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Sekine, Megumi; Sukegawa, Hidetoshi; Ishikuro, Yasuhiro; Oyama, Koji; Obata, Takashi; Hayashi, Kazuhiko; Inoue, Naoko
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 10 Pages, 2021/08
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) developed the virtual tour of a reference nuclear facility. The developed virtual tour was applied to the Design Information Questionnaire (DIQ) workshop exercise for the online SSAC course held in November 2020 in connection with the IAEA safeguards-related regional training course. Also, it was applied to the Complementary Access (CA) exercise for the online workshop of the Nuclear Security and Safeguards Project under the Forum for Nuclear Cooperation in Asia (FNCA), held in February 2021. The workshop exercises have been implemented for in-person format however due to COVID-19 pandemic, a virtual tour was applied. The virtual tour was found to be a strong tool not only for online training as an alternative for a facility tour, but also considered to be more advantageous even for the in-person training. The developed virtual tour of a reference nuclear facility, going to shut down, can find potentially varied applications. The paper describes how to create a virtual tour of a reference research reactor facility for the DIQ and CA exercises respectively which have different learning objectives. It emphasizes how the features of the reference facility were captured and the challenges encountered to convey to the training participants the importance of providing the required design information while not being physically present at the facility. It also show the advantage of using the same virtual tour to describe the safeguards-related verification activities of a complementary access. Virtual tours can be applied to a variety of training.
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, Yasuhiro; 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, Yasuhiro; Oki, Koichi
JNC TN8410 2004-012, 126 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, Yasuhiro; 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%.
; Sukegawa, Yasuhiro*; Suzuki, Satoshi*; Yoshida, Michihiro; ; *; Miyo, Hiroaki
JNC TN8440 2000-022, 180 Pages, 2000/10
JNC-TN8440-2000-022.pdf:12.16MB
At outside waste strage pits, containers for strage of wastes corroded and were flooded, and it was confirmed on August 26, 1997. Confirmation of contamination of the pits outskirts, installation of sheets to prevent rainwater from flowing into the pits, drawing stay water were executed, promptly. Design and authorization works of the work house and waste treatment devices to take out wastes of the pits were executed too. After construction of the work house, taking out wastes of the pits started, and finished on April 10, 1998. Investigations of the inflow point of rainwater and leak of stay water were executed next. The results were reported to Science and Technology Agency (STA), adjoining authorities on December 21, 1998. After decontamination of the pits inner walls to background level of the radioactivity which included general concrete, control area was removed, and the pits were closed by concrete. Measures of closing of the pits were prepared from the middle of August, 1999, and dismantlement of unnecessary instruments started. Decontamination of the pits started from the beginning of September, 1999. The above works finished on June 30, 2000. After decontamination of the pits, STA, adjoining authorities confirmed the dircumstances. Work pouring concrete into the pits was executed three times (three levels), and finished on August 31, 2000. In addition to above, the amount of concrete poured into the pits was about 1,200 m
. These data compiled the inspection of contamination in measures of closing of the pits.
Yoshida, Michihiro; Suzuki, Satoshi*; Sukegawa, Yasuhiro*; Miyo, Hiroaki
JNC TN8440 2000-021, 180 Pages, 2000/10
JNC-TN8440-2000-021.pdf:42.37MB
At outside waste storage pits, containers for storage of wastes corroded and were flooded, and it was confirmed on August 26, 1997. Confirmation of contamination of the pits outskirts, installation of sheets to prevent rainwater from flowing into the pits, drawing stay water were executed, promptly. Design and authorization works of the work house and waste treatment devices to take out wastes of the pits were executed too. After construction of the work house, taking out wastes of the pits started, and finished on April 10, 1998. Investigations of the inflow point of rainwater and leak of stay water were executed next. The results were reported to Science and Thechnology Agency (STA), adjoining authorities on December 21, 1998. After decontamination of the pits inner walls to background level of the radioactivity which included general concrete, control area was removed, and the pits were closed by concrete. Measures of closing of the pits were prepared from the middle of August, 1999, and dismantlement of unnecessaly instruments started. Decontamination of the pits started fiom the beginning of September, 1999. The above works finished on June 30, 2000. After decontamination of the pits, STA, adjoining authorities confirmed the circumstances. Work pouring concrete into the pits was executed three times (three levels), and finished on August 31, 2000. In addition to above, the amount of concrete poured into the pits was about 1,200 m. This report compiled the photographs of the works from confirmation of stay water at August, 1997 by finish of measures of closing of the pits at September, 2000.
; Ishibashi, Yuzo; Yoshida, Michihiro; Miyo, Hiroaki; Sukegawa, Yasuhiro*; *; Suzuki, Satoshi*
JNC TN8440 2000-020, 500 Pages, 2000/10
JNC-TN8440-2000-020.pdf:25.91MB
At outside waste storage pits, containers for storage of wastes corroded and were flooded, and it was confirmed on August 26, 1997. Confirmation of contamination of the pits outskirts, installation of sheets to prevent rainwater from flowing into the pits, drawing stay water were executed, promptly. Design and authorization works of the work house and waste treatment devices to take out wastes of the pits were executed too. After construction of the work house, taking out wastes of the pits started, and finished on April 10, 1998. Investigations of the inflow point of rainwater and leak of stay water were executed next. The results were reported to Science and Thechnology Agency (STA), adjoining authorities on December 21, 1998. After decontamination of the pits inner walls to background level of the radioactivity which included general concrete, control area was removed, and the pits were closed by concrete. Measures of closing of the pits were prepared from the middle of August, 1999, and dismantlement of unnecessary instruments started. Decontamination of the pits started from the begining of September, 1999. The above works finished on June 30, 2000. After decontamination of the pits, STA, adjoining authorities confirmed the circumstances. Work pouring concrete into the pits was executed three times (three levels), and finished on August 31, 2000. In addition t0 above, the amount of concrete poured into the pits was about 1,200 m.
Omori, Koji; Oki, Koichi; Ishibashi, Yuzo; Numano, Tatsuo; Sunaoshi, Mizuho*; 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
Oki, Koichi; Ishibashi, Yuzo; Muto, Katsumi; Komatsuzaki, Takashi*; Suzuki, Satoshi*; Sukegawa, Yasuhiro*
no journal, ,
no abstracts in English
