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Takahashi, Nobuo; Kubota, Shintaro; Takiya, Hiroaki; Sakaba, Ryosuke*; Sato, Koichi; Shichi, Ryo
JAEA-Testing 2021-002, 106 Pages, 2022/01
JAEA-Testing-2021-002.pdf:2.08MB
The Japan Atomic Energy Agency has various nuclear facilities such as reactor facilities and reprocessing facilities. Some aged facilities will be decommissioned after their original functions ended, and it is necessary to evaluate their decommissioning cost to formulate the initial decommissioning plans and the final decommissioning plans. We have developed an evaluation method called DECOST that can efficiently calculate the decommissioning cost in a short time based on factors such as features and similarity of the facilities and dismantling methods. The decommissioning of nuclear facilities has been implemented and new achievements and findings have been reported since the development of DECOST. These findings were reflected in DECOST. In consideration of the needs of DECOST users, DECOST has been improved so that the cost of dismantling the facility can be divided into the cost of releasing the controlled area and the cost of dismantling the facility building after the release of the controlled area. This report shows the improvement of DECOST, the concept of resetting the evaluation coefficient used in the cost evaluation formula, and the validity of the evaluation coefficient after resetting. In addition, the evaluation procedure of the improved DECOST is described, since the evaluation items and evaluation contents were partially changed due to the improvement.
Komeda, Masao; Toh, Yosuke; Tanabe, Kosuke*; Kitamura, Yasunori*; Misawa, Tsuyoshi*
Annals of Nuclear Energy, 159, p.108300_1 - 108300_8, 2021/09
Times Cited Count：2 Percentile：31.78(Nuclear Science & Technology)Yonomoto, Taisuke; Mineo, Hideaki; Murayama, Yoji; Hohara, Shinya*; Nakajima, Ken*; Nakatsuka, Toru; Uesaka, Mitsuru*
Nihon Genshiryoku Gakkai-Shi ATOMO
, 63(1), p.73 - 77, 2021/01
no abstracts in English
ionsShiina, Yoko*; Kinoshita, Ryo*; Funada, Shuhei*; Matsuda, Makoto; Imai, Makoto*; Kawatsura, Kiyoshi*; Sataka, Masao*; Sasa, Kimikazu*; Tomita, Shigeo*
Nuclear Instruments and Methods in Physics Research B, 460, p.30 - 33, 2019/12
Times Cited Count：2 Percentile：23.19(Instruments & Instrumentation)Takahashi, Nobuo; Suekane, Yurika; Sakaba, Ryosuke*; Kurosawa, Takuya*; Sato, Koichi; Meguro, Yoshihiro
JAEA-Testing 2018-002, 45 Pages, 2018/07
JAEA-Testing-2018-002.pdf:4.44MB
The Japan Atomic Energy Agency has many nuclear facilities such as research reactors, nuclear fuel facilities and research facilities. Although these facilities will be decommissioned due to the termination of the purpose of use of the facility and aging, it is necessary to evaluate the decommissioning cost of these facilities prior to the decommissioning. We have developed an evaluation method called DECOST code that can efficiently calculate the decommissioning cost in a short time based on factors such as features, similarity, and dismantling methods. This report is as a manual of the DECOST code prepared for improving convenience. Here, the evaluation formulae used for DECOST are presented and the method of using them is explained for each kind of nuclear facilities to be evaluated. In addition, the preparation method of facility information and dismantled waste amount that are need for evaluation is also shown.
plantsNomoto, Yasunobu; Horii, Shoichi; Sumita, Junya; Sato, Hiroyuki; Yan, X.
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 9 Pages, 2017/04
This paper presents the cost performance design of heat transport piping systems for GTHTR300C plant and HTTR-GT/H plant. Two types of pipe structure are designed and compared in terms of cost performance. Relative to the coaxial double-pipe structure, the insulated single pipe structure is found to have the advantage in overall cost performance considering both the material quantity and the heat loss because it reduces the quantity of steel used for construction. Furthermore it is possible to reduce the heat loss and temperature reduction of hot helium gas by the attachment of the external insulation. The pressure tube made of type-316 stainless steel with high-temperature strength is possible to achieve the same temperature reduction by smaller diameter than that made of 2 1/4Cr-1Mo steel. It contributes to the reduction of the quantity of steel. Specifications of heat transport piping systems for both plants are determined according to these study results.
