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methodSuzuki, Satoshi*; Komatsuzaki, Takashi*; Tadokoro, Hideaki*; Oki, Koichi
JAEA-Review 2011-039, 74 Pages, 2012/01
JAEA-Review-2011-039.pdf:2.6MB
This report summarizes outline, methods and measurement results of actual wastes of nondestructive measurement system using the passive method applied to the evaluation of the quantity of uranium in the drum waste (0.2 m
) and container waste (1 m). The following are the results. (1) The measurement number of drum wastes was 18,884 (4,703 of the number were pit wastes), at the end of March, 2011. (2) The measurement number of container wastes was 749 (110 of the number were pit wastes), at the end of March, 2011. (3) About 60% of drum wastes and about 80% of container wastes were metal and concrete. (4) 75% of drum wastes were less than detection limit, and average of radioactivity is 3.4 Bq (U-238)/g. Then 17% of container wastes were less than detection limit, and average of radioactivity is 2.3 Bq (U-238)/g. (5) If clearance level is 1.0 Bq (U-238)/g (IAEA RS-G-1.7), about 80% of wastes are below the clearance level.
Suzuki, Satoshi*; Komatsuzaki, Takashi*; Sukegawa, Yasuhiro*; Oki, Koichi
JAEA-Technology 2010-035, 134 Pages, 2010/09
JAEA-Technology-2010-035.pdf:22.59MB
It is important in the waste management to evaluate the quantity of radioactivity in the wastes. This report summarizes the improvement, examinations in the nondestructive measurement system using the passive method applied to the evaluation of the quantity of uranium in container waste. Results are followings. (1) Evaluation of the quantity of uranium in container waste was about 
50% against true value. (2) Repeatedly accuracy of the evaluation value is about 50%. (3) The validity of the evaluation to container wastes was confirmed by cross-checking with the system for the drum. (4) When the radioactivity is higher than 1 Bq/g, the facing couple method is effective. (5) If the weight of container is 1t, the detection limit by NaI detector is about 20g (U-238) at the center of container, 3g (U-238) at the surface. Detection limit by Ge detector is about 70g (U-238) at the center, 10g (U-238) at the surface. (6) There is a possibility that about 80% of the container wastes become clearance wastes.
Oki, Koichi; Aoyama, Yoshio; Sukegawa, Yasuhiro*; Suzuki, Satoshi*; Sagawa, Hiroshi*; Hideo, Doi,*; Endo, Yasumi*
Waste Management 2005 Proceeding, CD-ROM, 8p., 8 Pages, 2005/03
We developed as a new technique to remove the influence of distance between radionuclides and detectors. We named the technique "the Facing Couple Method (FCM)". Partcality inspection which uses uranium source was parformed.Furthermore, the application possibility to a system was confirmed.
Sukegawa, Yasuhiro*; Suzuki, Satoshi*; Aoyama, Yoshio; Oki, Koichi
JNC TN8410 2004-012, 117 Pages, 2004/11
JNC-TN8410-2004-012.pdf:6.06MB
This report summarizes the system design carried out in order for the passive gamma method to estimate the uranium content in container waste among uanium wastes, construction of an analysis evaluation code, simulation, performance tests.
Oki, Koichi; Aoyama, Yoshio; Sukegawa, Yasuhiro*; Suzuki, Satoshi*; Sagawa, Hiroshi*; Hideo, Doi,*; Endo, Yasumi*
Saikuru Kiko Giho, (25), p.57 - 68, 2004/00
The system which measures and evaluates the quantity of uranium in the uranium contaminated waste in a large-sized container by NDA technology was manufactured.Practicality inspection which uses an uranium source was performed. Furthermore, the application possibility to a system was confirmed.
Sukegawa, Yasuhiro*; Suzuki, Satoshi*; Yoshida, Michihiro; Oki, Koichi;
JNC TN8440 2002-019, 91 Pages, 2002/11
JNC-TN8440-2002-019.pdf:15.13MB
This report is completed about the measurement test and the proofreading of passive -rays measurement method for Non-destructive assay of uranium in a uranium-contaminated waste. The following are the results of the test. (1)The estimation of the amount of uranium by ionization survey meter is difficult for low intensity of -rays emitted from uranium under about 50g. (2)The estimation of the amount of uranium in the waste by NaI detector is possible in case of only uranium, but the estimation from mixed spectrums with transmission source (60-cobalt) is difficult to confirm target peaks. (3)If daughter nuclides of uranium and thorium chain of uranium ore exist, measurement by NaI detector is affected by -rays from the daughter nuclides seriously. As a result, the estimation of the amount of uranium is difficult. (4)The measurement of uranium in a uranium-contaminated waste by germanium detector is possible to estimate of uranium and other nuclides. (5)As to estimation of the amount of uranium, energy at 1,001keV emitted from 234m-protoactinium radiative equilibrium to 238-uranium had nothing to overlap with other nuclides peaks is effective. The following are the results of measurement precision and sensitivity by the proofreading of germanium detector system. (1)Measurement sensitivity about a 200L drum of Gamma System1(GS1) is 4 g/600sec about 238-uranium, and measurement precision is about 50%. (2)Measurement sensitivity about a 200L drum of Gamma System2(GS2)is 2 g/600sec about 238-uranium, and measurement precision is about 100%.
Omori, Koji; Oki, Koichi; Ishibashi, Yuzo; Numano, Tatsuo; Sunaoshi, Mizuho*; Suzuki, Satoshi*; Sukegawa, Yasuhiro*
no journal, ,
no abstracts in English
Oki, Koichi; Ishibashi, Yuzo; Muto, Katsumi; Komatsuzaki, Takashi*; Suzuki, Satoshi*; Sukegawa, Yasuhiro*
no journal, ,
no abstracts in English
Oki, Koichi; Omori, Koji; Ishibashi, Yuzo; Muto, Katsumi; Sukegawa, Yasuhiro*; Suzuki, Satoshi*
no journal, ,
no abstracts in English
