著者

大越 実 鳥井 弘之 藤井 靖彦

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 (ISSN:13472879)

巻号頁・発行日

vol.6, no.4, pp.421-433, 2007 (Released:2012-03-07)

参考文献数

15

被引用文献数

2 2

---

Siting of radioactive waste management facilities frequently raise arguments among stakeholders such as a municipal government and the residents. Risk communication is one of the useful methods of promoting mutual understanding on related risks among stakeholders. In Finland and Sweden, siting selection procedures of repositories for spent nuclear fuels have been carried out successfully with risk communication. The success reasons are analyzed based on the interviews with those who belong to the regulatory authorities and nuclear industries in both countries. Also, in this paper, risk communication among the Japan Radioisotope Association (JRIA), a local government and the general public, which was carried out during the establishment process of additional radioactive waste treatment facilities in Takizawa Village, Iwate Prefecture, is analyzed based on articles in newspapers and interviews with persons concerned. The analysis results showed that good risk communication was not carried out because of the lack of confidence on the JRIA, decision making rules, enough communication chances and econmic benefits. In order to make good use of these experiences for the future establishment of radioactive waste management facilities, the lessons learned from these cases are summarized and proposals for good risk communication (establishment of exploratory committee and technical support system for decision making, and measurements to increase familiarity of radioactive waste) are discussed.

著者

和田 隆太郎 田中 知 長崎 晋也

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 (ISSN:13472879)

巻号頁・発行日

vol.8, no.1, pp.19-33, 2009 (Released:2012-02-22)

参考文献数

28

被引用文献数

4 4

---

Generally speaking, a vast, advanced and unfamiliar science and technology are unacceptable to the public for fear of their unknown nature. Here, the social acceptance process model was examined on the basis of the analysis of the cause phenomenon and numerical grounds, by referring to the problems on the application of literature documentation for location examination of a high-level radioactive waste disposal site in Toyo town in Kochi Pref. in April 2007. In analyzing the Toyo town case, we have found a possibility that the majority of local residents knew very little about the object opposed by the fringe route processing. To ensure a healthy decision making by the public, it is vital to convey fundamental information using sufficient wide-area PR media before the issue becomes actual. After the issue becomes actual, dialog with residents through a careful technology assessment is indispensable. The authors focus attention on the decision-making process of human beings from the social and psychological viewpoints, and point out that it is desirable for promoting social acceptance by adopting two approaches: a direct approach aiming at better intelligibility for the different resident layers and a deductive approach in technological essence.

著者

八木 絵香 高橋 信 北村 正晴

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 (ISSN:13472879)

巻号頁・発行日

vol.6, no.4, pp.444-459, 2007 (Released:2012-03-07)

参考文献数

17

被引用文献数

2 5

---

An action research project called dialogue forum has been conducted in this study. The essential constituent of the project is a series of repetitive dialogue sessions carried out by lay citizens, nuclear experts, and a facilitator. One important feature of the project is that the study has been conducted based on the qualitative research methodology. The changes in opinions and attitude of the dialogue participants have been analyzed by an ethno-methodological approach. The observations are summarized as follows. The opinions of the citizen participants showed a significant shift from emotional to practical representations along with the progression of the dialogue sessions. Meanwhile, their attitude showed a marked tendency from problem-statement-oriented to problem-solving-oriented representation. On the other hand, the statements of the expert participants showed a significant shift from expert-based to citizen-based risk recognition and description, and their attitude showed a clear tendency from teaching-oriented to colearning-oriented thinking. These changes of opinions and attitude have been interpreted as a coevolving rather than a single process. It can be stressed that this type of change is most important for the reestablishment of mutual trust between the citizens and the nuclear experts. In this regard “The Process Model of Coevolution of Risk Recognition” has been proposed as a guideline for developing a new scheme of public communication concerning nuclear technology. The proposed process model of coevolution of risk recognition is regarded to be essential for appropriate relationship management between nuclear technology and society in the near future.

