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JAEA Reports

Development of deterministic approach to assess doses to the public from external exposures in the areas contaminated by the Fukushima Daiichi Nuclear Power Station Accident

Takahara, Shogo; Iijima, Masashi; Shimada, Kazumasa; Kushida, Teruo; Shiratori, Yoshitake

JAEA-Research 2014-024, 57 Pages, 2015/01

JAEA-Research-2014-024.pdf:5.49MB

In order to assess the doses to representative person using deterministic approach, we measured radiation dose rates and surveyed on behavioral patterns in the areas contaminated by the Fukushima Daiichi Nuclear Power Station Accident. Statistical analyzes were also performed to identify the characteristics of individual doses from external exposures, as well as radiation dose rates and behavioral patterns. Radiation dose rates measured in living areas distribute with lognormal form. Behavioral patterns of the populations were different corresponding to their occupation. Time spent outdoors of indoor workers were distributed in lognormal form and those of outdoor workers had the normal distribution. Multi-regression analyses were made to explore a significant relationship between individual doses and relevant contributors. These results indicated that the significant differences were given in individual doses due to the spatial differences of radiation dose rates as well as the interindividual differences of behavioral patterns. Based on the results of analyses of relevant contributors to the external exposures, deterministic dose assessment model was developed. The validity of this model was confirmed because the assessed values were higher than those measured.

JAEA Reports

Decontamination pilot projects for the environmental remediation of evacuation areas contaminated with radioactive materials discharged from the Fukushima Daiichi Nuclear Power Plant accident; Survey on individual doses to the inhabitants living in the areas contaminated by the accident (Contract research)

Takahara, Shogo; Iijima, Masashi; Kushida, Teruo; Shiratori, Yoshitake

JAEA-Research 2013-029, 36 Pages, 2013/12

JAEA-Research-2013-029.pdf:2.7MB

In the areas contaminated by the Fukushima Daiichi Nuclear Power Plant accident, to clarify the influences of the lifestyle habits to radiation exposures for inhabitants, we performed surveys on their behavioral patterns and measurements of their individual doses due to external exposures. In addition, an assessment model was developed and the assessments of the doses were performed based on the results of the surveys and the measurements of ambient dose equivalent rates. The assessed individual doses were compared with those measured in order to confirm the validity of the model. Clear differences were found in time spent outdoors of the inhabitants of various occupations. Significant differences in individual doses were also observed between those of indoor workers and outdoor workers. In order to assess more precisely the doses of inhabitants who continue to live in the affected areas, assessments should be performed taking into account the population-specific behavioral patterns.

Journal Articles

Hydrogen production by high-temperature gas-cooled reactor; Conceptual design of advanced process heat exchangers of the HTTR-IS hydrogen production system

Sakaba, Nariaki; Ohashi, Hirofumi; Sato, Hiroyuki; Hara, Teruo; Kato, Ryoma; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 7(3), p.242 - 256, 2008/09

Nuclear hydrogen production is necessary in an anticipated hydrogen society that demands massive quantity of hydrogen without economic disadvantage. Japan Atomic Energy Agency (JAEA) has launched the conceptual design study of a hydrogen production system with a near-term plan to connect it to Japan's first high-temperature gas-cooled reactor HTTR. The candidate hydrogen production system is based on the thermochemical water-splitting iodine-sulphur (IS) process. The heat of 10 MW that approximately 900$$^{circ}$$C, which can be provided by the secondary helium from the intermediate heat exchanger of the HTTR, is the energy input to the hydrogen production system. The paper describes the recent progresses made in the conceptual design of advanced process heat exchangers of the HTTR-IS hydrogen production system. A new concept of sulphuric acid decomposer is proposed that integrates three separate functions of sulphuric acid decomposer, sulphur trioxide decomposer and process heat exchanger in the previous design. A new mixer-settler type of Bunsen reactor is also designed that integrates three separate functions of Bunsen reactor, phase separator, and pump in the previous design. The new concepts are expected to result in improved economics through construction and operation cost reductions because the number of process equipment and complicated connections between the equipment has been substantially reduced.

