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Yamamoto, Masahiko; Kono, Soma; Saegusa, Yu; Kuno, Takehiko; Sekine, Megumi; Inoue, Naoko; Noro, Naoko; Rodriguez, D.; Yamaguchi, Tomoki; Stinett, J.*
Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 10 Pages, 2023/05
The gamma-ray measurement part of the Non-Destructive Assay (NDA) course of safeguards and nuclear material accountancy was developed to focus on gamma-ray measurement allotting two days out of five days. The lectures on the basic characteristics and detection methods and mechanism of gamma-ray detectors were provided as e-learnings which were developed. The part for hands-on exercises were implemented in JAEA facility. Participants have set up each gamma-ray detector, and performed measurements of uranium and the other gamma-ray emitting nuclides. Also, uranium-235 enrichment measurements have been performed. In addition, the participants trained with a handheld gamma-ray spectrometer, HM-5, that is popular for IAEA safeguards as the preparation in the measurement exercise of fresh fuel assemblies in JRR-3, a research reactor facility of JAEA. This paper reports on the development, implementation, and feedback from participants on gamma-ray measurement part of the NDA course.
Nomura, Yasushi; Murazaki, Minoru*; Okuno, Hiroshi
JAERI-Data/Code 2001-029, 120 Pages, 2001/11
no abstracts in English
; ; ; Omori, Eiichi
JNC TN8410 2001-021, 33 Pages, 2001/09
Carbon-14 released from the nuclear facilities is an important radionuclide for the safety assessment, because it tends to accumulate in environment through food chain and has as a significant impact to personal dose. Carbon-14 has been monitored routinely as one of the main gaseous radionuclides exhausted from the Tokai Reprocessing Plant (TRP) since OCtober of 1991. Furthermore, behavior of carbon-14 in TRP has been investigated through the reprocessing operation and the literature survey. This report describes the result of investigation about the behavior of carbon-14 in TRP as followings. (1)Only a very small amount of carbon-14 in the fuel was liberated into the shear off-gas and most of it was liberated into the dissolver of-gass. Part of the carbon-14 was trapped at the caustic scrubber installed in the of-gas treatment process, and untrapped carbon-14 was released into the environment from the main stack. Amount of carbon-14 released from the main stack was about 4.16.5GBq every ton of uranium reprocessed. (2)Carbon-14 trapped at the caustic scrubbers installed in the dissolver off-gas and in the vessel off-gas treatment process is transferred to the low active waste vessel. Amount of carbon-14 transferred to the low active waste vessel was about 5.4 9.6GBq every ton of uranium reprocessed. (3)The total amount of carbon-14 input to TRP was summed up to about 11.915.5 GBq every ton of uranium reprocessed considering the released amount from the main stack and the trapped amount in the off-gas treatment devices. The amount of nitrogen impurity in the initial fuel was calculated about 1522ppm of uranium metal based on the measured carbon-14. (4)The solution in the low active waste vesselis concentrated at the evaporator.Most of the carbon-14 in the solution was transferred into concentrated solution. (5)Tokai vitrification Demonstration Facility (TVF) started to operate in 1994. Since then, carbon-14 has been measured in the ...
Department of JMTR
JAERI-Review 97-006, 113 Pages, 1997/03
no abstracts in English
Department of JMTR
JAERI-Review 95-023, 94 Pages, 1996/02
no abstracts in English
Nakano, Yoshihiro
JAERI-Tech 95-002, 63 Pages, 1995/02
no abstracts in English
Department of JMTR
JAERI-Review 94-012, 83 Pages, 1994/12
no abstracts in English
Saito, Minoru; Yamamoto, Katsumune
Nihon Genshiryoku Gakkai-Shi, 36(4), p.321 - 322, 1994/00
no abstracts in English
Nakano, Yoshihiro
JAERI-M 92-103, 67 Pages, 1992/07
no abstracts in English
Ono, Akio; Osugi, Toshitaka;
JAERI-M 91-186, 63 Pages, 1991/11
no abstracts in English
; R.Abedin-Zadeh*; K.Murakami*
3rd Regional Training Course on State Systems of Accounting for and Control of Nuclear Material, 15 Pages, 1991/00
no abstracts in English
Iwai, Takashi; ; Nakagawa, Tetsuya; ; Miyata, Seiichi; Kawamata, Kazuo; Komukai, Bunsaku; Saito, Junichi; Itabashi, Yukio; ; et al.
JAERI-M 90-027, 28 Pages, 1990/02
no abstracts in English
; ; *; ; ; ; Okamoto, Yoshizo
ANL-RERTR-TM-9, P. 16, 1988/00
no abstracts in English
JAERI-M 82-051, 100 Pages, 1982/06
no abstracts in English
Murakami, Kiyonobu; ; ; Ono, Akio*; ; *; *; *
JAERI-M 9876, 83 Pages, 1982/01
no abstracts in English
;
JAERI-M 7139, 33 Pages, 1977/07
no abstracts in English
*; ; ; Inabe, Teruo; ; *; ;
JAERI-M 7085, 19 Pages, 1977/05
no abstracts in English
Sekiya, Yukou*; Takaki, Naoyuki*; Tonoike, Kotaro
no journal, ,
Fuel pellets may be scattered, in the accident of Fukushima Daiichi Nuclear Power Station, without melting in the containment vessels. Precise information of composition of the burnt BWR fuel assemblies is necessary to study the criticality control method for the scattered fuel pellets. In this study, distribution of residual U enrichment was evaluated, for each of the reactors, using a model of a fuel-rod array in a fuel assembly.