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Shimazaki, Yosuke; Yamazaki, Kazunori; Iigaki, Kazuhiko
Hozengaku, 18(1), p.16 - 20, 2019/04
no abstracts in English
Yoshinaka, Kazuyuki; Abe, Sadayoshi
Gijutsushi, 27(6), p.4 - 7, 2015/06
In a reprocessing plant, some apparatuses are in severe corrosive condition, like exposure to boiling nitric acid. Safety functions, like fire prevention on organic solvent, are needed on some apparatuses. To maintain the apparatuses and functions, various inspections are performed. The features of the maintenance in high dose, are represented in experiences of remote operation. The way of decommissioning of Tokai Reprocessing Plant has been indicated last year. But importance of maintenance will not change, because the apparatuses for treatment of high level liquid waste will be used for long term. Continuing development of remote maintenance technology and contribution to decommissioning Fukushima Dai-ichi NPP are expected.
Department of HTTR Project
JAERI-Review 2003-013, 98 Pages, 2003/05
The HTTR (High Temperature Engineering Test Reactor) with the thermal power of 30 MW and the reactor outlet coolant temperature of 850/950C is the first high temperature gas-cooled reactor (HTGR) in Japan, which uses coated-particle fuel, graphite for core components, and helium gas for primary coolant. The HTTR, which locates at the south-west area of 5000 m in the Oarai Research Establishment, had been constructed since 1991 before accomplishing the first criticality on November 10, 1998. Rise to power tests of the HTTR started in September, 1999 and the rated thermal power of 30 MW and the reactor outlet coolant temperature of 850C was attained in December 2001. 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&Ds on HTGRs from FY1999 to 2001.
; Terano, Toshihiro; ; ; Okubo, Toshiyuki
JNC TN9410 2000-004, 30 Pages, 2000/03
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 TJ9440 2000-003, 173 Pages, 1999/03
In FY 1997, a program which evaluates the risk in each phase of the maintenance was developed to support the maintenance planning on an FBR plant. In FY 1998, the GUI (Graphical User Interface) of the program developed in FY 1997 was enhanced for its user-friendlyness including facilitation of data settings and interpretation of the computational results. Specifically, following functions were incorporated : (1)To call associated window displays (editing and reporting display) mutually. (2)To edit the combinations of the systems for their maintenance scheduling. Furthermore, some risk evaluation functions such as the database function for cutsets of accident sequences and tracking function of risk trends were developed and added to its analysis module. A series of test on the programs with the GUI and the analysis module was performed and it was verified that the progam worked correctly.
Lund
PNC TN3410 98-001, 14 Pages, 1998/01
At the FUGEN Power Station a system for online monitoring of selected process component behavior, CONFU (CONdition monitoring at FUgen) has been implemented. This system is based on MOCOM (Model Based Condition Monitoring System), developed at IFE/OECD Halden Reactor Project. The system is currently monitoring the heat exchangers for the Reactor Auxiliary Cooling Water System. These heat exchangers has shown a slowly degrading performance over time due to fouling, i.e. accumulation of a heat resisting layer of organic material on the sea water side. This slow degradation, which is not detected by the conventional control and alarm systems, is not an operational, but rather a maintenance problem. CONFU is using dynamically updated mathematical models to compute the performance degradation of the heat exchangers, expressed in overall heat transfer, heat transfer coefficients or heat exchanger efficiency. The results of testing CONFU on real plant data identify the expected degradation trends. The data from CONFU can, in addition to give the plant operator a good impression of the component's operational state, be utilized by the maintenance planning personnel for determination of the most optimal maintenance schedule. Furthermore, the process models in CONFU have been used for simulation purposes.
; ; Yamada, Takeshi; ; ; ; Kaito, Yasuaki; ; Kotaka, Yoshinori; ; et al.
PNC TN2410 96-005, 339 Pages, 1996/03
Construction of the 'Monju' fuel handling systems was completed in April, 1992. From March 1991 to August 1992, pre-commissioning tests were carried out. In December 1992, all the systems of Monju were transfered to PNC, and commissioning tests and reactor physics tests, were started. For the first time, during these physics tests, the fuel handling systems were operated for one of the commissioning tests 'Loading to Criticality', without significant problems. 168 fuel sub-assemblies were loaded into the core and the first criticality was achieved on 5th April 1994. The fuel handling systems continued in operation for the 'Loading to Full Size of the Core', power distribution test and for cleaning discharged dummy sub-assemblies. To keep these fuel handling systems working somothly and satisfactorily annual maintenance has been carried out since 1992. This paper describes the operation and maintenance experience of fuel handling systems after the pre-commissioning tests and future study items for system reliability improvement.
Jitsukawa, T.*; Tojo, T.*; Takagi, M.*; Sudo, H.*
PNC TJ8674 95-001, 68 Pages, 1995/02
no abstracts in English
Muramatsu, Ken
Nihon Genshiryoku Gakkai-Shi, 36(5), p.387 - 390, 1994/00
no abstracts in English