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JAEA Reports

Consideration on roles and relationship between observations/measurements and model predictions for environmental consequence assessments for nuclear facilities

Togawa, Orihiko; Okura, Takehisa; Kimura, Masanori

JAEA-Review 2022-049, 76 Pages, 2023/01

JAEA-Review-2022-049.pdf:3.74MB

Before construction and after operation of nuclear facilities, environmental consequence assessments are conducted for normal operation and an emergency. These assessments mainly aim at confirming safety for the public around the facilities and producing relief for them. Environmental consequence assessments are carried out using observations/ measurements by environmental monitoring and/or model predictions by calculation models, sometimes using either of which and at other times using both them, according to the situations and necessities. First, this report investigates methods, roles, merits/demerits and relationship between observations/measurements and model predictions which are used for environmental consequence assessments of nuclear facilities, especially holding up a spent nuclear fuel reprocessing plant at Rokkasho, Aomori as an example. Next, it explains representative examples of utilization of data on observations/measurements and results on model predictions, and considers points of attention at using them. Finally, the report describes future direction, for example, improvements of observations/measurements and model predictions, and fusion of both them.

JAEA Reports

Proceedings of the 24th NSRR Technical Review Meeting; Tokyo, November 13-14, 2000

Fuel Safety Research Laboratory

JAERI-Conf 2001-010, 303 Pages, 2001/09

JAERI-Conf-2001-010.pdf:59.22MB

The 24th NSRR Technical Review Meeting was held at Tranomon Pastoral, Tokyo, on November 13 and 14, 2000. The purpose of the meeting was to present and discuss the recent progress of the NSRR program and other LWR fuel safety researches at JAERI. Twenty-one papers, including five by foreign institutes, were presented and discussed regarding fuel behavior during normal operation, reactivity initiated accident (RIA) and loss-of-coolant accident (LOCA) and FP release behavior during severe accident. The meeting was a great help in planning future research and promoting research cooperation. This proceeding contains the papers presented in the meeting.

Journal Articles

Radiation effects and safety control of tritium, IV-5; Dose assessment model and parameter

Noguchi, Hiroshi; Yokoyama, Sumi

Nihon Genshiryoku Gakkai-Shi, 39(11), p.931 - 933, 1997/00

no abstracts in English

Journal Articles

Computer code TERFOC-N to calculate doses to public using terrestrial foodchain models improved and extended for long-lived nuclides

Togawa, Orihiko

Journal of Nuclear Science and Technology, 27(4), p.360 - 374, 1990/04

no abstracts in English

JAEA Reports

Core Hydrodynamic Tests and Determination of Core Flow of JRR-3 to Be Renewed ata 20MWt

Sudo, Yukio; ; *;

JAERI-M 84-119, 108 Pages, 1984/06

JAERI-M-84-119.pdf:2.16MB

no abstracts in English

Journal Articles

Population doses due to the operation of LWRs in Japan

Iijima, T.; Yamaguchi, Yukichi; Homma, T.; Hidaka, Akihide; Miyanaga, I.

IAEA-CN-42/289, p.499 - 508, 1983/00

no abstracts in English

Journal Articles

Prospects of alloy design for zircaloy cladding

;

Zairyo Kagaku, 16(4,5), p.173 - 179, 1979/00

no abstracts in English

Oral presentation

Study on coating technic to enhance accident tolerance of fuel cladding, 3; Irradiation behavior of the Cr coated MDA cladding

Mohamad, A. B.; Chien, J.; Ioka, Ikuo; Suzuki, Eriko; Kondo, Keietsu; Nemoto, Yoshiyuki; Okubo, Nariaki; Yamashita, Shinichiro; Okada, Yuji*; Sato, Daiki*

no journal, , 

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