Extraction of Pm-147 from savannah river site nuclear material management programs

被引：2

作者：

Fenker, K. M. ^{[1
]}

DiPrete, D. P. ^{[1
]}

机构：

[1] Savannah River Natl Lab, Savannah River Site, Aiken, SC 29808 USA

来源：

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2022年 / 331卷 / 12期

关键词：

Radiochemical separation; promethuim-147; Savannah River Site; Used nuclear fuel; URANIUM;

D O I：

10.1007/s10967-022-08558-w

中图分类号：

O65 [分析化学];

学科分类号：

070302 ; 081704 ;

摘要：

The Savannah River Site (SRS) processes used-nuclear fuel to recover uranium. There are many interesting fission products lost in the raffinate from this separation including Pm-147. The goal of this work was to recover Pm-147 from SRS waste solutions. A radiochemical separation method typically used for the determination of Pm-147 and Sm-151 was modified to purify significant quantities of Pm-147 from the H Canyon waste solutions. The developed scheme was tested on a small aliquot of waste solution from the processing of used fuel from the High Flux Isotope Reactor at Oak Ridge National Laboratory.

引用

页码：5033 / 5038

页数：6

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