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Matsuda, Makoto; Abe, Shinichi; Ishizaki, Nobuhiro; Tayama, Hidekazu; Nakanoya, Takamitsu; Kabumoto, Hiroshi; Nakamura, Masahiko; Kutsukake, Kenichi; Otokawa, Yoshinori; Asozu, Takuhiro; et al.
Dai-27-Kai Tandemu Kasokuki Oyobi Sono Shuhen Gijutsu No Kenkyukai Hokokushu, p.142 - 145, 2015/03
no abstracts in English
Nara, Takayuki; Agematsu, Takashi; Ishibori, Ikuo; Kurashima, Satoshi; Yoshida, Kenichi; Fukuda, Mitsuhiro; Okumura, Susumu; Miyawaki, Nobumasa; Kashiwagi, Hirotsugu; Nakamura, Yoshiteru; et al.
JAEA-Review 2005-001, TIARA Annual Report 2004, P. 370, 2006/01
no abstracts in English
Department of HTTR Project
JAERI-Review 2005-010, 83 Pages, 2005/03
JAERI-Review-2005-010.pdf:5.18MB
The HTTR (High Teperature Engineering Test Reactor) with the thermal power of 30MW and the reactor outlet coolant temperature of 850/950
C is the first high temperature gas-cooled reactor (HTGR) in Japan, which uses coated fuel particle, graphite for core components and helium gas for primary coolant. December 2001, the thermal power of 30MW and the reactor outlet coolant temperature of 850C was attained. JAERI received the certificate of pre-operation test, that is, the commissioning licence for the HTTR in March 2002. This report summarizes operation, tests, maintenance, radiation control, and construction of components and facilities for the HTTR as well as R&D on HTGRs for FY2003.
Department of HTTR Project
JAERI-Review 2003-043, 92 Pages, 2004/02
JAERI-Review-2003-043.pdf:5.76MB
The HTTR (High Temperature Engineering Test Reactor) with the thermal power of 30MW and the reactor outlet coolant temperature of 850/950C is the first high temperature gas cooled reactor in Japan, which uses coated fuel particle, graphite for core components, and helium gas for primary coolant. In December 2001, the rated power of 30MW and the reactor outlet temperature of 850C was attained. JAERI received the certificate of pre-operation test, that is, the commissioning license for the HTTR in March 2002. This report summarizes operation, tests, maintenance, radiation control and construction of components and facilities for the HTTR as well as R&D on HTGRs for FY2002.
Onodera, Seiji; Hirose, Hideyuki; Izawa, Kazuhiko; Tanino, Shuichi; Kaminaga, Jota*; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; Miyoshi, Yoshinori; Yanagisawa, Hiroshi; et al.
JAERI-Tech 2001-057, 54 Pages, 2001/09
JAERI-Tech-2001-057.pdf:4.28MB
no abstracts in English
; Terano, Toshihiro; ; ; Okubo, Toshiyuki
JNC TN9410 2000-004, 30 Pages, 2000/03
JNC-TN9410-2000-004.pdf:0.86MB
The Operation and Maintenance Support Systems for JOYO are being developed, with the aim of ensuring the stable and safe operation of JOYO and improving operational reliability of future FBR plants. Plant Operation Management Expert Tool named JOYPET had been developed as one of the Operation and Maintenance Support Systems, which helps plant operation management. The following functions were developed and applied. (1)Papers management (Plant status management) function for maintenance activities (2)Isolation management support function for plant operation (3)Automatically drawing function of plant operation schedule (4)Isolation judgment function for plant operation By use this system, the plant management of JOYO was able to improved reliability and reduced manpower.
*; *; *; *
JNC TJ3410 2000-021, 73 Pages, 2000/03
JNC-TJ3410-2000-021.pdf:52.78MB
no abstracts in English
*; *; Tanai, Kenji
JNC TN8400 99-050, 94 Pages, 1999/11
This paper reports on the evaluations of operational activities for a High Level Radioactive Wastes Disposal Facility, from initial acceptance of vitrified waste at a surface facility to emplacement engineered barriers in underground facilities. The purpose of this analysis is to confirm the technical feasibility of geological disposal. First, the basic design and repository system requirements are identified. Second, operational activities in surface facilities, access facilities and underground facilities are described. The required procedures and equipment, suitable for specific emplacement concepts and configurations for engineered barrier systems are discussed for specific examples. Countermeasures for potential adverse events or conditions are based on extensive civil engineering and mining experiences in Japan and abroad. The time schedule is also evaluated on the basis of these concepts. In addition, the concept of stationary and mobile radiation control areas is studied based on experiences and practice in current nuclear facilities. Finally future research and development items are summarized.
