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Iguchi, Tetsuo*; Hasegawa, Makoto; Takahashi, Kuniaki; Enokido, Yuji*
Dekomisshoningu Giho, (52), p.12 - 19, 2015/09
no abstracts in English
Nakayama, Fusao*; Enokido, Yuji*; Yoshida, Eiichi; Matsumoto, Toshiyuki; Hasebe, Shinichi
JNC TN9420 2005-001, 115 Pages, 2005/03
JNC-TN9420-2005-001.pdf:9.24MB
None
; ; ; Tanimoto, Kenichi; Enokido, Yuji
PNC TN9410 93-053, 99 Pages, 1993/03
It is must deceasse the pool risk for the radio active wastes. So it is necessary to decontaminate the wastes low level 
(
500
Sv/h) during control the secendry wastes. Had been product the decontaminations hood system for scattaring proof. For that, high-pressure ice brasting method tested using the system. The number of the test piece was 12 from MMF. The resultes is as follows; (1)The hood system have good capacity for scattering proof and remort handling. (2)Aa the test condition, the pressure and the flux was used 9kgf/cm
and 6m
/min, feed volume was used 2kg/min. From the results, the number of test piece being low level (500Sv/H) was 7, containing of ten several mSv/h wastes, from among. The lesves could not decontaminate. (3)The contamination in the hood was decreased from 87mSv/h to 3mSv/h by nomal pressuer icebrasting (the pressure is 4kgf/cm, 2m/min, the feed volume is 1 kg/min).
; Enokido, Yuji;
Proceedings of 2nd ASME-JSME International Conference on Nuclear Engineering (ICONE-2), p.813 - 819, 1993/00
None
Tanimoto, Kenichi; ; ; Kikuchi, Yutaka; ; Enokido, Yuji
Donen Giho, (84), p.21 - 34, 1992/12
None
; ; ; Tanimoto, Kenichi; Enokido, Yuji
PNC TN9410 92-208, 68 Pages, 1992/07
The plan of the gelogic disposal of high level waste that need to do estimate the effect of radiation in near field surrouding waste. We have applied "JOYO" spent fuel storage pool as irradiation field and investigated the effect of gamma radiation about quality of groundwater, because we have to obtained a basic data related geologic dispose under irradiaton condition. The experiment was applied artificial brine for simulated groundwater. The same samples were located in "JOYO" spent fuel storage pool without gamma radiation and other effects were estimated. The samples were also observed the variation of quality of artifical brine every fixed time after irradiation and were estimated the effect as the function of time, gamma irradiation were carried out from 24hours (1.0
10
1.310Gy) to 1440 hours (4.410
6.810Gy). The results indicate the following. (1)The change of pH, conductivity and ion concentrations in artifical brine could not be observed in the samples before and after irradiation. (2)Eh of the samples was 241mV before irradiation, but it decreased 156mV after irradiaton for 1440 hours. Eh tend to decrease by increase of the absorption dose. (3)Do of the samples before and after irradiation for 1440 hours were 20.76 and 5930 g/
, respectively. Do tend to increases by increase of the absorption dose. (4)Before and after irradiation test for 480 hours, nitric ion was detected 2.9 and 105ppm, respectively, In no gamma irradiaton test, nitric ion was detdcted 4.0 and 5.6ppm, respectively. For 1440 hours, nitric ion was detected 15ppm after irradiation and 11ppm after rest without gamma irradiation. (5)pH, Eh, Do, conductivity and all ion concentrations in artifical brine have no the variation as the function ot time within fixed time (about 4hours) after irradiation. These results suggest that oxygen which were generated by the gamma radiolysis of water was incrased Do, ...
; Nakano, Tomoyuki; ; ; Asami, Makoto*; Tanimoto, Kenichi; Enokido, Yuji
PNC TN9080 92-001, 107 Pages, 1992/01
None
Enokido, Yuji*; ; ; Onishi, Nobuaki; ; Shiozawa, Shusaku
Nihon Genshiryoku Gakkai-Shi, 31(7), p.742 - 772, 1989/07
no abstracts in English
; Ukai, Shigeharu; Unno, Ichiro; ; Shibahara, Itaru*; Enokido, Yuji*
PNC TN9410 88-206, 71 Pages, 1988/12
None
Unno, Ichiro; Ukai, Shigeharu; ; ; Shibahara, Itaru*; Enokido, Yuji*
PNC TN9410 88-186, 62 Pages, 1988/02
None
; ; Ukai, Shigeharu; Unno, Ichiro; ; Shibahara, Itaru*; Enokido, Yuji*
PNC TN9410 87-189VOL2, 103 Pages, 1987/02
PNC-TN9410-87-189VOL2.pdf:13.74MB
None
; ; Ukai, Shigeharu; Unno, Ichiro; ; Shibahara, Itaru*; Enokido, Yuji*
PNC TN9410 87-189VOL1, 45 Pages, 1987/02
PNC-TN9410-87-189VOL1.pdf:5.59MB
None
Ukai, Shigeharu; ; ; Enokido, Yuji
Journal of Nuclear Materials, 149(3), p.209 - 218, 1987/00
None
; Enokido, Yuji*; Hasegawa, Masahiro; ; Ogata, Yoshiaki
PNC TN9410 85-143, 91 Pages, 1985/08
None
; Enokido, Yuji*;
PNC TN9410 85-139, 89 Pages, 1985/04
Nondestructive examination of subassembly and its fuel elements of two "JOYO" MK-I Core Fuel Subassemblies (Fab. No. PPJD18 and PPJD1J) has been performed. The subassembly (PPJD18)was adjoin in the control rod and its average burnup was 26,700 MWD/MTM. The subassembly (PPJD1J) was adjoin in the blanket fuel subassembly and its average burnup was 23,600 MWD/MTM. The purposes of the Examination were inspected adjoin-effects in the control rod and the blanket about each subassemblies. (1)There was no deterioration of the subassemblies and their fuel elements. (2)The circumferential activation profiles of Wrapper tube by measure Y-intensity a steep slope in reactor center direction for <PPJDIJ> than <PPJD18>. It seems that this phenomenon is difference from position in reactor of both subassemblies. (3)The bowing of outer-most fuel pins in both subassemblies were large. It was confirmed that the fuel pins locates at the surface of Wrapper tube with the direction of reactor center bowed much larger than the others. (4)Fuel densification was detected by X-ray radiography in subassembly by <PPJD1J> which adjoined in blanket fuel. (5)The results of Gas pressure in <PPJD1J> detected low data that seem under the influence of position in reactor.
