A UO2-based salt target for rapid isolation of fission products

被引：3

作者：

Dorhout, Jacquelyn M. ^{[1
,2
]}

Wilkerson, Marianne P. ^{[2
]}

Czerwinski, Kenneth R. ^{[1
]}

机构：

[1] Univ Nevada Las Vegas, Dept Chem & Biochem, Las Vegas, NV 89154 USA

[2] Los Alamos Natl Lab, Chem Div, Los Alamos, NM 87545 USA

来源：

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2019年 / 319卷 / 03期

关键词：

Fission products; Recoil energy; UO2; irradiation; Acid extraction; Uranium microparticles; Fission path lengths; Catcher; ACID-ASSISTED SYNTHESIS; COORDINATION POLYMERS; LOS-ALAMOS; NUCLEAR; SEPARATOR; CHEMISTRY; HISTORY;

D O I：

10.1007/s10967-019-06433-9

中图分类号：

O65 [分析化学];

学科分类号：

070302 ; 081704 ;

摘要：

We report here an initial isolation study based upon the use of small uranium oxide particles dispersed in a soluble salt matrix to evaluate the relative recovery of fission products into acidic media. We further show that the macrostructures of the uranium microparticles are largely preserved, such that the bulk target material could be retained for additional irradiations or characterizations. Through this approach, fission products can be separated from the actinide-based target using low molarities of acid without the need to dissolve the actinide itself, reducing the amount of acidic waste. Extraction yields using two molarities of HCl and HNO3 are compared.

引用

页码：1291 / 1300

页数：10

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