ACOMS+ 및 학술지 리포지터리 설명회

  • 한국과학기술정보연구원(KISTI) 서울분원 대회의실(별관 3층)
  • 2024년 07월 03일(수) 13:30
 

  • P-ISSN1225-0163
  • E-ISSN2288-8985
  • SCOPUS, ESCI, KCI

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  • P-ISSN 1225-0163
  • E-ISSN 2288-8985

유도결합플라스마 질량분석을 위한 사용후핵연료 중 테크네튬-99의 추출크로마토그래피 분리

Extraction Chromatographic Separation of Technetium-99 from Spent Nuclear Fuels for Its Determination by Inductively Coupled Plasma-Mass Spectrometry

분석과학 / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2004, v.17 no.5, pp.438-442
서무열 (한국원자력연구소)
이창헌 (한국원자력연구소)
한성호 (한국원자력연구소)
박영재 (한국원자력연구소)
지광용 (한국원자력연구소)
김원호 (한국원자력연구소)
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Abstract

To determine the contents of <TEX>$^{99}Tc$</TEX> in the spent PWR (pressurized water reactor) nuclear fuels by ICP-MS (inductively coupled plasma-mass spectrometry), a technetium separation method using an extraction chromatographic resin (TEVA Spec resin) has been established. <TEX>$^{99}Tc$</TEX> was separated from a spent PWR nuclear fuel solution by this separation procedure and its concentration was determined by ICP-MS. The result agrees well with the value calculated by the program ORIGEN 2 and also the value measured by AG MP-1 resin/ICP-MS method described in our previous paper. It can be concluded that the present separation procedure is superior to the AG MP-1 resin procedure with respect to the time required for technetium separation as well as the efficiency of decontamination from other radioactive nuclides.

keywords
technetium, spent nuclear fuel, extraction chromatographic resin, TEVA.Spec resin, ICP-MS


참고문헌

1

(1960.) The Radiochemistry of Technetium,

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