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

Journal Article · · Journal of Radioanalytical and Nuclear Chemistry
ORCiD logo [1]; ORCiD logo [2];  [3]
  1. Univ. of Nevada - Las Vegas, Las Vegas, NV (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  3. Univ. of Nevada - Las Vegas, Las Vegas, NV (United States)
+ Show Author Affiliations

Here, 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.

Research Organization:
Los Alamos National Laboratory (LANL)
Sponsoring Organization:
USDOE
Grant/Contract Number:
89233218CNA000001
OSTI ID:
1494476
Report Number(s):
LA-UR-18-24296
Journal Information:
Journal of Radioanalytical and Nuclear Chemistry, Journal Name: Journal of Radioanalytical and Nuclear Chemistry Journal Issue: 3 Vol. 319; ISSN 0236-5731
Publisher:
SpringerCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (1)

Irradiation and isolation of fission products from uranium metal–organic frameworks journal March 2019

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Related Subjects

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
Acid extraction
Catcher
Fission path lengths
Fission products
Recoil energy
UO2 irradiation
Uranium microparticles