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Izumo, Sari; Usui, Hideo; Kubota, Shintaro; Tachibana, Mitsuo; Kawagoshi, Hiroshi; Takahashi, Nobuo; Morimoto, Yasuyuki; Tokuyasu, Takashi; Tanaka, Yoshio; Sugitsue, Noritake
JAEA-Technology 2014-021, 79 Pages, 2014/07
JAEA-Technology-2014-021.pdf:22.8MB
Japan Atomic Energy Agency has developed PROject management data evaluation code for DIsmantling Activities (PRODIA) to make an efficient decommissioning for nuclear facilities. PRODIA is a source code which provides estimated value such as manpower needs, costs, etc., for dismantling by evaluation formulas according to the type of nuclear facility. Evaluation formulas of manpower needs for dismantling of equipments about reprocessed uranium conversion in Uranium Refining and Conversion Plant are developed in this report. In the result, 7 formulas for prepare process, 24 formulas for dismantling process and 8 formulas for clean-up process are derived. It is confirmed that an unified evaluation formula can be used instead of 8 formulas about dismantling process of steel equipment for uranium conversion process, and 3 types of simplified formula can be used for preparation process and clean-up process respectively.
Sugitsue, Noritake; Morimoto, Yasuyuki; Tokuyasu, Takashi; Tanaka, Yoshio
Nihon Genshiryoku Gakkai Wabun Rombunshi, 12(3), p.242 - 256, 2013/09
This technical report showed the situation of the dismantling of the main equipment in the radiation controlled area of a uranium refining and conversion plant. And, the dismantling which we did is the work of the beginning of a uranium refining and conversion plant decommissioning project. We started dismantling in April 2008, and finished dismantling of the main equipment in a radiation controlled area in 29 September 2011. The dismantling waste and equipment was stored in the 200 little drum. All the contamination equipment can be sealed and kept in this stage. The radioactivity inventory of a uranium refining and conversion plant does not change in this stage. However, the risk of contamination by aged deterioration of this facility became remarkable small. Moreover, we were able to get many information and experience about dismantling.
Izumo, Sari; Usui, Hideo; Tachibana, Mitsuo; Morimoto, Yasuyuki; Takahashi, Nobuo; Tokuyasu, Takashi; Tanaka, Yoshio; Sugitsue, Noritake
Proceedings of 15th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2013) (CD-ROM), 9 Pages, 2013/09
Times Cited Count：0 Percentile：0.00(Engineering, Environmental)Ueno, Takashi; Tokuyasu, Shingo; Kawamoto, Koji; Kuboshima, Koji; Ishibashi, Masayuki; Tsuruta, Tadahiko; Sasao, Eiji; Ikeda, Koki; Mikake, Shinichiro; Hara, Ikuo; et al.
JAEA-Data/Code 2012-008, 136 Pages, 2012/07
JAEA-Data-Code-2012-008.pdf:27.39MBJAEA-Data-Code-2012-008(errata).pdf:1.55MB
JAEA-Data-Code-2012-008-appendix(DVD-ROM)-1.zip:790.9MBJAEA-Data-Code-2012-008-appendix(DVD-ROM)-2.zip:834.48MBJAEA-Data-Code-2012-008-appendix(DVD-ROM)-3.zip:533.98MBJAEA-Data-Code-2012-008-appendix(DVD-ROM)-4.zip:712.56MBJAEA-Data-Code-2012-008-appendix(DVD-ROM)-5.zip:525.5MB
This report compiles data of results from borehole investigations which has been carried out research gallery of Mizunami Underground Research Laboratory (MIU) in the fiscal year from 2005 to 2011. These data include results of core observation, geophysical logging, and so on.
Kunimaru, Takanori; Mikake, Shinichiro; Nishio, Kazuhisa; Tsuruta, Tadahiko; Matsuoka, Toshiyuki; Ishibashi, Masayuki; Ueno, Takashi; Tokuyasu, Shingo; Daimaru, Shuji; Takeuchi, Ryuji; et al.
JAEA-Review 2012-020, 178 Pages, 2012/06
JAEA-Review-2012-020.pdf:33.16MB
Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is pursuing a geoscientific research and development project namely the Mizunami Underground Research Laboratory (MIU) Project in crystalline rock environment in order to construct scientific and technological basis for geological disposal of High-level Radioactive Waste (HLW). The MIU Project has three overlapping phases: Surface-based Investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III). The MIU Project has been ongoing the Phase II. And Phase III started in 2010 fiscal year. This report shows the results of the investigation, construction and collaboration studies in fiscal year 2010, as a part of the Phase II based on the MIU Master Plan updated in 2002.
