Modified TTA method for the determination of plutonium

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• 作者：P. Sivakumar (1) prasu@igcar.gov.in
  S. Meenakshi (2)
  S. V. Mohan (1)
  R. V. Subba Rao (1)
  M. Venkataraman (1)
• 关键词：Hydroxyurea – ; TTA – ; Plutonium
• 刊名：Journal of Radioanalytical and Nuclear Chemistry
• 出版年：2012
• 出版时间：October 2012
• 年：2012
• 卷：294
• 期：1
• 页码：93-96
• 全文大小：232.7 KB
• 参考文献：1. Milyukov MS, Gusev NL, Sentyurin LG, Sklyarenko Jerusalem LS (1967) Analytical chemistry of plutonium
  2. Natarajan MV, Subba Rao RV (2007) Role and future trends of analytical chemistry for fast reactor fuel reprocessing. In: Proceedings of DAE-BRNS tropical symposium on role of analytical chemistry in nuclear technology (RACNT), IT-5. BARC, Mumbai, pp 38–43
  3. Zhaowu Z, Jianyu H, Zefu Z, Zhang Y, Weifang Z (2004) J Radioanal Nucl Chem 260(3):601–606
  4. Zhaowu Z, Jianyu H, Zefu Z, Zhang Y, Jianmin Z, Weifang Z (2004) J Radioanal Nucl Chem 262(3):707–711
  5. Natarajan R (2005) In: Proceedings of Indian nuclear society annual conference, IT-X. BARC, Mumbai
  6. Natarajan R (1998) IANCAS Bull 14(2):27–32
  7. Subba Rao RV (1998) Analytical manual for the reprocessing of FBTR fuels
  8. Coleman GH (1965) The radiochemistry of plutonium
  9. Davis W, Gray W (1964) A rapid and specific titrimetric method for the precise determination of uranium using iron(II) sulphate as reductant, Talanta, vol (II), pp 1203–1211
• 作者单位：1. Reprocessing Plant Operations Division, Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, 603 102 India2. Gandhigram Rural University, Gandhigram, 624302 India
• ISSN：1588-2780

文摘

The spent fuel from Fast Breeder Test Reactor of various burnups from 25 to 155 GWd/te is being reprocessed in CORAL (COmpact Reprocessing of Advanced fuels in Lead shielded cell) using a modified PUREX (Plutonium Uranium Recovery by EXtraction) process. Total plutonium (Pu238, 239, 240, 241 & 242) concentration in the sample is analysed by HTTA (Thenoyl Trifluoro Acetone) extraction method wherever interference from other alpha emitting nuclides (Raffinate) and bulk natural uranium (uranium products) are present "as reported by Milyukov et al. (Analytical chemistry of plutonium, 1967) and Natarajan and Subba Rao (BARC, pp. 38–43, 2007)". This method requires the addition of corrosive reagents such as NH₂OH.HCl which is a problem in waste disposal for reduction. A salt-free reagent such as Hydroxyurea is studied as a reducing agent which has the ability to reduce both Pu(VI) and Pu(IV) to Pu(III) "as reported by Zhaowu (260(3):601–606, 2004) and Zhaowu (262(3):707–711, 2004)". Pu(III) thus formed can be easily oxidised to Pu(IV) by NaNO₂ for the extraction of Pu by HTTA.