Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Adachi, Junichi*; Sasaki, Shinobu; Kaminaga, Masanori; Hino, Ryutaro
FAPIG, (155), p.48 - 54, 2000/07
no abstracts in English
; ; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi
JNC TN9410 2000-002, 149 Pages, 1999/12
JNC-TN9410-2000-002.pdf:23.51MB
LEDF (Large Equipment Dismantling Facility) is the solid waste processing technology development facility that carries out high-volume reduction and low dosage processing. The high-volume reduction processing of the high dose 
-waste configured with combustible waste, pvc & rubber, spent ion exchange resin, and noncombustible waste have been planned the incinerating and melting facility using the in-can type high frequency induction heating in LEDF. This test is intended to clarify the design data. It was confirmed that the incinerating and melting performance, molten solid properties and exhaust gas processing performance with pilot testing equipment and bench scale equipment. The result of this test are as follows. (1)Processing speed is 6.7kg/h for the combustible waste, 13.0kg/h for the ion exchange resin, and 30.0kg/h for the noncombustible waste. For above optimum processing conditions are as follows. (a)Operating temperature is 1000
C for the combustible waste, 1300C for the ion exchange resin, 1500C for the noncombustible waste. (b)Air flow is 90Nm
/h. Air temperature is 300C. Air velocity is 20m/s. (2)Incineration time per day is 5h. Warm-up time and incineration time from the stop of waste charging is 0.5h. Melting time per day is 5h inconsideration of heating hold time of incinerated ash and melting of quartz. Warm-up time is 0.5h. (3)The system decontamination factor in Co, Cs and Ce with pilot testing equipment is 10
or more. (4)Design data of the iron doped silica gel judged to be have a applicability as RuO
gas absorber is as follows. (a)Its diameter distribute in the range of 0.8-1.7mm. (b)To have a decontamination factor of 10 can achieve for retention time of 3 seconds and its life time is about 1 year. (5)In terms of the distribution of the nuclear species in molten solid is evenly distributed. It was also confirmed that the distribution of main elements in ceramic layer is ...
; ; Yoshida, Eiichi; Aoto, Kazumi
JNC TN9400 2000-011, 33 Pages, 1999/03
JNC-TN9400-2000-011.pdf:13.45MB
The damage was observed in rupture disk for the A-loop superheater of sodium-water reaction products releasing system for MONJU on March 3, 1998. Low temperature creep and stress corrosion cracking tests were carried out as the causes investigation of the damage. As the result, the followings are clarified. (1)The possibility that low temperature creep is the principal damage is small. (2)The stress corrosion cracking under NaOH environment due to the reaction of Na vapor and moisture condensed on the surface of glass beads as remains is the most probable cause on the damage. (3)Comparatively many glass beads remained in damaged surface. The gap between rupture disk and vacuum support was narrower than other parts, and they were not directly exposed to the Na vapor for a long time. The above factors caused the perfect intergranular cracking by stress corrosion. Since NaOH was chemically changed into the harmless Na
O on the location except for damaged zone by full Na vapor, the stress corrosion cracking was not generated.
; Yanagihara, Satoshi; Kozaki, Tamotsu*; Tachibana, Mitsuo
Genshiro Kaitai; Anzen Na Taieki No Tameni, 341 Pages, 1993/04
no abstracts in English
Araki, Kunio; ; ; ; ;
JAERI-M 9389, 13 Pages, 1981/03
no abstracts in English
Ogino, Hideki; Nakayoshi, Akira; Yamada, Seiya*
no journal, ,
R&D plan of the characteristics of fuel debris related to package, transportation and storage was devised through the information exchange with the developers' project team of such technology.
Nakayoshi, Akira; Kano, Yoshiharu; Okamura, Nobuo; Koizumi, Kenji; Watanabe, Masayuki; Yamada, Seiya*
no journal, ,
no abstracts in English
Suzuki, Seiya; Nakayoshi, Akira; Okamura, Nobuo; Watanabe, Masayuki; Koizumi, Kenji
no journal, ,
no abstracts in English
Okumura, Keisuke; Terashima, Kenichi; Nagatani, Taketeru; Komeda, Masao; Shiba, Tomooki; Nauchi, Yasushi*; Takada, Akira*; Kosuge, Yoshihiro*
no journal, ,
no abstracts in English
Sasagawa, Tsuyoshi; Shimada, Taro; Takeda, Seiji
no journal, ,
IAEA standard document (GSR part6) requires appropriate dose control and minimization of radioactive waste for decommissioning of nuclear facilities. It is necessary to develop a method to optimize the amount of radioactive waste and the radiation dose. Therefore, we developed a code to evaluate the optimum conditions of dismantling work by calculating the amount of radioactive waste in radioactive level and the radiation dose according to the conditions of the decommissioning process and analyzing the cost-benefit of both results. Furthermore, based on the information of decommissioning of JPDR, the sensitivity analysis was performed for the case of decontamination and dismantling of three kinds of tanks and associated piping, focusing on the size of cut pieces and the type of container. As a result, different trends were observed for the minimum number of containers of the radioactive waste in radioactive level and the minimum dose to workers. The cost-benefit analysis was performed to derive the optimum conditions of the type of container and the size of cut pieces with cost as an index, and the optimization method by the cost-benefit analysis based on the results of the amount of radioactive waste generated in radioactive level and the radiation dose was shown to be applicable.