著者

山田 英司

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 (ISSN:13472879)

巻号頁・発行日

vol.6, no.4, pp.383-392, 2007 (Released:2012-03-07)

参考文献数

27

被引用文献数

3 3

---

In response to the recent structural imbalance of oil supply and demand, Japan has placed energy security at the top agenda of its energy policies. A review of the energy security level has importance in formulating and steering energy policies. Although energy security meant national energy security that puts the main priority on a stable energy supply, we are now required to consider energy security from wider viewpoints of global energy security, which includes environment, nuclear concerns, international relations and others as its priority aspects. This report is prepared to suggest a method of estimating energy security level in a quantitative manner. In this method, Japan's energy supply and demand structure is evaluated on the selected aspects and indexes as standard deviation among eight advanced nations and one area. The aspects and indexes include energy consumption, environment and economics as well as energy supply. The outcomes prepared by this method show that Japan is now placed at a lower position than most advanced nations and area, although its energy security level has been improved mainly with the contribution of the diversification of energy supply sources. The estimation also shows that Japan's energy security could improve until the portion of nuclear energy in the power supply reaches around 60% on the assumption of its present energy supply and demand structure. The future task is to determine the aspects and indexes to be picked up or the possible weight to be distributed among the aspects and indexes in response to the situations surrounding energy.

著者

大越 実 鳥井 弘之 藤井 靖彦

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 (ISSN:13472879)

巻号頁・発行日

vol.6, no.4, pp.393-403, 2007 (Released:2012-03-07)

参考文献数

29

---

Clearance is one of the useful concepts to manage large amounts of slightly contaminated solid radioactive materials generated from the decommissioning of nuclear facilities. Cleared materials are expected to be disposed of as conventional wastes or recycled to produce consumer goods. In Japan, the legal framework for clearance was established in 2005 by amending the Law to regulate nuclear materials, reactors and so on. However, it is not so clear whether the general public understands clearance well. In this paper, major concerns about clearance from the general public are analyzed based on the public comments for reports on clearance prepared by the Nuclear Safety Commission and the Nuclear Institute Safety Agency. The major anxieties for clearance expressed by the general public are the safety of clearance, unknown factors of radiation effects, possibilities of excess radiation exposure due to inadequate measurements of radioactivities and fairness in decision making. In order to deal with those anxieties, some countermeasures including the confidence in nuclear operators and regulatory authorities and controllability of clearance by the general public are discussed to promote the social acceptance of clearance by the general public.

著者

木村 浩 田中 博 勝村 聡一郎 古田 一雄

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 (ISSN:13472879)

巻号頁・発行日

vol.8, no.3, pp.197-210, 2009 (Released:2012-02-22)

参考文献数

24

被引用文献数

2 2

---

Risk communication about high-level radioactive waste (HLW) disposal is necessary for public acceptance of the HLW disposal program in Japan. To support risk communication, we developed the Online Risk Communication Assistant Tool (ORCAT) system on the World Wide Wed (WWW). In this research, we analyzed the changes in participants' attitudes to HLW disposal through the test operation of the ORCAT system. We carried out the test operation of the ORCAT system from Oct. 29 to Dec. 12, 2005. One hundred fifty nonexpert participants, five experts, and two facilitators participated in this operation. To measure the changes in participants' attitudes to a HLW disposal program, we carried out web questionnaires before and after the test operation. Consequently, we found that most of the participants exhibited on increased level of concern about HLW as well as increased understanding regarding the necessity of HLW disposal. Nonetheless, they did not necessarily reduced their perceived risk of HLW disposal. In addition, we also found that the active participants drew conclusions based on thorough review of the information that experts posted on the ORCAT system, while the inactive participants made decisions primarily based on the context of the information presented on the ORCAT system.

著者

井上 尚子 久野 祐輔

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 (ISSN:13472879)

巻号頁・発行日

vol.9, no.3, pp.305-317, 2010 (Released:2012-02-08)

参考文献数

56

被引用文献数

2 2

---

The fabrication of fast neutron reactor cycles is intended for next-generation nuclear energy systems. This is in line with the fact that the amount of plutonium, which should be reprocessed, increases significantly. Techniques for increasing the nuclear proliferation resistance, especially extrinsic measures including safeguards, are essential for such systems to be accepted by the international community. A highly resistant system with a high detection capability, as well as satisfying current safeguards requirements, was studied for an advanced aqueous reprocessing, and its technical practicability and operational compatibility were discussed. The effect of the proposed safeguards system in this paper was evaluated using the Markov model approach developed by the GIF Proliferation Resistance and Physical Protection Working Group (PR & PP WG). The proposed safeguards system includes a high-detection-capability system and the accountancy/verification measures based on the monthly interim inventory taking or verification that should be performed at a similar level of quality to the normal physical inventory verification with very little impact to the practical plant operation. This can only be realized with “safeguards by design.”

