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*; Ijiri, Yuji*; *; *
JNC TN8400 2000-021, 66 Pages, 2000/04
JNC-TN8400-2000-021.pdf:4.38MB
A reliability evaluation for radionuclide transport analysis code, MATRICS, used in radionuclide transport analysis in the natural barrier system PA in H12 report has been carried out. Sensitivity analysis to radionuclide transport parameter in MATRICS and analytical solution has been performed, and the results of each analysis have been compared. Additionally sensitivity analysis using Talbot Method, Crump method and Hosono method has been carried out, and the results of each inverse Laplace transform method has been compared. The conclusions obtained from the results of the evaluation are summarized as follows, (1)In case of the infinite matrix diffusion distance, an error among the results of each calculation is maximum about 0.4% in the range of Pe number from 1.0 to 100. And, an error among the results of each calculation is maximum about 5.5% in the range of transmissivity from 1.0
10
to 1.010
(m
/s). (2)In case of the finite matrix diffusion distance (0.03
1.0(m)), an error among the results of each calculation is maximum about 0.7% in the range of Pe number from 1.0 to 100. And, an error among the results of each calculation is maximum about 2.4% in the range of transmissivity from 1.010 to 1.010(m/s). 3)By comparing Talbot method with other inverse Laplace transform method, Talbot method is confirmed to give similar results with other inverse Laplace transform method in the range of Pe number from 5.010
to 2.010
, and that of transmissivity below 1.010
(m/s). Therefore, it is concluded that the reliability of MATRICS are confirmed by conducting sensitivity analysis in the range of Pe number and transmissivity coefficient used in H12 report.
Ezaki, Tetsuro*; Jinno, Kenji*; Mitani, Yasuhiro*; *; Uchida, Masahiro; *
JNC TY8400 2000-004, 94 Pages, 2000/03
JNC-TY8400-2000-004.pdf:7.73MB
no abstracts in English
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.
Suzuki, Kazuhiko*; *
JNC TJ8400 2000-052, 136 Pages, 2000/02
JNC-TJ8400-2000-052.pdf:4.16MB
Though HAZOP is recognized as the useful safety assessment method, it requires a labor-intensive and time-consuming process. So recently computer-aided HAZOP has been proposed. The research report in 1999 (PNC TJ1400 99-003) presented HAZOP system based on the plant component malfunctions basic models. By using this basic model, not only state malfunction of component but also the consequence to external circumstance can be assessed. G2, which is an excellent object-oriented developer tool in GUI (Graphical User Interface), was used as a tool for developing the system. By using the graphical editor in the system, the user can carry out HAZOP easily. The purpose of this research is to improve the ability of the HAZOP system to obtain a more detailed HAZOP results. HAZOP is carried out according to the fault propagation of component level and the one of plant level based on plant component malfunctions basic models. Furthermore, the HAZOP system which can do the cause and effect analysis in detail intended for the component which processes two or more materials is developed. It is possible to carry out HAZOP for various plants by newly adding material information to the knowledgebase. We have applied this system to the Nuclear Reprocessing Facilities to demonstrate the utilities of developing system.
*
Joho Shori Gakkai Rombunshi, 39(3), p.529 - 541, 1998/03
no abstracts in English
Shirai, Nobutoshi; Sudo, Toshiyuki
PNC TN8460 95-001, 92 Pages, 1995/09
no abstracts in English
Fukushima, Mineo; ; ; ;
PNC TN8410 93-192, 129 Pages, 1993/05
There is much data available from irradiation tests on various electrical devices and materials simulating conditions found in nuclear plants. This data is very helpful for selecting the components to be used in unclear plant and for equipment design. A data base has been designed to provide easy acquisition and utilization of the test data. Basic items (target user, scope for collecting data, etc.), qualifications (purpose, function, etc.) and input data sheets have been considered in the design of the data base architecture. A prototype data base system architecture has been designed based on these considerations. After improvement and debugging of the prototype system, irradiation data from tests on semiconductors and polymers were entered into the data base using the data sheets. The data base architecture is designed to be simple so that beginners can easily use it. This system has about 1000 electronic equipments data and about 500 polymers data as of July, 1993. Radiation resistance of electronic equipment is now being evaluated using the data base system. Further improvements and rssolution of problems will be made so the data base system can provide optimum support to the design of equipment used in radiation anvironments.
; Maruo, Yoshihiro; ; Shinohara, Kunihiko
PNC TN8460 92-001, 65 Pages, 1992/03
no abstracts in English
Murakami, Hiroyuki*; Kanamori, Masashi; Nakamoto, Athushi*; Seki, Akio
PNC TN841 81-57, 19 Pages, 1981/10
no abstracts in English
