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Takahashi, Hiroki; Nakajima, Nobuya; Kusunoki, Tsuyoshi
JAERI-Tech 2003-052, 59 Pages, 2003/06
JAERI-Tech-2003-052.pdf:5.95MB
The feasibility study of a distributed small reactor system has been performed in JAERI for the utilization of the heat source for public welfare, especially for air-conditioning and hot water supply, from the view point of use expansion of nuclear energy. In this report, the optimization of heat supply system including the set up and analysis of the model city are studied for the prediction of short and long term heat demand in the heat supply area. It is important process for understanding the whole system image to estimate the suitable heat source scale for the heat demand of the heat supply area, which is within a 5-km radius from heat supply source. From the analysis, it is clear that two or more set of the nuclear reactors based on 100 MW thermal power are suitable. Furthermore, it is indicated that the introduced reactor system can be utilized for more than 30 year and the heat reserve system is indispensable. This results show the feasibility of a small reactor system for district heat-and cooling supply.
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JNC TJ8400 2000-017, 74 Pages, 2000/02
JNC-TJ8400-2000-017.pdf:1.71MB
The report concerns the improvement of the method measuring thermal conductivity of buffer materials using a thermistor probe and the measurement of thermal conductivity of compacted bentonites and mixtures of bentonite and silica sand using the proposed method measuring thermophysical properties. The method measuring thermal conductivity is improved in accuracy and the apparatus is improved so as to measure easily with more short time. The calculated values of the conventional correlations predicting thermal conductivity of bentonite and mixture were compared with the exising and present data of thermal conductivity of bentonites and mixtures. The correlation proposed by Sakashita and Kumada can predict the best fitted values with the data of the bentonites and Fricke and Bruggeman correlations are fitted with the data for the mixtures with practical accuracy.
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PNC TN9410 98-053, 43 Pages, 1998/04
In the Power Reactor and Nuclear Fuel Development Corporation (PNC), the following are examined as part of an application technology using a high power electron linac : monochromatic gamma ray sources, free electron lasers, and intense positron sources. This report describes an adaptive estimate of a superconducting magnet in order to efficiently converge a positron beam for the development of an intense positron source. By comparing the intensity of a positron beam using a superconducting magnet with a normal conducting magnet, the intensity obtained was more than double. In addition, a small magnet was manufactured in order to examine the characteristics of the superconducting magnet as a solenoid coil. An excitement test was carried out with rated current. As a result of measuring the maximum magnetic field on the central axis, we achieved 5.6 Tesla, which was the designed value. Therefore, it was confirmed to function as a focusing device, when the superconducting magnet was used to converge the positron beam.
; Hishida, Makoto; Takizuka, Takakazu
Genshiryoku Kogyo, 38(1), p.53 - 59, 1992/01
no abstracts in English
Genka, Tsuguo
Radioisotopes, 41(8), p.61 - 62, 1992/00
no abstracts in English
; Kubota, Masumitsu; *; *
JAERI-M 91-147, 191 Pages, 1991/09
no abstracts in English
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JAERI-M 8573, 20 Pages, 1979/11
no abstracts in English
synthesis process for solidification of strontium-90Nihon Genshiryoku Gakkai-Shi, 18(12), p.781 - 785, 1976/12
Times Cited Count：0no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 15(8), p.534 - 543, 1973/08
no abstracts in English
Dambo, 2(8), 2 Pages, 1962/00
no abstracts in English
Yamamoto, Masaya; Sekine, Takashi; Yoshida, Akihiro
no journal, ,
Beyond design basis accident have been evaluated in Joyo. Anticipated transient without scram, loss of reactor level and protected loss of heat sink are identified as main accident sequence group. Unprotected transient over power and protected loss of heat sink are selected as representative accident by the view point of frequency and impact. As the result of safety analysis of these accident, we confirmed that no beyond design basis accident reach to release a large amount of radioactive materials.
Okano, Yasushi; Yamano, Hidemasa; Takata, Takashi; Nishino, Hiroyuki; Kurisaka, Kenichi
no journal, ,
External hazard related to meteorological phenomena may impact on decay heat removal system using ambient air as an ultimate heat sink such as in sodium-cooled fast reactor system. This study identify the combination of external hazards to be considered and the items to be quantified for probabilistic risk assessment from the view point of strength and affecting duration of the hazard in case that secondary external hazard which has predicted appearance frequency overlaps after an primary external hazard which is very rare but high consequence.
