著者

菅原 慎悦 城山 英明

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan (ISSN:13472879)

巻号頁・発行日

vol.9, no.4, pp.368-383, 2010-12-01

被引用文献数

1 2

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In France, there exist organizations called "Commission Locale d'Information" (CLI) in all the siting areas where nuclear facilities located. Previously, the CLI organizations were established voluntarily by some local governments or nuclear utilities. Since 2006, however, the Nuclear Transparency and Safety Act has obliged the establishment of CLI in all the siting areas in conjunction with reforming the nuclear regulatory agencies. This means that the concerned local governments are officially part of nuclear safety regulation. In this study, we investigated present conditions of the CLI organizations through some interviews in France and consider their roles from the standpoint of nuclear regulatory governance. As a result, we found that the CLI plays the following roles: (1) medium of communication among concerned parties (not only between nuclear utilities and local habitants but also between the national nuclear regulatory agency and various local governments) and (2) implementing various activities in accordance with each local condition through the participation of local assembly members. In addition, we clarified that CLI's activities are supported by related institutional infrastructures, such as cost burden between central and local governments, and some other systems of citizen participation in building or expanding nuclear facilities.<br>

著者

中田 翔治 高嶋 隆太 長野 浩司 木村 浩 班目 春樹

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan (ISSN:13472879)

巻号頁・発行日

vol.9, no.3, pp.252-270, 2010-09-01

被引用文献数

3

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Replacement of nuclear power plants has the possibility of affecting the management of electric power suppliers. Therefore, in the nuclear policy, a depreciation method as an equalization method, which means that part of the investment cost is accumulated as an allowance, and after the start of operation, the depreciation cost in the replacement project is equalized, has been introduced in Japan. In this paper, we evaluate the replacement of nuclear power plants by taking into account the uncertainty of operating costs and the depreciation cost in order to examine the effect of the depreciation method on the decision criteria of the replacement. We found that the equalization method is effective for inducing the acceleration of the replacement. Furthermore, we show the relationship between the uncertainty and the depreciation method. It turns out that as uncertainty increases, the difference in investment threshold between the equalization method and the existing depreciation method decreases, and that in option value increases.<br>

著者

芳中 一行 大塚 正弘 星野 昌人 菊池 憲治 河田 剛 滝 清隆

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan (ISSN:13472879)

巻号頁・発行日

vol.7, no.3, pp.268-279, 2008-09-01

参考文献数

9

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&nbsp;&nbsp;Fluorescent liquid penetrant test equipment, for testing welded parts of the evaporator for phosphate liquid waste generated by solvent waste treatment at Tokai Reprocessing Plant, was developed. It is composed of a CCD camera and UV light for observation, nozzles for fluorescent liquid, water for washing, and air for drying, and a positioning mechanism that can adjust the position of this equipment relative to the inspection object by three-axis operation, varying the insert length, bending angle and turn angle. Also, the equipment can be inserted by way of the nozzle for inspection, whose inside diameter is 60 mm, into the evaporator. It was confirmed that the standard faults, as defined in JIS, could be observed by the equipment. Then, a fluorescent liquid penetrant test of an evaporator that has treated phosphate liquid waste for 18 years with a heating temperature of about 105&deg;C was performed. The result of the test indicates the absence of faults in the evaporator.<br>

著者

土田 辰郎 木村 浩

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan (ISSN:13472879)

巻号頁・発行日

vol.10, no.4, pp.332-346, 2011-12-01

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Taking into consideration the influence of the media coverage, this research aims to analyze the characteristics of the local newspapers that cover diverse events relevant to nuclear energy in regional areas where nuclear facilities are located (hereinafter called the "region"). According to the previous surveys, local residents in the region are more interested in the nuclear energy matters than those who live in urban areas. Plus, the local newspapers turn out to report more events of nuclear energy from a variety of angles. Through interviews with executives and journalists of the local newspaper companies in the regions, it is revealed that the local newspapers tend not to report news sensationally, but they would rather take a supportive stance toward the development in their regions. The interviewees hope that various activities of the nuclear industry will promote education, employment and cooperation among government, industry and academia. They also desire that the industry's activities will help to increase benefits in their regions. It appears that the interviewees' awareness reflects articles of the local newspapers. As a result of the surveys conducted for this research, it is considered that the journalists expect that their region will make particularly qualitative progress in the future.<br>

