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Yamamoto, Masahiro
Zairyo To Kankyo 2017 Koenshu (CD-ROM), 4 Pages, 2017/05
The committee surveying the corrosion losses in Japan was established in 1976, with conjunction of the Japan Society of Corrosion Engineering and the Japan Association of Corrosion Control. The report made by the committee introduced that corrosion loss was estimated to be about 1.8% of GDP (Gross Domestic Product). About quarter century had passed after the first survey, JSCE and JACC made the second surveying committee for the cost of corrosion in Japan in 1998. During that time, Japan's economic circumstances had changed drastically. In this report, results and problems of the former two researches are summarized.
Kunii, Katsuhiko
JAERI-Review 2005-021, 81 Pages, 2005/07
JAERI-Review-2005-021.pdf:3.34MB
Today we cannot ignore the risk of health and/or environment by energy production such as power generation since the risk has been made large enough. In this report an information survey has been done in order to know the outline and points of risk assessment. Based on the information of reports and literature about risk assessment, have been surveyed mainly the external cost assessment of power generation (in which quantification of health and/or environment risk has been done), in addition, risks of disasters, accidents, investments, finance etc. and impacts of those risks on social activities. The remarks obtained by the survey are as follows: (1) Some of external cost assessment of power generation show different results even if the assessment conditions of technology, site, etc. are mostly the same. It is necessary to remark on the information such as basic data, model, background, application limit of assessment considering the reliability. (2) Especially it is considered that the reliability of risk assessment is not enough at present because of the lack of basic data.
Sasajima, Tadayuki; Yagyu, Junichi; Miyo, Yasuhiko; Miya, Naoyuki; Sakakibara, Satoru*
KEK Proceedings 2003-16 (CD-ROM), 4 Pages, 2004/02
no abstracts in English
Takei, Masanobu; Katanishi, Shoji; Nakata, Tetsuo; Oda, Takefumi*; Izumiya, Toru*; Kunitomi, Kazuhiko
JAERI-Tech 2002-089, 44 Pages, 2002/11
JAERI-Tech-2002-089.pdf:3.35MB
no abstracts in English
Nakamura, Hiroo; Ida, Mizuho*; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki*; IFMIF International Team
Fusion Engineering and Design, 58-59, p.919 - 923, 2001/11
Times Cited Count：9 Percentile：56.04(Nuclear Science & Technology)no abstracts in English
Sugo, Takanobu; Tamada, Masao; Seguchi, Tadao; Shimizu, Takao*; Uotani, Masaki*; Kashima, Ryoichi*
Nihon Genshiryoku Gakkai-Shi, 43(10), p.1010 - 1016, 2001/10
Times Cited Count：16 Percentile：73.13(Nuclear Science & Technology)The cost of uranium recovered from seawater was estimated by using the amidoxime adsorbent of polymer fibers synthesized by radiation modification, and the technical problems in the recovery system were extracted. The cost of adsorbent materials, storage in seawater for uranium absorption, and the uranium detachment from the adsorbent was estimated respectively in three different systems of the storage in seawater as a buoy, floating body, and chain binding system. The recovery cost of uranium from seawater was estimated to be 8
10 times of that from mine uranium. More than 80% of the total cost was occupied by the cost for storage in seawater, which is owing to a weight of metal cage for the holding of adsorbents. The cost can be attained to half by the reduction of the weight to 1/4. One of facing research subject is the improvement of adsorbent ability, since the cost directly depends on the adsorbent performance.
Sato, Osamu; Tatematsu, Kenji; Tanaka, Yoji*
Genshiryoku eye, 47(7), p.60 - 64, 2001/07
no abstracts in English
Nakamura, Hiroo; Ida, Mizuho*; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki*
JAERI-Tech 2000-078, 17 Pages, 2001/01
JAERI-Tech-2000-078.pdf:1.93MB
no abstracts in English
Iwai, Yasunori; Yoshida, Hiroshi; Yamanishi, Toshihiko; Senrui, S.*; Nishi, Masataka
Fusion Engineering and Design, 49-50, p.847 - 853, 2000/11
Times Cited Count：15 Percentile：68.6(Nuclear Science & Technology)no abstracts in English
Hagiwara, Shigeru*; Sakamoto, Yoshiaki; Takebe, Shinichi; Okuda, Katsuzo*; Ogawa, Hiromichi
JAERI-Research 2000-039, 119 Pages, 2000/09
JAERI-Research-2000-039.pdf:5.04MB
no abstracts in English
*
JNC TN1440 2000-007, 115 Pages, 2000/08
JNC-TN1440-2000-007.pdf:4.45MB
no abstracts in English
Fujiwara, Masayuki; Mizuta, Shunji;
JNC TN9400 2000-050, 19 Pages, 2000/04
JNC-TN9400-2000-050.pdf:0.82MB
For evaluating the fast reactor system technology, it is important to evaluate the practical feasibility of ODS ferritic cdaddings, which is the most promising matelials to attain the goal of high coolant temperature and more than 150 GWd/t. Based on the results of their technology development, mass production process with highly economically benefit as well as manufacturing cost estimation of ODS ferritic claddings were preliminarily conducted. From the view point of future utility scale, the cost for manufacturig mother tubes has a dominant factor in the total manufacturing cost. The method to reduce the cost of mother tube manufacturing was also preliminarily investigated.