;
PNC TN9410 97-064, 42 Pages, 1997/06
In our study on a hyblid fast reactor system, we have investigated it from the view point of transmutation ability of trans-uranium (TRU) nuclide making the most effective use of special features (controllability, hard neutron spectrum) of the system. It is proved that a proton beam is superior in generation of neutrons compared with an electron beam. Therefore a proton accelerator using spallation reaction with a target nucleous has an advantage to transmutation of TRU than an electron one. A fast reactor is expected to primarily have a merit that the reactor can be operated for a long temrm without employment of highly enriched plutonium fuel by using external neutron source such as the proton accelerator. Namely, the system has a desirable characteristic of being possible to self-sustained fissile plutonium. Consequently in the present report, core characteristics of the system were roughly studied by analyses using 2D-BURN code. The possibility of self-sustained fuel was investigated from the burnup and neutronic calculation in a cylindrical core with 300w/cc of power density without considering a target material region for the accelerator. For a reference core of which the height and the radius are both 100cm, there is a fair prospect that a long term reactor operation is possible with subsequent refueling of natural uranium, if the medium enriched (around 10wt%) uranium or plutonium fuels are fully loaded in the initial core. More precise analyses will be planed in a later fiscal year.
; ; Ozawa, Kenji; *; *
PNC TN9410 97-006, 46 Pages, 1996/12
Since it is desired to enhance availability and safety of nuclear power plants operation and maintenance by removing human factor, there are many researches and developments for intelligent operation or diagnosis using artificial intelligence(AI) technique in the Frontier Research. In this development, We have been developing an autonomous operation and maintenance system for nuclear power plants by substituting AI's. On the other hand, Ship Research Institute(SRI) have been developing a monitoring system for cooperative function of distributed systems in the autonomous operation and maintenance systems. In this report, we have studied telecommunication methods between PNC and SRl to combine the autonomous operation and maintenance system and its monitorillg systan. As the result, we have confinned a proper performance of that telecommunication facility by the test via public telephone line or Internet.
; ; Yoshikawa, Shinji; Ozawa, Kenji
PNC TN9410 96-101, 40 Pages, 1996/04
Since it is desired to enhance availability and safety of nuclear power plants operation and maintenance by removing human factor, there are many researches and developments for intelligent operation or diagnosis using artificial intelligennce (AI) technique. We have been developing an autonomous operation and maintenance system for nuclear power plants by substituting AI's and intelligent robots. It is indispensable to use various and large scale knowledge relative to plant design, operation, and maintenance, that is, whole life cycle data of the plant for the autonomous nuclear power plant. These knowledge must be given to AI system or intelligent robots adequately and opportunely. Moreover, it is necessaly to insure real time operation using the large scale knowledge base for plant control and diagnosis performance. We have been studying on the large scale and real time knowledge base system for autonomous plant. In the report, we would like to present the basic concept and expecting performance of the knowledge base for autonomous plant, especialy, autonomous control and diagnosis system.
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 95-002, 98 Pages, 1995/11
no abstracts in English
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 95-001, 104 Pages, 1995/11
no abstracts in English
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 94-002, 100 Pages, 1994/02
no abstracts in English
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 94-001, 95 Pages, 1994/02
no abstracts in English
Karube, Koji; ; ; ; Kawai, Masashi;
PNC TN9440 93-012, 83 Pages, 1993/04
This report describes the operating experience of the primary main cooling system from January 1982 to March 1992, and of the primary auxiliary cooling system from october 1986 to March 1992. 0ut lines of the operating experience ale followings; There have been no serious troubles in this period. (1)The main system; Operation time of the circulation pumps are about 67675 hours. Accumulated operation time of the pumps are about 105970 hours. The pumps has been started 212 times. (2)The auxiliary system; Operation time of the circulation pump (EMP) is about 4767 hours. Accumulated operation time of the pump is about 8667 hours. The pump has been automatically started 31 times with the scheduled test.
Isozaki, Kazunori; ; Ito, Hideaki; ; Chatani, Keiji; ;
PNC TN9520 93-006, 198 Pages, 1992/11
None
Department of JMTR
JAERI-M 91-228, 185 Pages, 1992/02
no abstracts in English