著者

濱本 真平 坂場 成昭 竹田 陽一

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan (ISSN:13472879)

巻号頁・発行日

vol.9, no.2, pp.174-182, 2010-06-01

被引用文献数

1

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It is important to control the chemistry of the helium coolant used in high-temperature gas-cooled reactors (HTGRs). The effect of a decarburizing environment on the creep rupture properties tends to decrease the creep rupture life of the heat-resistant alloy used in heat exchangers. In this paper, we describe an active control method for the concentration of impurities using the existing helium purification system, which consists of a helium heater, a copper oxide trap (CuOT), a molecular sieve trap, a cold charcoal trap, and a bypass line. Analysis showed that the efficiency control of CuOT is effective in improving the decarburizing atmosphere. The efficiency control of CuOT increases the concentrations of carbon monoxide and hydrogen. It was found that both the enrichment of carbon monoxide suggested in previous studies and the enrichment of hydrogen are also effective in forming the carburizing atmosphere.<br>

著者

加藤 尊秋 八田 昌久 西川 雅史 松本 史朗

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan (ISSN:13472879)

巻号頁・発行日

vol.6, no.4, pp.404-420, 2007-12-25

被引用文献数

3

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Although dwellers living near a nuclear power station are entitled to economic/financial benefits such as increased job opportunities and local tax revenues pertaining to the power station, it is not clear whether such benefits are appreciated by the dwellers. Two findings of this study based upon a social survey of local dwellers living near the Kashiwazaki-Kariwa Nuclear Power Station are summarized as follows. First, an increase in the per capita sizes of the local tax revenue and national subsidies resulted in a larger share of respondents who thought that those revenues are beneficial. Therefore, local dwellers are aware of the sizes of economic/financial benefits. Second, given the same risk level of nuclear disaster, a larger per capita financial benefit resulted in a larger share of respondents who felt compensated for the nuclear risk. However, this increase in the number of compensated respondents is low relative to the increase in the amount of financial benefits.<br>

著者

篠田 佳彦 山野 直樹 鳥井 弘之

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan (ISSN:13472879)

巻号頁・発行日

vol.7, no.4, pp.350-369, 2008-12-01

被引用文献数

1

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The social research group of the 21st century COE program "Innovative Nuclear Energy Systems for Sustainable Development of the World" has studied under the theme coevolution of nuclear technology and society. As part of this study, this group conducted a questionnaire survey of 2,500 adults (collection rate of 22.0%; 551 replies) who live in the Tokyo metropolitan area. The purpose of this survey asking opinion about the relationship between attitude toward nuclear technology utilization and social awareness is to determine their request, exception and concern about nuclear technology utilization. The survey reveals that the differences of attitudes towards nuclear technology utilization can be explained in terms of differences of general views on the society, such as the directionality of social progress. Thus, it is necessary to argue with citizens about the strategy on nuclear technology utilization from the viewpoint of the directionality of the future society. The social decision-making process on nuclear technology utilization has to be renovated through dialogue among citizens as the partner taking on the achievement and contribution toward the directionality of the future society.<br>

著者

三田地 紘史 山本 高久 吉岡 律夫 杉本 哲也

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan (ISSN:13472879)

巻号頁・発行日

vol.7, no.2, pp.127-133, 2008-06-01

被引用文献数

1 7

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In this paper, the burn-up characteristics of a 200 MW_e molten-salt reactor are studied. This reactor has a three-region core in order to reduce the peak in fast neutron flux distribution. The reactor is operated for 30 years with the load factor of 0.75. The fuel is fed to the reactor every 33 days. The chemical processing of the fuel salt is performed every 7.5 years. Based on calculations using the nuclear analysis code SRAC2006 and the burn-up analysis code ORIGEN2, the following results have been obtained. (1) The graphite moderators can be used throughout the reactor lifetime without replacement. (2) The reactor is self-sustainable having an average fuel conversion ratio of 1.01. (3) The initial inventory of ²³³U is 1.13 t, net feed in 30 years is 0.34 t; thus, the necessary amount of ²³³U is 1.48 t. (4) Pu isotopes are produced at 1.5 kg and minor actinides at 27 kg per 1 GWe output in 30 years, which are absolutely small compared with those produced by BWR.<br>