Aoki, Isao; ; Haga, Tetsuya; ; Sudo, Katsuo; Tsunashima, Yasumichi;
JNC TN8420 2000-005, 42 Pages, 2000/04
JNC-TN8420-2000-005.pdf:2.09MB
On August 1999, the Director of Tokai Work proposed an activity regarding recycling and reuse of general waste generated from Tokai Works. The activity was initiated by the Waste Management and Fuel Cycle Research Center, and is now being in progress through out the Tokai Works. In the course of this activity, Plutonium Fuel Center had settled the Working Group and the issues related to the waste reduction have been examined. This report collects the problems that became obvious through the survey of existing segregation method, treatment process, and the amount of the waste generation, and accounts for the concrete methodology for the recycling and reuse of general waste. In order to reduce waste, it is necessary to aware of the facing issues and adopt the countermeasures proposed in this report whenever possible. The activity will then leads us to reduce waste generation, which in turn will enable us to make 100 % waste recycling possible.
Kon, Tetsuro
JNC TN8440 2000-004, 93 Pages, 2000/03
TCMD (Tokai Construction Maintenance Division) Intranet System Integration has started in 1995. The first active activities between 1995 and 1996 has reported in a previous PNC report (PNC PN8440 97-032 TCMD Intranet System Integration Part 1). This is the second active activity's report between 1997 and 1999. Main content of this report is as follows. TCMD Intranet System Integration has completed by TCMD LAN system construction with high-speed LAN equipments and WINS services. TCMD group scheduler and conference rooms appointment system has developed by the operation of Exchange Server 5.5. The plant construction management data base system has developed - ACCESS 97/SQL Server 6.5 version. The plant construction management data base system has also developed---Internet Explorer / Active Server Pages version. The formal TCMD homepage service has begun in l998.
Zushi, Hideki*; Sugie, Tatsuo; Kusama, Yoshinori
Purazuma, Kaku Yugo Gakkai-Shi, 75(10), p.1221 - 1222, 1999/10
no abstracts in English
emission reduction strategy and roles of nuclear energy in JapanSato, Osamu; *; ;
JAERI-Research 99-015, 95 Pages, 1999/03
JAERI-Research-99-015.pdf:7.17MB
no abstracts in English
Matsumoto, Hiroshi; Boucher, D.*; Mukhovatov, V.*
26th European Physical Society Conference on Controlled Fusion and Plasma Physics (CD-ROM), 4 Pages, 1999/00
no abstracts in English
; Kakehi, Isao; Moro, Satoshi; ; ; ;
JNC TN9400 98-003, 422 Pages, 1998/10
Advanced recycle system engineering group of OEC has being carried out a design study of the advanced nuclear fuel recycle system using molten salt (electro-metallurgical process). This system is aiming for improvements of fuel cycle economy and reduction of environmental burden (MA recycles, Mimmum of radioactive waste disposal), and also improvement of safety and nuclear non-proliferation. This report describes results of the design study that has been continued since December 1996. (1)A design concept of the advanced nuclear fuel recycle system, that is a module type recycle system of pyrochemical reprocessing and fuel re-fabrication was studied. The module system has advantage in balance of Pu recycle where modules are constructed in coincidence with the construction plan of nuclear power plants, and also has flexibility for technology progress. A demonstration system, minimum size of the above module, was studied. This system has capacity of 10 tHM/y and is able to demonstrate recycle technology of MOX fuel, metal fuel and nitride fuel. (2)Each process of the system, which are pyrochemical electrorefining system, cathode processor, de-cladding system, waste disposal system, etc., were studied. In this study, capacity of an electrorefiner was discussed, and vitrification experiment of molten salt using lead-boric acid glass was conducted. (3)A hot cell system and material handling system of the demonstration system was studied. A robot driven by linear motor was studied for the handling system, and an arrangement plan of the cell system was made. Criticality analysis in the cell system and investigation of material accountancy system of the recycle plant were also made. This design study will be continued in coincidence with design study of reactor and fuel, aiming to establish the concept of FBR recycle system.
