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Journal Articles

Development of training course on non-destructive assay of nuclear material for Asian region, 2; Development of lectures and exercises on gamma-ray measurement

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.

JAEA Reports

Preparation of data relevant to "equivalent uniform burnup" and "equivalent initial enrichment" for burnup credit evaluation

Nomura, Yasushi; Murazaki, Minoru*; Okuno, Hiroshi

JAERI-Data/Code 2001-029, 120 Pages, 2001/11

JAERI-Data-Code-2001-029.pdf:6.16MB

no abstracts in English

JAEA Reports

Behavior of carbon-14 in the Tokai reprocessing plant

; ; ; Omori, Eiichi

JNC TN8410 2001-021, 33 Pages, 2001/09

JNC-TN8410-2001-021.pdf:4.37MB

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 4.1$$sim$$6.5GBq 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$$sim$$ 9.6GBq every ton of uranium reprocessed. (3)The total amount of carbon-14 input to TRP was summed up to about 11.9$$sim$$15.5 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 15$$sim$$22ppm 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 ...

JAEA Reports

Annual report of JMTR, No.10; JMTR operation and technical development (April 1, 1995 $$sim$$ March 31, 1996)

Department of JMTR

JAERI-Review 97-006, 113 Pages, 1997/03

JAERI-Review-97-006.pdf:4.24MB

no abstracts in English

JAEA Reports

Annual report of JMTR, No.9; JMTR operation and technical development April 1, 1994 - March 31, 1995

Department of JMTR

JAERI-Review 95-023, 94 Pages, 1996/02

JAERI-Review-95-023.pdf:4.05MB

no abstracts in English

JAEA Reports

JAEA Reports

Annual report of JMTR, 1993

Department of JMTR

JAERI-Review 94-012, 83 Pages, 1994/12

JAERI-Review-94-012.pdf:2.75MB

no abstracts in English

Journal Articles

16th International Meeting on Reduced Enrichment for Research and Test Reactors

Saito, Minoru; Yamamoto, Katsumune

Nihon Genshiryoku Gakkai-Shi, 36(4), p.321 - 322, 1994/00

no abstracts in English

JAEA Reports

JAEA Reports

Measurement of power distribution in FCA-HCLWR core(Phase-1)

Ono, Akio; Osugi, Toshitaka;

JAERI-M 91-186, 63 Pages, 1991/11

JAERI-M-91-186.pdf:1.5MB

no abstracts in English

Journal Articles

Demonstration of NDA and C/S techniques; Basis for NDA measurement

; 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

JAEA Reports

Release behavior of fission products from irradiated dispersion fuel at high temperature

Iwai, Takashi; ; Nakagawa, Tetsuya; ; Miyata, Seiichi; Kawamata, Kazuo; Komukai, Bunsaku; Saito, Junichi; Itabashi, Yukio; ; et al.

JAERI-M 90-027, 28 Pages, 1990/02

JAERI-M-90-027.pdf:1.24MB

no abstracts in English

Journal Articles

Post-irradiation examination of LEU miniplates in the JMTR

; ; *; ; ; ; Okamoto, Yoshizo

ANL-RERTR-TM-9, P. 16, 1988/00

no abstracts in English

JAEA Reports

JAEA Reports

Critical Experiment for Power Flattening in Plutonium Fuel Lattice, 1; Measurement of Power Distribution

Murakami, Kiyonobu; ; ; Ono, Akio*; ; *; *; *

JAERI-M 9876, 83 Pages, 1982/01

JAERI-M-9876.pdf:3.09MB

no abstracts in English

JAEA Reports

Adeguacy for the Analysis of Mock-up Control Red Experiment on FCA

;

JAERI-M 7139, 33 Pages, 1977/07

JAERI-M-7139.pdf:1.27MB

no abstracts in English

JAEA Reports

Study on Critical Mass of UO$$_{2}$$ Fuel by Calculation with a Transport Code XSDRN

*; ; ; Inabe, Teruo; ; *; ;

JAERI-M 7085, 19 Pages, 1977/05

JAERI-M-7085.pdf:0.7MB

no abstracts in English

Oral presentation

Evaluation of residual uranium enrichment in burnt BWR fuel assembly

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 $$^{235}$$U enrichment was evaluated, for each of the reactors, using a model of a fuel-rod array in a fuel assembly.

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