Awual, M. R.; Yaita, Tsuyoshi; Shiwaku, Hideaki; Suzuki, Shinichi
Chemical Engineering Journal, 276, p.1 - 10, 2015/09
Times Cited Count：184 Percentile：98.61(Engineering, Environmental)Takei, Masanobu*; Kosugiyama, Shinichi*; Mori, Tomoaki; Katanishi, Shoji; Kunitomi, Kazuhiko
Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(2), p.109 - 117, 2006/06
no abstracts in English
Oshima, Soichiro; Shiraishi, Kunio; Shimada, Taro; Sukegawa, Takenori; Yanagihara, Satoshi
JAERI-Tech 2005-046, 46 Pages, 2005/09
JAERI-Tech-2005-046.pdf:3.43MB
A model for estimating decommissioning costs consisting of labor cost, device cost and expense, was developed for items which OECD/NEA had standardized, and was installed into the computer system for planning and management of reactor decommissioning (COSMARD). Input data files and databases for the decommissioning of JPDR were prepared, and the decommissioning cost was calculated with COSMARD. In addition, the decommissioning cost for a large scale BWR power plant was also calculated on the assumption of the advantage of scale. The calculations have shown that it is useful and efficient for studying the decommissioning costs for nuclear reactors to apply the COSMARD with database for cost estimation to the decommissioning cost calculation.
Nishihara, Tetsuo; Takeda, Tetsuaki
JAERI-Tech 2005-038, 40 Pages, 2005/07
JAERI-Tech-2005-038.pdf:5.01MB
R&D of the IS process technology and the integration technology of a high-temperature gas reactor and a heat utilization system is advanced by Japan Atomic Energy Research Institute. Hydrogen suuply system to fuel cell cars consists of off-site system and on-site system. The cost evaluation of on-site system must include the cost of storage, transportation, and refueling as well as that of production. Moreover, the hydrogen produced with the fossil fuel must consider the cost of carbon dioxide disposal. The cost evaluation data related to storage, transportaion and refueling in Japan and the USA are investigated. The cost evaluation of several off-site and on-siste systems are carried out.
Sato, Osamu
JAERI-Research 2005-012, 32 Pages, 2005/05
JAERI-Research-2005-012.pdf:4.37MB
A study was made on the evolution of energy demand and supply toward the year 2050 and on the potential benefits of nuclear energy utilization in Japan. For this purpose, assumptions were made on future economic growths, improvement in energy intensity, availability and costs of energy sources and energy technologies. Then, based on these assumptions, three cases of long-term energy scenarios were built with a different scale of nuclear energy utilization, and through their comparison possible role of nuclear energy was analyzed. It was indicated from this study that expansion of nuclear energy utilization will contribute to the reduction of fossil energy consumption, and therefore, enhancement of stable supply of energy and substantial reduction of carbon dioxide emissions with low economic costs.
Mizukoshi, Seiji; Oshima, Soichiro; Shimada, Taro
JAERI-Tech 2005-011, 122 Pages, 2005/03
JAERI-Tech-2005-011.pdf:13.25MB
The radiological and physical characteristic on decommissioning, such as component and structure weights and radioactivity of the 1.1 MWe class reference nuclear power plants summarized in the NUREG reports of the US NRC were classified,arranged and compared with the domestic commercial nuclear power plants and JPDR from a view point of dismantling plan and waste management for decommissioning. As the results, it was found that the radioactive component and structure weights was about 28,000ton、and non-radioactive structure weights was about 124,000ton less than the domestic commercial BWR. And it was found that this differences has mainly influenced dismantling costs for decommissioning. Farther, it was found that the concrete element composition rates of B, Ni, Nb and so were differerence of one or more figures btween the reference nuclear power plants and the domestic commercial PWR or JPDR.Also,it was found that the this difference became about two or three times by radioactivity concentration and has mainly influenced transport and disposal costs for decommissioning.
