Nuclear Engineering and Technology
- Volume 25 Issue 2
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- Pages.259-264
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- 1993
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- 1738-5733(pISSN)
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- 2234-358X(eISSN)
Separation of Pu and Nd from Uranium Matrix by Equilibrated Cation Exchanger for Burnup Measurement of Irradiated Nuclear Fuel
조사후핵연료의 연소도 측정을 위한 동적이온교환체에 의한 우라늄 매질로부터 Pu 및 Nd의 분리
- Joe, Kih-Soo (Korea Atomic Energy Research Institute) ;
- Kim, Jung-Suk (Korea Atomic Energy Research Institute) ;
- Jeon, Young-Shin (Korea Atomic Energy Research Institute) ;
- Han, Sun-Ho (Korea Atomic Energy Research Institute) ;
- Eom, Tae-Yoon (Korea Atomic Energy Research Institute)
- Published : 1993.06.01
Abstract
Ion chromatographic method has been applied for burnup measurement of irradiated nuclear fuel by dynamic system using 1-octanesulfonate as a cation exchanger and
조사후핵연료의 연소도측정에 1-octanesulfonate 를 양이온 교환체로 사용하고
Keywords