Tsuruta, Tadahiko; Takeda, Masaki; Ueno, Takashi; Daimaru, Shuji; Tokuyasu, Shingo; Onoe, Hironori; Shingu, Shinya; Ishibashi, Masayuki; Takeuchi, Ryuji; Matsuoka, Toshiyuki; et al.
JAEA-Technology 2012-001, 134 Pages, 2012/03
JAEA-Technology-2012-001.pdf:41.2MBJAEA-Technology-2012-001(errata).pdf:0.44MBJAEA-Technology-2012-001-appendix(CD-ROM).pdf:6.37MB
Tono Geoscientific Research Unit of Japan Atomic Energy Agency (JAEA) is performing the Mizunami Underground Research Laboratory (MIU) project in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in fractured crystalline rock. The borehole investigations (two boreholes; 10MI22 borehole and 10MI23 borehole) have been carried out to obtain information on geological, hydrological and hydrochemical characteristics in and around the Main-shaft fault. These investigations provided that features of fracture and alteration on rock mass in and around the Main-shaft fault. Hydrological and hydrochemical properties based on the geological features were also obtained.
Usui, Hideo; Izumo, Sari; Shibahara, Yuji; Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Tanaka, Yoshio; Sugitsue, Noritake; Tachibana, Mitsuo
Proceedings of International Waste Management Symposia 2012 (WM2012) (CD-ROM), 13 Pages, 2012/02
Dismantling of dry conversion facility in the uranium refining and conversion plant at Ningyo-toge began in 2008. During dismantling activities, project management data have been collected. Establishment of the calculation formula for dismantling of each kind of equipment makes it possible to evaluate manpower for dismantling the whole facility. However, it is not easy to prepare calculation formula for all kinds of equipment in the facility. Therefore, a simpler evaluation method was considered to calculate manpower based on facility characteristics. The results showed promise for evaluating dismantling manpower with respect to each chemical process. To create an effective dismantling plan, it is necessary to carefully consider use of a GH preliminarily. Thus, an evaluation method of project management data such as manpower and secondary waste generation was considered. The results showed promise for evaluating project management data of GH by using established calculation formula.
Sugitsue, Noritake; Tanaka, Yoshio; Tokizawa, Takayuki; Annen, Sotonori; Yonekawa, Shigeru; Nakakura, Hiroyuki*; Tokuyasu, Takashi*; Aritomi, Tadahiko*
Dekomisshoningu Giho, (30), p.53 - 66, 2004/09
In the Ningyo-Toge Environmental Engineering Center, we clarify a relation of all works about the decommissioning. And, as an information base to plan promotion of efficiency of a work, we develop the Decommissioning Engineering System. The Decommissioning Engineering System consists of the function to do work support of a decommissioning, the function to gather the results information the decommissioning technology and the general evaluation function of the decommissioning plan on the basis of facilities information collected by three-dimensional CAD. The decommissioning of the nuclear fuel cycle facility has the characteristics that a period from the plan to the decommissioning is long in comparison with the general chemical plant. And the peculiarity to handle radioactive waste is a reason. In addition the System Decontamination, Dismantling, Treatment and Waste disposal are each other influence it closely in the decommissioning process. Therefore as for the decommissioning process, system engineering is important.
