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JNC TN8440 2000-013, 179 Pages, 2000/04
JNC-TN8440-2000-013.pdf:10.31MB
The plutonium conversion development facility (PCDF) has been operated for 17 years and about 12 tons plutonium-uranium mixed oxide (MOX) powder has been converted since operation started in 1983. The first maintenance program for aging of apparatus was carried out from 1993 to 1994. The calcination-reduction fumace, liquid waste evaporator had been dismantled and renewed. The second maintenance program was carried out form 1998 to 1999. The microwave ovens, powder blender, ventilation control panel and so on were dismantled and renewed. Large volume radioactive wastes were generated during this maintenance such as the furnace, the filter casings and glove boxes. These wastes were too large to be packed into the waste container and these wastes were polluted by MOX powder unfixed on these surface. SO cutting and packing operation for these wastes and recovery of MOX powder from them were carried out. In this report, the method of this cutting and packing operation, the radioactive exposure to the operators in this operation, the estimation of nuclear material quantity migrated to filters, the evaluation of re-floating factor of radioactive material, etc. were discussed.
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JNC TJ8420 2000-010, 171 Pages, 2000/03
JNC-TJ8420-2000-010.pdf:5.34MB
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 ...
PNC TN241 83-22, 166 Pages, 1984/03
Discussion on partial modification of the Monju design is described, corresponding with the results of research and development, and with the advance of detail design. Items discussed are cancellation of the Concrete Cooling System and alterations of the Primary Argon Gas System, the EX-vessel Fuel Storage System, the SHTS Pump and the Solid Waste Processing System. Safety evaluation of the modifications are described according to the necessity.