JAEA Reports

Structural concept design of the Bunsen reactor and sulphuric acid decomposer of the HTTR-IS hydrogen production system

Hara, Teruo; Sakaba, Nariaki; Sato, Hiroyuki; Ohashi, Hirofumi; Tachibana, Yukio; Kunitomi, Kazuhiko

JAEA-Technology 2008-020, 28 Pages, 2008/03

JAEA-Technology-2008-020.pdf:5.69MB

Since nuclear hydrogen production system should be economically competitive compared with other hydrogen production methods, it is important to reduce the construction cost of the IS process hydrogen production plant. Japan Atomic Energy Agency (JAEA) has started the conceptual design study of components in the IS process hydrogen production system to be connected with the HTTR (HTTR-IS system). This paper describes the additional proposal for the mixer-Settler type Bunsen reactor and combined sulphuric acid decomposer of the HTTR-IS system which enhances their performance and enables reduction of fabrication cost. The enhancements of the mixing and separating performance in the Bunsen reactor using static mixers with microbubble and dams, and minimizing the size of the combined sulphuric acid decomposer by optimizing its flow path remarkably contribute to the size reduction of components.

JAEA Reports

Conceptual design of the HTTR-IS hydrogen production system

Sakaba, Nariaki; Sato, Hiroyuki; Hara, Teruo; Kato, Ryoma; Ohashi, Kazutaka; Nishihara, Tetsuo; Kunitomi, Kazuhiko

JAEA-Research 2007-058, 31 Pages, 2007/08

JAEA-Research-2007-058.pdf:16.44MB

Since hydrogen produced by nuclear should be competitiveness economically compared by other method in a hydrogen society, it is important to built hydrogen production system to be coupled with the reactor as a conventional chemical plant. Japan Atomic Energy Agency started the safety study to establish a new safety philosophy with safety requirements and with considering non-nuclear grade hydrogen production system for the nuclear coupling system. Also, structural concepts with integrating functions for the Bunsen reactor and sulphuric acid decomposer were proposed to reduce construction cost of the IS process hydrogen production system. In addition, HI decomposer which enabled the process condition to be eased and could adopt conventional materials and technologies was studied. Moreover, basic approval of the HTTR-IS system in which the hydrogen production rate of 1,000 Nm$$^{3}$$/h by using the supplied heat of 10 MW from the intermediate heat exchanger of the HTTR was confirmed. This paper describes the conceptual design of the HTTR-IS hydrogen production system.

JAEA Reports

Case study on chemical plant accidents for flow-sheet design of the HTTR-IS system

Homma, Hiroyuki; Sato, Hiroyuki; Kasahara, Seiji; Ohashi, Hirofumi; Hara, Teruo; Kato, Ryoma; Sakaba, Nariaki

JAEA-Technology 2007-006, 60 Pages, 2007/02

JAEA-Technology-2007-006.pdf:15.91MB

At the present time, we are alarmed by depletion of fossil energy and adverse effect of rapid increase in fossil fuel burning on environment such as climate changes and acid rain, because our lives depend still heavily upon fossil energy. It is thus widely recognized that hydrogen is one of important future energy carriers in which it is used without emission of carbon dioxide greenhouse gas and atmospheric pollutants and that hydrogen demand will increase greatly as fuel cells are developed and applied widely in the near future. To meet massive demand of hydrogen, hydrogen production from water utilizing nuclear, especially by thermochemical water-splitting Iodine-Sulphur (IS) process utilizing heat from High-Temperature Gas-cooled Reactors (HTGRs), offers one of the most attractive zero-emission energy strategies and the only one practical on a substantial scale. However, to establish a technology based for the HTGR hydrogen production by the IS process, we should close several technology gaps through R&D with the High-Temperature Engineering Test Reactor (HTTR), which is the only Japanese HTGR built and operated at the Oarai Research & Development Centre of Japan Atomic Energy Agency (JAEA). We have launched design studies of the IS process hydrogen production system coupled with the HTTR (HTTR-IS system) to demonstrate HTGR hydrogen production. In designing the HTTR-IS system, it is necessary to consider preventive and breakdown maintenance against accidents occurred in the IS process as a chemical plant. This report describes case study on chemical plant accidents relating to the IS process plant and shows a proposal of accident protection measures based on above case study, which is necessary for flow-sheet design of the HTTR-IS System.

JAEA Reports

Building of nuclear ship engineering simulation system; Development of the simulator for the integral type reactor

Takahashi, Teruo; Shimazaki, Junya; Nakazawa, Toshio; Yabuuchi, Noriaki; Fukuhara, Yoshifumi*; Kusunoki, Tsuyoshi; Ochiai, Masaaki

JAERI-Tech 2000-039, p.94 - 0, 2000/03

JAERI-Tech-2000-039.pdf:4.0MB

no abstracts in English

Journal Articles

Submersible compact reactor SCR for under-sea research vessel

Odano, Naoteru; Kusunoki, Tsuyoshi; Yoritsune, Tsutomu; Fukuhara, Yoshifumi*; Saito, Kazuo*; Takahashi, Teruo*; Ishida, Toshihisa