Takahashi, Nobuo; Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Tokuyasu, Takashi; Sugitsue, Noritake
no journal, ,
no abstracts in English
Morimoto, Yasuyuki; Ikegami, Sohei; Tanaka, Yoshio; Tokuyasu, Takashi; Takahashi, Nobuo; Sugitsue, Noritake
no journal, ,
no abstracts in English
Tanaka, Yoshio; Morimoto, Yasuyuki; Ikegami, Sohei; Tokuyasu, Takashi; Takahashi, Nobuo; Sugitsue, Noritake
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no abstracts in English
Morimoto, Yasuyuki; Tanaka, Yoshio; Tokuyasu, Takashi; Takahashi, Nobuo; Sugitsue, Noritake
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no abstracts in English
Usui, Hideo; Tachibana, Mitsuo; Morimoto, Yasuyuki; Takahashi, Nobuo; Tokuyasu, Takashi; Sugitsue, Noritake
no journal, ,
no abstracts in English
Takahashi, Nobuo; Morimoto, Yasuyuki; Tanaka, Yoshio; Tokuyasu, Takashi; Sugitsue, Noritake
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Cutting/Abrasion of the steel with the conventional diamond-coated cutter has a short tool life. Therefore it has been assumed that the cutting of steel with the diamond-coated cutter was unsuitable. However, the abrasive installation strength of the diamond-coated cutter which used the adhesive of Ni base for increases. Therefore it was reported that even the cutting/abrasion of steel had longer tool life in a meeting of autumn, 2009. We examined the cutting with a diamond-coated cutter at reported. In this announcement, we announce following items about examined result. (1) A characteristic of nuclear fuel plant decommissioning project extracted from the dismantling results of the uranium conversion plant. (2) The cutting examined result of the SS for the diamond-coated cutter. (3) An applicability evaluation result to the decommissioning project for the diamond-coated cutter.
Tanaka, Yoshio; Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Sugitsue, Noritake
no journal, ,
In the decommissioning of the atomic energy plant, the secondary waste is generated by the equipment dismantlement. In the decommissioning of the uranium conversion plant in fiscal 2008, a lot of secondary waste was generated due to the dismantlement of the "greenhouse (GH)" (GH stands for the temporary construction where workers cut off the equipments to prevent the pollution expansion.). Therefore, there is a possibility that the size reduction of GH leads to the secondary waste reduction. In fiscal 2009, the size reduction of GH was tried by the cutting area setup. In this report, the effect of the cutting area was examined with a view toward the secondary waste reduction. As a result, the cutting area is effective in the workers number reduction and the secondary waste reduction at the complicated plant such as the uranium conversion plant.
Matsuoka, Toshiyuki; Tsuruta, Tadahiko; Tagami, Masahiko; Ishibashi, Masayuki; Tokuyasu, Shingo; Ueno, Takashi; Yuguchi, Takashi
no journal, ,
Current status of geological investigations of the MIU Project Phase II are summarized. Geological mapping, reverse VSP, Analog model simulation and so on, were conducted as Phase II investigations. As results of these investigations, the methodology for the evaluation of geological model constructed in Phase I could be presented.
Tanimoto, Masataka; Morimoto, Yasuyuki; Ikegami, Sohei; Tokuyasu, Takashi; Tanaka, Yoshio; Sugitsue, Noritake; Tachibana, Mitsuo; Ishigami, Tsutomu
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no abstracts in English
Takahashi, Nobuo; Morimoto, Yasuyuki; Tanaka, Yoshio; Tokuyasu, Takashi; Sugitsue, Noritake
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In the Decommissioning Project of Uranium Conversion Plant, we try that gather dismantling objects for a purpose by promotion of efficiency of work, SW (Secondary Waste) reduction to the exclusive area from 2009. About the feature of the SW generation, we weighed it against the results of 2008 when we didn't gather dismantling objects to the exclusive area. The SW generation per dismantling objects 1 ton was "non gathered case" = 51.3 kg and "gathered case" = 38.3 kg. We confirmed a reduction effect that 20 % with combustibles and 40 % with flame retarded by gathering dismantling objects. The main SW materials were Gh structure materials, mainly on the polyethylene seats, together in 2008 and 2009. In addition, "non gathered case" generates SW after Gh removal work intensively. On the other hand, "gathered case" generates SW constantly for a dismantling period.
Tanaka, Yoshio; Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Sugitsue, Noritake
no journal, ,
In Ningyo-toge environmental engineering center started the decommissioning project of commercial-scale nuclear fuel facility in 2008. We worked on dismantling/removal of equipments in the radiation controlled area, and about 80 % were finished. Therefore, we arranged it systematically for dismantling work in work elements to need for the decommissioning project. The man-hour ratio of 3 work division was preparation 29 % and dismantlement 59 %, post-processing 12 %. The breakdown of each work division is preparations 14 processes and dismantlement 32, post-processing 11. At least 57 processes classifications are necessary for dismantling work. In addition, a man-hour ratio to need for post-processing was almost a constant in every result. On the other hand, the man-hour ratios of preparations and dismantling were classified in 3 groups.
Izumo, Sari; Usui, Hideo; Tachibana, Mitsuo; Sugitsue, Noritake; Morimoto, Yasuyuki; Tokuyasu, Takashi
no journal, ,
no abstracts in English
