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- W757872557 abstract "Chang Heon Lee*,Kwang Soon Choi, Jung Suk Kim, Ke Chon Choi,Kwang Yong Jee, and oW n Ho KimKorea Atomic Energy Research Institute, Nuclear Chemistry Research Team, Daejeon 305-600, Korea(Received May 3, 2001) . !# $ %& )* '( , +-. (ICP-AES)/ 012 314 5(6/78 !# 9, :*; ? , @1 +.# C ;1B A . 6 5( ? E D F I GH tri-n-butyl phosphate(TBP)J 9,K 14 L MN Amberlite XAD CO! NP Q RST# UV TBP RSWX MY Z AmberliteXAD-16# NN[ BC ]1 . _` ^ a!X bc ^_# 14 TBP RSN Q Pc defg# a1h , ? i 4j kP# lm C 1B . Pd n Ru# Ko Q7 c ! # P pq$ 3.1% X1c 3E r pm/ @s tC .ABSTRACT. A study has been carried out on the extraction chromatographic separation of fission prod-ucts from spent pressurized water reactor (PWR) fuels for inductively coupled plasma atomic emission spec-trometric analysis. Impregnation capacity of tri-n-butyl phosphate (TBP), which is well known as an extractantin the field of uranium separation from various nuclear grade materials, on Amberlite XAD polymericmacroporous support materials was measured. Amberlite XAD-16 of which the surface area is the highest wasselected as a support material because its TBP impregnation capacity was the largest in Amberlite XADs. Sorp-tion behaviour of this TBP impregnated resin was investigated for the fission product elements using acidicsolutions simulated for dissolver solutions of spent PWR fuels. The parameters affecting the performance ofthe separation system were optimized. The fission product elements studied excluding Pd and Ru were quan-titatively recovered with the precision of less than 3.1%." @default.
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- W757872557 date "2001-01-01" @default.
- W757872557 modified "2023-09-23" @default.
- W757872557 title "Separation of fission product elements from synthetic dissolver solutions of spent pressurized water reactor fuels by TBP/XAD-16/HNO 3 extraction chromatography" @default.
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