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Sakurai, Kiyoshi; Nojiri, Ichiro*
JAERI-Conf 2003-019, p.855 - 857, 2003/10
This paper provides overview of sub-criticality safety analysis seminar (July 2000-July 2003, JAERI, total 40 engineers from universities, research institutes and enterprises) for nuclear fuel cycle facility with the Monte Carlo method in Japan. MCNP-4C2 system (MS-DOS version) was installed in each note-type personal computer. Fundamental theory of reactor physics and Monte Carlo simulation including MCNP-4C manual was lectured. Effective neutron multiplication factor and neutron spectrum were calculated for JCO deposit tank, JNC uranium solution storage tank, JNC plutonium solution storage tank and JAERI TCA core. In the seminar, methodology of safety management for nuclear fuel cycle facility was discussed in order to prevent criticality accident.
Tachibana, Haruo; Sekita, Tsutomu; Yamaguchi, Takenori
JAERI-Data/Code 2003-002, 46 Pages, 2003/03
JAERI-Data-Code-2003-002.pdf:4.49MB
A computer code (W-View) was developed to analyze the meteorological data statistically based on “the guideline of meteorological statistics for the safety analysis of nuclear power reactor"(Nuclear Safety Commission on January 28,1982; revised on March 29,2001), which code is used for statistical analysis of meteorological data to assess the public dose in case of normal operation and severe accident to get the license of nuclear reactor operation. This code was revised from large office computer code and developed for personal computer user to analyze the meteorological data simply and conveniently and to make the statistical data tables and figures of meteorology.
Sakurai, Kiyoshi; Ueki, Kotaro*; Naito, Yoshitaka*
Nihon Genshiryoku Gakkai-Shi, 43(3), p.219 - 220, 2001/03
no abstracts in English
Sakurai, Kiyoshi; Kume, Etsuo; Yatabe, Shigeru*; Maekawa, Fujio; Yamamoto, Toshihiro; Nagaya, Yasunobu; Mori, Takamasa; Ueki, Kotaro*; Naito, Yoshitaka*
JAERI-Review 2000-034, 133 Pages, 2001/02
JAERI-Review-2000-034.pdf:7.69MB
no abstracts in English
Sakurai, Kiyoshi; Kume, Etsuo; Yatabe, Shigeru*; Maekawa, Fujio; Yamamoto, Toshihiro; Nagaya, Yasunobu; Mori, Takamasa; Ueki, Kotaro*; Naito, Yoshitaka*
Nihon Genshiryoku Gakkai-Shi, 42(10), p.1062 - 1065, 2000/10
no abstracts in English
Tsukimori, Kazuyuki
JNC TN9400 2000-086, 103 Pages, 2000/08
JNC-TN9400-2000-086.pdf:3.67MB
ln order to evaluate the integrity of the floor liner of "MONJU" at sodium leakage accident, nonlinear finite element analyses have been conducted considering the effect of thinning of the liner due to molten salt type corrosion. Modeling by shell elements is appropriate since liner is composed of thin plates, however, it is difficult to deal with the very local strain behaviors. 0n the other hand, modeling by solid elements makes the numerical calculation impractical. If we extract the small part of the liner which includes local discontinuities, it is possible to evaluate local strain behaviors practically by using the solid element analysis model of the part. To realize this approach, the method to generate all the boundary displacements of the part model from the shell element analysis result of total structure is needed. The aims of this study are to develop the method to deal with the incompatibility between shell and solid elements at part model boundary, and to build numerical analysis circumstances including this method to make the detailed nonlinear finite element analyses of the floor liner of "MONJU" possible. Summary of the results is shown below, (1)The problem of the incompatibility between shell and solid elements was solved by introducing weighting function at 'T' and 'L' type corners and the interpolation function of 4-node rectangular plate bending element at the connection between liner plate and frame. (2)Software system was developed by using 'FINAS' and verified. (3)This approach was applied to one of the cases of the floor liner analyses of "MONJU" at sodium leakage accident. The analysis result showed that three-dimensional local strain behavior could be evaluated directly. ln addition, it was confirmed that the result by shell element analysis was conservative in evaluation of strain compared with that by solid element analysis in this case.
