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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

Journal Articles

Transient response of LWR fuels (RIA)

Udagawa, Yutaka; Fuketa, Toyoshi*

Comprehensive Nuclear Materials, 2nd Edition, Vol.2, p.322 - 338, 2020/08

Journal Articles

Behaviors of high-burnup LWR fuels with improved materials under design-basis accident conditions

Amaya, Masaki; Udagawa, Yutaka; Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10

Journal Articles

Creep behavior and microstructure for two-dimensional C/C composite

Shibata, Taiju; Baba, Shinichi; Yamaji, Masatoshi*; Sumita, Junya; Ishihara, Masahiro

Nihon Kikai Gakkai M&M 2004 Zairyo Rikigaku Kanfarensu Koen Rombunshu, p.407 - 408, 2004/00

no abstracts in English

JAEA Reports

Dose evaluation with ICRP Publication 60 at postulated accidents of NSRR, 2003

Kashima, Yoichi; Taki, Mitsumasa; Kikuchi, Masamitsu; Sasajima, Hideo; Nakamura, Takehiko

JAERI-Tech 2003-088, 100 Pages, 2003/12

JAERI-Tech-2003-088.pdf:5.55MB

A new experiment plan is in progress to perform pulse-irradiation experiments at the NSRR with irradiated fuel rods in the high temperature and high pressure capsules. This report describes the results of the public dose evaluation for the design basis accident and postulated accidents with the models that follow the ICRP Publication 60. It was confirmed that the results met the criteria for safety design and siting with ample margins.

JAEA Reports

JAEA Reports

Analysis of ROSA-IV/LSTF experiment simulating a steam generator tube rupture design basis incident by using RELAP5/MOD2 code

Watanabe, Tadashi; M.Wang*; Kukita, Yutaka

JAERI-M 93-039, 26 Pages, 1993/03

JAERI-M-93-039.pdf:0.85MB

no abstracts in English

JAEA Reports

Safety analysis of JMTR LEU fuel core, 3; Dose analysis at accidents in safety and site evaluation

Tsuchida, Noboru; ; ; ; ; Saito, Minoru;

JAERI-M 92-152, 92 Pages, 1992/10

JAERI-M-92-152.pdf:2.71MB

no abstracts in English

JAEA Reports

Safety Analysis of the Upgranded JRR-3 with HEATING5 Code

; ; *;

JAERI-M 85-019, 40 Pages, 1985/02

JAERI-M-85-019.pdf:1.02MB

no abstracts in English

Oral presentation

Current status toward the reoperation of JMTR

Kaminaga, Masanori; Kusunoki, Tsuyoshi; Araki, Masanori

no journal, , 

The Japan Materials Testing Reactor (JMTR) is a light water cooled and moderated tank type research reactor with 50MW thermal power. From its first criticality in March 1968, the JMTR has been utilized for the fuel/material irradiation examinations of the LWRs, the HTGR and nuclear fusion research as well as for the RI productions. The JMTR operation was once stopped in order to have a check & review in August 2006, and the refurbishment and restart of the JMTR was finally determined after the national discussion. The refurbishment was started from JFY 2007, and was finished in March 2011. However, at the end of the JFY 2010, the Great East Japan Earthquake occurred, and the functional tests before the JMTR restart were delayed. On the other hand, based on the safety assessments considering the Great East Japan Earthquake in 2011, new regulatory requirements for research and test reactors have been established on Dec.18, 2013 by the NRA (Nuclear Regulation Authority). The new regulatory requirements include the satisfaction of integrities for the updated earthquake forces, Tsunami, the consideration of natural phenomena, the provision of manuals for full evacuation, and the management of consideration in the Beyond Design Basis Accidents to protect fuel damage and to mitigate impact of the accidents. Above analyses have intensively been performed, and an application to the NRA was submitted on March 27, 2015. In this presentation, the recent activities for the new regulatory requirements and a training course for foreign young researchers and engineers are introduced.

Oral presentation

Fuel safety research at JAEA

Amaya, Masaki

no journal, , 

no abstracts in English

Oral presentation

New approach to beyond design basis events in structural strength field

Kasahara, Naoto*; Demachi, Kazuyuki*; Sato, Takuya*; Ichimiya, Masakazu*; Wakai, Takashi; Yamano, Hidemasa; Nakamura, Izumi*

no journal, , 

The conventional purpose in the field of structural strength has been to prevent damage to design basis events (DBE). For beyond design basis events (BDBE), it is necessary to mitigate the impact on safety on the premise that damage will occur. The authors propose a mitigation method that suppresses the consequence into a fracture mode with a large impact by reducing the load due to a fracture with a small impact on safety. We will introduce the research results for individual component, extend the applicable area to systems of components, and propose a new approach that contributes to improving plant safety.

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