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Matsui, Yoshinori; Takahashi, Hiroyuki; Yamamoto, Masaya; Nakata, Masahito; Yoshitake, Tsunemitsu; Abe, Kazuyuki; Yoshikawa, Katsunori; Iwamatsu, Shigemi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; et al.
JAEA-Technology 2009-072, 144 Pages, 2010/03
JAEA-Technology-2009-072.pdf:45.01MB
"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from FY2006 in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupled irradiations or single irradiation by JOYO fast reactor and JRR-3 thermal reactor were performed for about two years. The irradiation specimens are very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we summarized about the overall plan, the work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.
Kimura, Nobuyuki; Miyake, Yasuhiro*; Miyakoshi, Hiroyuki; Nagasawa, Kazuyoshi*; Igarashi, Minoru; Kamide, Hideki
JNC TN9400 2003-077, 96 Pages, 2003/06
JNC-TN9400-2003-077.pdf:3.96MB
A quantitative evaluation on thermal striping, in which temperature fluctuation due to convective mixing causes high cycle thermal fatigue in structural components, is of importance for structural integrity and reactor safety.Thermal conductivity of sodium is approximately 100 times larger than that of water. Thus, temperature fluctuation characteristics will be different between sodium, which is used as a coolant of a fast reactor, and water, which is used in general industries. In this study, a comparison of convective mixing among jets was performed in parallel triple wall jets with the same geometries between sodium and water. The discharged velocity in the sodium experiment was experimental parameter and set at the same velocity and the same Reynolds number in comparison with the water experiment. And also, the velocity ratio among the triple jets was varied to change flow pattern. It was seen that the water jets were mixed in slightly closer region to the nozzle than in sodium jets. As for the power spectrum densities (PSD) of temperature fluctuation, the PSD of sodium was similar to the PSD of water under the same discharged velocity condition. At the neighborhood of the wall, the lower frequency component in the PSD of sodium decreased in comparison with the PSD of water. It was shown that the amplitude and frequency characteristics obtained by rain-flow method, which was important to evaluate structural damage by the thermal fatigue, were identical between sodium and water overall. These experimental results show that water experiment could simulate the frequency and the amplitude in temperature fluctuation characteristics in the sodium cooled reactor.
Kimura, Nobuyuki; Nagasawa, Kazuyoshi*; Miyakoshi, Hiroyuki; Miyake, Yasuhiro*; Igarashi, Minoru; Kamide, Hideki
JNC TN9400 2003-003, 66 Pages, 2002/10
JNC-TN9400-2003-003.pdf:3.61MB
A quantitative evaluation on thermal striping, in which temperature fluctuation due to convective mixing causes high cycle thermal fatigue in structural components, is of importance for reactor safety. The reasonable and safety design could be approved by taking account of decay of temperature fluctuation in fluid, during heat transfer from fluid to structural surface and thermal conduction in the structure. Temperature fluctuation characteristics due to convective mixing will be influenced by the velocity/temperature boundary layers near the structure. In this study, an experimental analysis was performed using DNS in order to separate influence of heat capacity of the structure and to evaluate an attenuation due to the boundary layer near the wall surface for a sodium experiment of parallel triple jets configuration. In the experiment, a cold jet on center and hot jets on both sides flowed vertically and along the wall, and the discharged velocities of triple jets were O.5m/s equally. The calculated temperature field was in good agreement with the experimental result at further position from the wall surface, including the power spectrum density of the temperature fluctuation. On the other hand, at near position from the wall surface, calculated temperature fluctuation intensity was not attenuated whereas the experimental intensity was decreased. This means that the intensity of temperature fluctuation is not decreased by the boundary layer. Thermal interaction between fluid and the wall will decrease the temperature fluctuation intensity in the fluid near the wall. The effect of wall friction on second moments of turbulence was evaluated.
H.Tanab*; Miyake, Osamu*; M.hori*; Y.Ohmor*; Daigo, Y.*; Sato, Minoru*; T.Takah*
PNC TN943 81-02, 25 Pages, 1981/01
Analyses of leak propagation have been performed in order to support the selection of a design basis leak (DBL) for sodium-water reaction accidents in steam generators of the Japanese prototype fast breeder reactor, MONJU. For the purpose of estimating the possible maximum leak rate due to the failure propagation, a computer code, (LEAP) (Leak Enlargement and propagation), has been developed. This code analyzes the failure propagation process taking account of data from sodium-water reaction experiments throughout the world. This paper describes the model and structure of the LEAP code, a validation study, and results of the LEAP calculation for the MONJU steam generators and it has been concluded that the sodium-water reaction accidents can be terminated before the leak rate exceeds the DBL (one plus three DEG's) with the present detection system and safety devices.
Miyake, Osamu*; Shindo, Yoshihisa*; Sato, Minoru*
PNC TN952 79-20Tr, 76 Pages, 1979/09
Miyake, Osamu*; Shindo, Yoshihisa*; Sato, Minoru*
PNC TN952 79-19TR, 44 Pages, 1979/09
Matsui, Yoshinori; Takahashi, Hiroyuki; Ichise, Kenichi; Usami, Koji; Endo, Shinya; Iwamatsu, Shigemi; Yonekawa, Minoru; Ito, Kazuhiro; Yamamoto, Masaya; Soga, Tomonori; et al.
no journal, ,
"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from 2006 fiscal year in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupling irradiations or single irradiations by JOYO fast reactor and JRR-3 fission reactor were performed for about two years. The irradiation specimens are the very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we will present about the overall plan, work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.
Todaka, Azumi*; Toyoda, Shin*; Tachi, Momoko*; Shimazaki, Tatsuya*; Oka, Toshitaka; Yamaguchi, Ichiro*; Inoue, Kazuhiko*; Yasuda, Hiroshi*; Hirota, Seiko*; Tani, Atsushi*; et al.
no journal, ,
To estimate the external exposure dose using electron spin resonance technique, we use a "standard sample" which were prepared at each laboratory with each preparation protocol. It is necessary to unite the preparation protocol for the "real" standard sample. In the point of view of the enamel extraction method, no difference was observed for five dose responses between the absorbed dose and the CO
radical intensity.