著者

中田 翔治 高嶋 隆太 長野 浩司 木村 浩 班目 春樹

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 (ISSN:13472879)

巻号頁・発行日

vol.9, no.3, pp.252-270, 2010 (Released:2012-02-08)

参考文献数

16

被引用文献数

1 3

---

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.

著者

菅原 慎悦 城山 英明

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 (ISSN:13472879)

巻号頁・発行日

vol.9, no.4, pp.368-383, 2010 (Released:2012-02-08)

参考文献数

35

被引用文献数

2 2

---

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.

著者

島田 隆 松井 嶺迪 西村 正史 石田 安弘 森 行秀 黒田 一彦

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 (ISSN:13472879)

巻号頁・発行日

vol.10, no.4, pp.310-322, 2011 (Released:2011-11-30)

参考文献数

6

---

This paper discusses the reprocessing plant concept suitable for the transition period from the Light Water Reactors (LWRs) to the Fast Breeder Reactors (FBRs). This transition requires the reprocessing of spent fuels in order to supply an adequate volume of fissile plutonium (Pu-fissile) for the FBRs. The transition period would continue for more than 60 years, and the reprocessing plant should match with the change in the power generation plan during the transition period. The ability to supply Pu-fissile has been evaluated for two plant concepts. One is the independent-type concept, which contains two processes for reprocessing either LWR or FBR fuels. The other is the modularized-type concept, which contains only one process for reprocessing both the LWR and FBR fuels. The result showed the superiority of the modularized-type concept over the independent-type concept, because the former can enhance the ability to supply Pu-fissile with less reprocessing capacity. Therefore, the reprocessing plant suitable for the transition period is that based on the modularized-type concept.

著者

鳥飼 誠之 小澤 通裕 鐘ヶ江 直道 谷 雅明 班目 春樹 宮越 直樹

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 (ISSN:13472879)

巻号頁・発行日

vol.9, no.4, pp.347-359, 2010 (Released:2012-02-08)

参考文献数

12

被引用文献数

1 2

---

On March 30, 2007, Japan's electric utilities reported the results of a complete review of their power-generating units to the Nuclear and Industrial Safety Agency of the Ministry of Economy, Trade, and Industry (METI). The Ethics Committee of the Atomic Energy Society of Japan (AESJ) then recommended an assessment method to analyze the seriousness of the problems from multiple perspectives in order to support the public's understanding of the reported problems. Accordingly, the Ethics Committee conducted the assessment. The assessment considered each reported problem associated with nuclear power-generating units and the preventive measures completed between June 2007 and September 2008 (corrective measures continued beyond that period). The results were presented at the autumn conferences of AESJ in 2007 and 2008, and are discussed in this report.

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.2, no.11, pp.705-707, 1960-11-30 (Released:2009-02-12)

著者

柴田 俊一

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.26, no.3, pp.211-216, 1984-03-30 (Released:2009-04-21)

---

National Committee for Nuclear Energy Research, Japan Science Council has completed a future plan for basic nuclear energy research by university researchers. The JSC has recommended the promotion of basic research for nuclear energy based on the plan in 1983. The future plan consists of four main research fields, namely, (1) improvements of reactor safety, (2) down stream, (3) thorium fuel reactors, and (4) applications of research reactor and radioisotopes.

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.1, no.5, pp.340-342, 1959-10-30 (Released:2009-02-12)

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.1, no.5, pp.342a-342a, 1959 (Released:2009-02-12)

著者

東 哲史 多久島 秀 林 真照 西沢 博志 仲嶋 一 猪又 憲治 中西 正一 渡辺 幸信

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 年会・大会予稿集 2013年春の年会

巻号頁・発行日

pp.84, 2013 (Released:2013-07-31)

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食品中の放射能を高速に測定する装置を開発中である。従来は、検出効率の低さから測定精度の確保に多大な測定時間を要していた。測定の高速化には、アンフォールディング手法を適用するが、測定値の信頼性を確保するには、測定ばらつきによる誤差を抑制する必要がある。そこで、品質工学を用いて安定な出力が得られる装置を設計した。

著者

坂本 文徳 大貫 敏彦 香西 直文 山崎 信哉 吉田 善行 難波 謙二

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 (ISSN:13472879)

巻号頁・発行日

vol.12, no.4, pp.257-266, 2013 (Released:2013-11-15)

