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Journal Articles

Numerical study of initiating phase of core disruptive accident in small sodium-cooled fast reactors with negative void reactivity

Ishida, Shinya; Fukano, Yoshitaka; Tobita, Yoshiharu; Okano, Yasushi

Journal of Nuclear Science and Technology, 13 Pages, 2023/00

 Times Cited Count:1 Percentile:68.31(Nuclear Science & Technology)

Journal Articles

Issues and recommendations about application of graded approach to research reactors

Yonomoto, Taisuke; Mineo, Hideaki; Murayama, Yoji; Hohara, Shinya*; Nakajima, Ken*; Nakatsuka, Toru; Uesaka, Mitsuru*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(1), p.73 - 77, 2021/01

no abstracts in English

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.

Journal Articles

Development of an evaluation methodology for the natural circulation decay heat removal system in a sodium cooled fast reactor

Watanabe, Osamu*; Oyama, Kazuhiro*; Endo, Junji*; Doda, Norihiro; Ono, Ayako; Kamide, Hideki; Murakami, Takahiro*; Eguchi, Yuzuru*

Journal of Nuclear Science and Technology, 52(9), p.1102 - 1121, 2015/09

 Times Cited Count:13 Percentile:72.94(Nuclear Science & Technology)

A natural circulation (NC) evaluation methodology has been developed to ensure the safety of a sodium-cooled fast reactor (SFR) of 1500MW adopting the NC decay heat removal system (DHRS). The methodology consists of a 1D safety analysis which can evaluate the core hot spot temperature taking into account the temperature flattening effect in the core, a 3D fluid flow analysis which can evaluate the thermal-hydraulics for local convections and thermal stratifications in the primary system and DHRS, and a statistical safety evaluation method. The safety analysis method and the 3D analysis method have been validated using results of a 1/10 scaled water test simulating the primary system of the SFR and a 1/7 scaled sodium test simulating the primary system and the DHRS, and the applicability of the safety analysis for the SFR has been confirmed by comparing with the 3D analysis. Finally, a statistical safety evaluation has been performed for the SFR using the safety analysis method.

Journal Articles

Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool

Mascari, F.*; Nakamura, Hideo; Umminger, K.*; De Rosa, F.*; D'Auria, F.*

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.4921 - 4934, 2015/08

JAEA Reports

Summary of the 6th Workshop on the Reduced-Moderation Water Reactor; March 6, 2003, JAERI, Tokai

Nabeshima, Kunihiko; Nakatsuka, Toru; Ishikawa, Nobuyuki; Uchikawa, Sadao

JAERI-Conf 2003-020, 240 Pages, 2003/11

JAERI-Conf-2003-020.pdf:27.66MB

The research on Reduced-Moderation Water Reactors (RMWRs) has been performed in JAERI for the development of future innovative reactors. The workshop on the RMWRs has been held every year since 1998 aimed at information exchange between JAERI and other organizations such as universities, laboratories, utilities and vendors. The workshop began with five lectures on status of research and development on RMWRs in JAERI entitled "Status and Future Program of Research and Development on Reduced-Moderation Water Reactors", "Design of Small Reduced-Moderation Water Reactors", "Critical Experiments for Reduced-Moderation Water Reactors", "Critical Heat Flux Experiments in Tight Lattice Core" and "Development of High Performance Cladding". Then two lectures followed: "Status of Phase II of Feasibility Studies on Commercialized Fast Breeder Reactor System" by JNC and "Present Status of Study on Super-critical water Cooled Power Reactor" by Toshiba Corporation.

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

Design of advanced integral-type marine reactor, MRX

Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Ishida, Toshihisa; Hoshi, Tsutao*; Sako, Kiyoshi*

Nuclear Engineering and Design, 201(2-3), p.155 - 175, 2000/10

 Times Cited Count:47 Percentile:92.29(Nuclear Science & Technology)

no abstracts in English

Journal Articles

JAERI's practice for analysis of human behavior during abnormal occurrences at research facilities

Watanabe, Norio; Hirano, Masashi; Yoshida, Kazuo;

Proc. of ICNCA Nuclear Safety Culture Workshop, p.1 - 12, 1998/01

no abstracts in English

Journal Articles

Fusion reactor safety; Issues and perspective

Inabe, Teruo; Seki, Masahiro; Tsunematsu, Toshihide

Fusion Engineering and Design, 42, p.7 - 12, 1998/00

 Times Cited Count:5 Percentile:44.25(Nuclear Science & Technology)

no abstracts in English

Journal Articles

RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following sblocas with totally failed HPI

*; Kukita, Yutaka*; Asaka, Hideaki; M.Wang*; Otani, Etsuo*

Nuclear Technology, 126(3), p.331 - 339, 1998/00

 Times Cited Count:9 Percentile:57.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Design concept of disposal systems for highly activated waste

Okoshi, Minoru; Abe, Masayoshi; Yoshimori, Michiro; Sakai, Akihiro

Proc. of Waste Management'98 (CD-ROM), 5 Pages, 1998/00

no abstracts in English

Journal Articles

Near surface disposal of very low level waste generated from reactor decommissioning and related safety requirements

Okoshi, Minoru; Yoshimori, Michiro; Abe, Masayoshi

Planning and Operation of Low Level Waste Disposal Facilities IAEA-SM-341/70, 0(0), p.416 - 425, 1997/00

no abstracts in English

Journal Articles

Safety features of JAERI passive safety reactor (JPSR)

Murao, Yoshio

Proc. of 11th KAIF/KNS Annual Conf., 0, p.587 - 596, 1996/00

no abstracts in English

Journal Articles

Possibility of a pressurized water reactor concept with highly inherent heat removel following capability

Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 32(4), p.339 - 350, 1995/04

 Times Cited Count:3 Percentile:36.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Concept of passive safety light water reactor system (JPSR)

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.723 - 728, 1995/00

no abstracts in English

Journal Articles

Conceptual design of the JAERI passive safety reactor and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

Transactions of the American Nuclear Society, 71, p.527 - 529, 1995/00

no abstracts in English

Journal Articles

Analysis of system thermal hydraulic responses for passive safety injection experiment at ROSA-IV/Large Scale Test Facility using JAERI modified version of RELAP5/MOD2 code

; Yonomoto, Taisuke; Kukita, Yutaka

Journal of Nuclear Science and Technology, 31(12), p.1265 - 1274, 1994/12

 Times Cited Count:3 Percentile:35.77(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of REFLA/TRAC code for engineering work station

Onuki, Akira; ; Murao, Yoshio

JAERI-M 94-026, 60 Pages, 1994/03

JAERI-M-94-026.pdf:1.81MB

no abstracts in English

Journal Articles

Conceptual design of JAERI passive safety reactor (JPSR) and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

10th Proc. of Nuclear Thermal Hydraulics, 0, p.3 - 12, 1994/00

no abstracts in English

62 (Records 1-20 displayed on this page)