo; Maruyama, So; Shiozawa, Shusaku; *

Atsuryoku Gijutsu, 32(3), p.154 - 165, 1994/00

no abstracts in English

68 (Records 1-20 displayed on this page)