Proceedings of International Workshop on Utilization of Nuclear Power in Oceans (N'ocean 2000), p.164 - 169, 2000/02

no abstracts in English

JAEA Reports

Experimental data report for test TS-4, Reactivity initiated accident test in the NSRR with pre-irradiated BWR fuel rod

Nakamura, Takehiko; ; Sobajima, Makoto; Ishijima, Kiyomi; ; Yamahara, Takeshi; ; Kikuchi, Teruo

JAERI-M 94-030, 103 Pages, 1994/03

JAERI-M-94-030.pdf:10.15MB

no abstracts in English

JAEA Reports

Experimental data report for test TS-3; Reactivity initiated accident test in the NSRR with pre-irradiated BWR fuel rod

Nakamura, Takehiko; ; Sobajima, Makoto; ; ; Yamahara, Takeshi; ; Kikuchi, Teruo

JAERI-M 93-183, 115 Pages, 1993/09

JAERI-M-93-183.pdf:13.73MB

no abstracts in English

JAEA Reports

Design study of fuel fabrication and test facility and post-irradiation examination facility for the development of new type fuels

Amano, Hidetoshi; ; Yamahara, Takeshi; ; Furuta, Teruo

JAERI-M 93-103, 75 Pages, 1993/05

JAERI-M-93-103.pdf:2.35MB

no abstracts in English

JAEA Reports

Experimental data report for test TS-2; Reactivity initiated accident test in NSRR with pre-irradiated BWR fuel rod

Nakamura, Takehiko; ; Sobajima, Makoto; ; ; Yamahara, Takeshi; ; Kikuchi, Teruo

JAERI-M 93-006, 101 Pages, 1993/02

JAERI-M-93-006.pdf:11.47MB

no abstracts in English

JAEA Reports

Pre-pulse irradiation examination, NSRR pulse irradiation and post-pulse irradiation examination of MH-2 fuel rod

Yanagisawa, Kazuaki; Katanishi, Shoji; *; Sasajima, Hideo; ; Horiki, Oichiro; Mimura, Hideaki; ; ; ; et al.

JAERI-M 92-015, 211 Pages, 1992/02

JAERI-M-92-015.pdf:8.77MB

no abstracts in English

JAEA Reports

Pre-pulse irradiation examination, NSRR pulse irradiation and post-pulse irraditaiton examination of MH-1 fuel rod

Yanagisawa, Kazuaki; Sasajima, Hideo; Katanishi, Shoji; *; ; Horiki, Oichiro; Mimura, Hideaki; ; ; ; et al.

JAERI-M 91-220, 186 Pages, 1992/01

JAERI-M-91-220.pdf:7.02MB

no abstracts in English

JAEA Reports

Experimental data report for test TS-1; Reactivity initiated accident test in NSRR with pre-irradiated BWR fuel rod

Nakamura, Takehiko; ; Sobajima, Makoto; ; Horiki, Oichiro; Yamahara, Takeshi; ; Kikuchi, Teruo

JAERI-M 91-217, 76 Pages, 1992/01

JAERI-M-91-217.pdf:4.58MB

no abstracts in English

Journal Articles

Fission density in plutonium-uranium mixed oxide fuel irradiated by pulsed power in the NSRR experiments

Yanagihara, Satoshi; ; Inabe, Teruo

Journal of Nuclear Science and Technology, 26(8), p.787 - 794, 1989/08

no abstracts in English

Journal Articles

Test of high-T$$_{c}$$ superconductor in a 2.7 GHz RF cavity

Okubo, Makio; Minehara, Eisuke; ; Kawarasaki, Yuki; Katano, Susumu; Takamura, Saburo; Kato, Teruo; Watanabe, Mitsuo; Naramoto, Hiroshi;

Proceedings of 12th Linear Accelerator Meeting in Japan, p.42 - 43, 1987/00

no abstracts in English

JAEA Reports

The First loading fuel elements and power-up for JRR-2

JRR-2 Control Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.

JAERI 1027, 57 Pages, 1962/09

JAERI-1027.pdf:4.76MB

no abstracts in English

JAEA Reports

Critical experiments and characteristic measurement for JRR-2

JRR-2 Critical Experiments Group; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.

JAERI 1025, 62 Pages, 1962/03

JAERI-1025.pdf:4.6MB

no abstracts in English

Oral presentation

Development of simulation system for vitrification melter, 2; Evaluation on physical behavior of the TVF melter during ordinary operation

Miura, Akihiko; Nakajima, Masayoshi; Yamashita, Teruo; Sakai, Takaaki; Shiotsuki, Masao; Sato, Akihiro*; Kawahara, Hitoshi*

no journal, , 

no abstracts in English

25 (Records 1-20 displayed on this page)