参考文献数

20

被引用文献数

4 5

---

The local area distribution and relocation of radioactive cesium deposited in trees after the 2011 tsunami-related accident at the Fukushima Daiichi Nuclear Power Plant (FDNPP) have been studied by measuring the spatial distribution of cesium on/in trees by autoradiography analysis. Samples of trees were collected from places located between 4 and 55 km from FDNPP approximately 2, 8, 20, and 22 months after the accident. The autoradiography analyses of Cryptomeria japonica, Torreya nucifera, and Thujopsis dolabrata var. hondae samples collected approximately 2 and 8 months after the accident showed that radioactive Cs was mainly distributed as spots on the branches and leaves of the trees emerged before the accident, and was detected in negligible amounts in new branch and leaves that emerged after the accident. On the contrary, radioactive Cs was detected at the outermost tip of the branches in the trees collected 20 months after the accident. Morus alba samples collected 22 months after the accident contained radioactive Cs inside and outside their stems, even though no radioactive Cs was detected in their roots, strongly suggesting that a certain amount of radioactive Cs was translocated from the outside to the inside of stems. These results indicate that the distribution of radioactive Cs deposited on/in the trees gradually changes with time (scale: year).

著者

白井 孝治 伊藤 千浩 加藤 安久 服部 清一 三枝 利有 大沼 博志

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.37, no.5, pp.430-441, 1995-05-30 (Released:2010-01-08)

参考文献数

13

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Cask-storage is the best method for storing spent fuels at a reactor site. It is necessary to confirm the integrity of a cask subjected to impact load caused by cask mishandling drop accident because it is one of the technical issues to be considered in the safety analysis for cask and storage house. In this paper, an evaluation method of the dynamic interaction between cask and floor of the Storage facility Subjected to impact load is proposed. Firstly, the cask drop tests onto the reinforced concrete slab representing floor of the storage facility were conducted. Test results showed that the structural integrity of the cask was maintained even under impact load due to free drop caused by mishandling of cask. Secondly, drop analysis was performed using a finite element method analysis code considering concrete model developed at our laboratory, and compared with the experimental results. As a result, the applicability of this code for drop impact analysis of the cask was confirmed.

著者

吉村 忍 小林 敬 秋葉 博 鈴木 智 荻野 正雄

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 (ISSN:13472879)

巻号頁・発行日

vol.11, no.3, pp.203-221, 2012 (Released:2012-08-15)

参考文献数

17

被引用文献数

3 7

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In this paper, we present the three-dimensional finite element seismic response analysis of the full-scale boiling water reactor BWR5 at the Kashiwazaki-Kariwa Nuclear Power Plant subjected to the Niigata-ken Chuetsu-Oki (NCO) earthquake that occurred on 16th July 2007. During the earthquake, the automatic shutdown of the reactors was performed successfully. Although the monitored seismic acceleration significantly exceeded the design level, it was found through in-depth investigation that there was no significant damage of the reactor cores or other important systems, structures and components (SSCs). In the seismic design commonly used in Japan, a lumped mass model is employed to evaluate the seismic response of SSCs. Although the lumped mass model has worked well so far for a seismic proof design, more precise methods should be developed to understand response behaviors visually. In the present study, we propose the three-dimensional finite element seismic response analysis of the full-scale and precise BWR model in order to directly visualize the dynamic behaviors of this model. Through the comparison of the analysis results, we discuss the characteristics of both models. The stress values were also found to be generally under the design value.

著者

柳 千裕 村瀬 道雄 吉田 至孝 楠木 貴世志

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 (ISSN:13472879)

巻号頁・発行日

vol.11, no.3, pp.193-202, 2012 (Released:2012-08-15)

参考文献数

12

---

A prediction method for water temperature in a spent fuel pit of a PWR has been developed to calculate the increase in water temperature during the shutdown of cooling systems. In this study, the prediction method was extended to calculate the water level in a spent fuel pit during loss of all AC powers, and predicted results were compared with data of spent fuel pools in the Fukushima Daiichi Nuclear Power Station. The calculations gave reasonable results, but overestimated the decreasing rate of the water level and water temperature. This result indicated that decay heat was overestimated and evaporation heat transfer from the water surface was underestimated. Results of calculations with 80% decay heat and 155% (No. 4 pool) or 230% (No. 2 pool) evaporation heat flux were in good agreement with data. The data-fitted evaporation heat fluxes agreed rather well with the evaporation heat transfer correlation proposed by Fujii et al.