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JAEA Reports

Development of the desalting method for gross alpha activity determination (Contract research)

Koike, Yuko; Yamada, Ryohei; Nagaoka, Mika; Nakano, Masanao; Ono, Yosuke; Suitsu, Yuichi

JAEA-Technology 2021-011, 39 Pages, 2021/08

JAEA-Technology-2021-011.pdf:1.56MB

In the Analyzed Liquid Treatment Facility of Japan Nuclear Fuel Co., Ltd. (JNFL) MOX Fuel Fabrication Plant (J-MOX), the interfere by salts with the analysis of gross alpha activity concentration analysis will be caused during the treatment process. Therefore, JNFL devised the desalting method using a solid-phase extraction chromatography. Japan Atomic Energy Agency carried out the experimental study to confirm the validity of this desalting method for the treatment liquid based on the contract with JNFL. This study consists of three experiments as follows: Step 1 - Selection of an optical solid-phase extraction agent, Step 2 - Evaluation of variation optical solid-phase extraction agent, and Step 3 - Application of the imitation liquid waste. The result of Step 1 determined the solid-phase extraction agent (InertSep ME-2) and the optimum condition (aspiration method by manifold (about 5-10 mL/min), 3M nitric acid as eluent, pH: 5, and no adjustment of ionic valence). Then, the result of Step 2 and 3 made sure the validation of this method by obtaining over 70% recovery for the imitation liquid waste sample of the Analyzed Liquid Treatment Facility of J-MOX.

Journal Articles

Parametric studies on nuclear criticality safety design of MOX fuel fabrication facility

Shimizu, Yoshio; Suitsu, Yuichi; Murakami, Tatsutoshi; Yuri, Akiya

Proceedings of 8th International Conference on Nuclear Criticality Safety (ICNC 2007), p.335 - 340, 2007/05

Nuclear criticality safety evaluations for the fast breeder reactor's MOX fuel fabrication facility were performed. In the parametric studies made with SCALE, following three cases are here introduced. (1) The effect of the plutonium isotopic ratio on Pu$$^{*}$$ ($$^{235}$$U, $$^{239}$$Pu, $$^{241}$$Pu) mass control were evaluated. The design conditions of the plutonium isotopic ratio under the operating condition were adjusted from the evaluation. (2) The moderation effects of organic materials in MOX fuel fabrication facility were evaluated. The water contents equivalent moderation effects to organic contents were obtained from the evaluation. (3) The effects of nonuniform mixture of MOX powder and water were evaluated by two-phase model and SMORES. The $$Delta$$k, which differ from the k$$_{eff}$$ of uniform model, were evaluated.

JAEA Reports

None

; Hidano, Tsuyoshi; ; Suitsu, Yuichi

JNC TN8440 99-021, 43 Pages, 1999/04

JNC-TN8440-99-021.pdf:2.16MB

None

Oral presentation

Nuclear criticality safety for the MOX fuel facility, 2; Parametric evaluation of plutonium isotopic composition for mass control limits

Shimizu, Yoshio; Suitsu, Yuichi; Murakami, Tatsutoshi; Yuri, Akiya

no journal, , 

no abstracts in English

Oral presentation

Nuclear criticality safety for the MOX fuel facility, 1; Establishing critical limits

Suitsu, Yuichi; Shimizu, Yoshio; Murakami, Tatsutoshi; Yuri, Akiya

no journal, , 

no abstracts in English

Oral presentation

Nuclear criticality safety for the mox fuel facility, 3; Commitment to the double contingency principle

Yuri, Akiya; Shimizu, Yoshio; Suitsu, Yuichi; Murakami, Tatsutoshi; Ninagawa, Junichi

no journal, , 

no abstracts in English

Oral presentation

Fire and explosion safety in the MOX fuel facility, 2; Accident analysis

Suitsu, Yuichi; Murakami, Tatsutoshi; Yuri, Akiya

no journal, , 

We assumed fire and explosion accidents would occur in the MOX fuel facility of JAEA and reevaluated the radiation dose to the public with a recent method.

Oral presentation

Fire and explosion safety in the MOX fuel facility, 1; Safety design review

Murakami, Tatsutoshi; Suitsu, Yuichi; Yuri, Akiya

no journal, , 

no abstracts in English

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