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; ; Isozaki, Tokuju; ; ; *
PNC TN8440 97-037, 501 Pages, 1997/10
None
; Chatani, Keiji; ; ;
PNC TN9410 92-224, 81 Pages, 1992/07
The radioactive corrosion product (CP) deposition density and gamma dose rate have been measured along the primary sodium circuits in Experimental Fast Reactor "JOYO" during every annual inspection and the CP behavior analysis code "PSYCHE" has been verified with measurement data in order to contribute the reduction of exposure dose of plant personal. The deposition density is measured by using a pure germanium detector system and determined by multiplying count rates by conversion factor. Gamma dose rate is measured with CaSO
thermoluminescence dosimeters (TLD). This report presents measurement results during the 9th annual inspection and the evaluation results for all data measured so far. The results on this study are summarized as follows: (1)Major CP nuclides deposited along the primary sodium circuits are 
Mn and 
Co. Mn is most dominant isotopes. Amounts of deposited Mn is about twenty times as much as those of Co. (2)Mn is deposited mainly on the cold leg pipings between the outlet of the intermediate heat exchanger (IHX) and the inlet of the reactor vessel. Co is deposited mainly on the hot leg pipings between the outlet of the reactor vessel and the inlet of IHX. (3)The buildup of Mn is saturated at 4
4.5 EFPY. The averaged dose rate of the pipings is saturated at about 1.5mSV/h. The dose rates of IHX and primary sodium pump are about 1.5 mSv/h and 2.1 mSv/h, respectively. The dose rate distributions around IHX and primary sodium pump show the peaks at the stagnant part of the flow and at the turbulence part. (4)Calculation by "PSYCHE" and measurement are compared. Calculation-to-measurement ratio is 1.2 for the CP deposition density and 1.5 for the dose rate. It can be said that the features of the CP behavior in the primary circuit of "JOYO" is made clear. The more effort will be required for the evaluation of CP behavior for subassemblies such as outer reflectors, clearness of ...
Yamamura, Osamu; ; Sugiyama, Toshihide; Ikeda, Hisashi ; ; ;
PNC TN8410 91-169, 166 Pages, 1991/05
None
Miyahara, Kenji; Yamamura, Osamu; Takahashi, Keizo; Sugiyama, Toshihide; ; Ikeda, Hisashi
PNC TN8440 91-022, 42 Pages, 1991/04
This paper is compiled as a record of oral presentation by O.YAMAMURA at RECOD' 91 in April 15. 1991 in Sendai Japan with more than 600 attendance. It contains a proceeding, a manuscript of oral presentation and a manuscript of viewgraphs. The abstract of presentation is as belows. Since the start of construction of the Tokai Reprocessing Plant (TRP) in 1971, large efforts were taken by the Power Reactor and Nuclear Fuel Development Corporation (PNC) and various organizations to root the LWR fuel reprocessing technology in Japan. These efforts produced many achievements around the TRP, and now the future plan for the TRP is being studied.