Hirota, Koichi; Sakai, Hiroki*; Washio, Masakazu*; Kojima, Takuji
Industrial & Engineering Chemistry Research, 43(5), p.1185 - 1191, 2004/03
Times Cited Count：46 Percentile：79.46(Engineering, Chemical)Twenty volatile organic compounds (VOCs) were irradiated with electron beams in laboratory scale to obtain an electron-beam energy required for a 90% treatment. The experiments showed that the energy was related with the chemical structure and roughly estimated from rate constants for reactions with OH radicals. The cost analysis revealed that the unification of a self-shielding electron accelerator with a reactor could reduce the capital cost for an electron-beam system. Electron-beam technology is a promising method for the treatment of VOCs.
Takei, Masanobu; Katanishi, Shoji; Kunitomi, Kazuhiko; Izumiya, Toru*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.490 - 499, 2003/12
no abstracts in English
Uotani, Masaki*; Shimizu, Takao*; Tamada, Masao
Proceedings of 2003 International Congress on Advances in Nuclear Power Plants (ICAPP '03) (DVD-ROM), 8 Pages, 2003/00
The present paper describes the current technology of uranium recovery from seawater by using radiation-induced graft-adsorbent and the utilization scenario of collected uranium from the viewpoint of long-term perspective of nuclear energy demand in Japan. The several thousand tons of uranium will be required in the latter half of 21st century in Japan, even if the plutonium is practically used in fast breeder reactors (FBRs). This demand of uranium can be supplied by the uranium recovered from seawater if the recovery cost is reasonable. In conclusion, the utilization of uranium from seawater will be able to play an essential role of providing enough time to develop safe and economical FBRs.
Katanishi, Shoji; Kunitomi, Kazuhiko; Takei, Masanobu; Nakata, Tetsuo; Watanabe, Takashi*; Izumiya, Toru*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.373 - 383, 2002/12
no abstracts in English
Yanagihara, Satoshi
Dekomisshoningu Giho, (25), p.2 - 11, 2002/03
no abstracts in English
Nakatsuka, Toru; Ishikawa, Nobuyuki; Iwamura, Takamichi
JAERI-Conf 2001-013, 263 Pages, 2001/09
JAERI-Conf-2001-013.pdf:13.37MB
The research on Reduced-Moderation Water Reactors (RMWRs) has been performed in JAERI for the development of future innovative reactors. The 4th workshop on the RMWRs was held on March 2, 2001 aimed at information exchange between JAERI and other organizations. This report includes the eight original papers presented at the workshop and summaries of the questions and answers for each lecture. Titles of the papers are“Recent Situation of Research on Reduced-Moderation Water Reactor“, “Analysis on Electricity Generation Costs of Reduced Moderation Water Reactors“,“Reprocessing Technology for Spent Mixed-Oxides Fuel from LWR“,“Micro Reactor Physics of MOX Fueled LWR“, “Fast Reactor Cooled by Supercritical Light Water “, “Phase 1 of Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System“, “Integral Type Small PWR with Stand-alone Safety“ and “Utilization of Plutonium in Reduced-Moderation Water Reactors“.
Miyamoto, Yoshiaki; Ogawa, Masuro; Akino, Norio; Shiina, Yasuaki; Inagaki, Yoshiyuki; Shimizu, Saburo; Onuki, Kaoru; Ishiyama, Shintaro; Katanishi, Shoji; Takeda, Tetsuaki; et al.
JAERI-Review 2001-006, 147 Pages, 2001/03
JAERI-Review-2001-006.pdf:9.2MB
no abstracts in English
Department of Decommissioning and Waste Management
JAERI-Review 2000-013, 49 Pages, 2000/09
JAERI-Review-2000-013.pdf:3.26MB
no abstracts in English
