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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.6
- 수록면
- 727 - 732 (6page)
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초록· 키워드
오류제보하기
A simple and rapid spectrophotometric method has been developed to enable the determinationof plutonium concentration in an irradiated fuel solution in the presence of allfission products. An excess of ceric ammonium nitrate solution was employed to oxidizeall the valence states of plutonium to þ6 oxidation state. Interference due to the presenceof fission products such as ruthenium and zirconium, and corrosion products such as ironin the envisaged concentration range, as in the irradiated fuel solution, was studied in thedetermination of plutonium concentration by the direct spectrophotometric method. Thestability of plutonium in þ6 oxidation state was monitored under experimental conditionsas a function of time. Results obtained are reproducible, and this method is applicable toradioactive samples resulting before the solvent extraction process during the reprocessingof fast reactor spent fuel. An analysis of the concentration of plutonium shows a relativestandard deviation of <1.2% in standard as well as in simulated conditions. This reflects thefast reactor fuel composition with respect to uranium, plutonium, fission products such asruthenium and zirconium, and corrosion products such as iron.
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참고문헌 (19)
참고문헌 신청
R. Natarajan / 1998 / Challenges in fast reactor fuel reprocessing / IANCAS Bull 14:27~32
R. Natarajan / 2007 / Fast reactor fuel reprocessing technology in India / J. Nucl. Sci. Technol 44:393~397
W.B. Lanham / 1949 / Purex process for plutonium and uranium recovery USAEC / ORNL 479
R. Natarajan / 2013 / Optimization of flow sheet for scrubbing of ruthenium in reprocessing of fast reactor spent fuel / Sep. Sci. Technol 48:2494~2498
W. Davies / 1964 / A rapid and specific titrimetric method for the precise determination of uranium using iron(II)sulphate as reductant / Talanta 11:1203~1211
R. Natarajan / 2007 / Fast reactor fuel reprocessing technology in India / J. Nucl. Sci. Technol 44:393~397
W.B. Lanham / 1949 / Purex process for plutonium and uranium recovery USAEC / ORNL 479
R. Natarajan / 2013 / Optimization of flow sheet for scrubbing of ruthenium in reprocessing of fast reactor spent fuel / Sep. Sci. Technol 48:2494~2498
W. Davies / 1964 / A rapid and specific titrimetric method for the precise determination of uranium using iron(II)sulphate as reductant / Talanta 11:1203~1211
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