; Nemoto, Masaaki; Saikawa, Takuya*; Sukegawa, Kazuya*
JNC TN9410 2000-008, 66 Pages, 2000/03
JNC-TN9410-2000-008.pdf:1.39MB
The experimental fast reactor "JOYO" served as the MK-II irradiation bed core for testing fuel and material for FBR development for 15 years from 1982 to 1997. During the MK-II operation, impurities concentrations in the sodium and the argon gas were determined by 67 samples of primary sodium, 81 samples of secondary sodium, 75 samples of primary argon gas, 89 samples of secondary argon gas (the overflow tank) and 89 samples of secondary argon gas (the dump tank). The sodium and the argon gas purity control data were accumulated from in thirty-one duty operations, thirteen special test operations and eight annual inspections. These purity control results and related plant data were compiled into database, which were recorded on CD-ROM for user convenience. Purity control data include concentration of oxygen, carbon, hydrogen, nitrogen, chlorine, iron, nickel and chromium in sodium, concentration of oxygen, hydrogen, nitrogen, carbon monoxide, carbon dioxide, methane and helium in argon gas with the reactor condition.
Nomura, Toshibumi
Hoken Butsuri, 35(1), p.127 - 135, 2000/03
no abstracts in English
*
JNC TJ7400 2000-013, 26 Pages, 2000/02
JNC-TJ7400-2000-013.pdf:1.25MB
no abstracts in English
Sakurai, Kiyoshi; Ueki, Kotaro*; Naito, Yoshitaka*
Nihon Genshiryoku Gakkai-Shi, 42(2), p.114 - 115, 2000/02
no abstracts in English
Kazama, T.*; Hashimoto, T.*; Seito, Y.*; *; Kanamori, Miwa*; *; *
JNC TJ1450 2000-001, 160 Pages, 1999/12
JNC-TJ1450-2000-001.pdf:18.71MB
no abstracts in English
Harada, Yasunori; Sasamoto, Nobuo; Sakamoto, Yukio; Kurosawa, Naohiro*; *
JAERI-Data/Code 97-013, 196 Pages, 1997/03
JAERI-Data-Code-97-013.pdf:4.59MB
no abstracts in English
gas turbine power generation system (User's manual); Sekiguchi, Nobutada
PNC TN9520 95-002, 66 Pages, 1995/02
This analysis program code STEDFAST; Space, TErrestrial and Deep sea FAST reactor gas tubine system; is used to get the adequate values of system parameters on fast reactor gas turbine power generation systems used as power sources for deep sea, space and terrestrial cogeneration. Characteristics of the code are as follows. Objective systems of the code are a deep sea, a space and a terrestrial reactors. Primary coolants of the systems are NaK, Na, Pb and Li. Secondary coolant is the mixture gas of He and Xe. The ratio of He and Xe is arbitrary. Modeling of components in the systems was performed so that detailed modeling might be capable in future and that a transient analytical code could be easily made by using the code. A progra㎜ing language is MAC-FORTRAN. The code can be easily used in a personal computer. The code made possible instant calculation of various state values in a Brayton cycle, understanding the effects of many parameters on thermal efficiency and finding the most adequate values of the parameters. From now on, detailed modeling of the components will be performed. After that, the transient program code will be made.
Watanabe, Norio; *
JAERI-M 93-120, 82 Pages, 1993/06
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.
Itabashi, Keizo;
Dai-29-Kai Joho Kagaku Gijutsu Kenkyu Shukai Happyo Rombunshu, p.263 - 272, 1993/00
no abstracts in English
Shimooke, Takanori; *; Kobayashi, Kensuke;
Proc. of the Int. Conf. on Radiation Effects and Protection, p.496 - 499, 1992/00
no abstracts in English
