Pretreatment of americium/curium solutions for vitrification | Zendy

Tracy S. Rudisill | Zendy

AI Assistant Blog Pricing

Home ZAIA Blog

Open Access

Pretreatment of americium/curium solutions for vitrification

Author(s) -

Tracy S. Rudisill

Publication year - 1996

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/565235

Subject(s) - vitrification , curium , americium , nitric acid , radiochemistry , lanthanide , precipitation , fission products , oxalate , actinide , chemistry , nuclear chemistry , plutonium , inorganic chemistry , nuclear physics , ion , physics , organic chemistry , meteorology

Vitrification will be used to stabilize an americium/curium (Am/Cm) solution presently stored in F-Canyon for eventual transport to the heavy isotope programs at Oak Ridge National Laboratory. Prior to vitrification, an in-tank oxalate precipitation and a series of oxalic/nitric acid washes will be used to separate these elements and lanthanide fission products from the bulk of the uranium and metal impurities present in the solution. Pretreatment development experiments were performed to understand the behavior of the lanthanides and the metal impurities during the oxalate precipitation and properties of the precipitate slurry. The results of these experiments will be used to refine the target glass composition allowing optimization of the primary processing parameters and design of the solution transfer equipment

The content you want is available to Zendy users.

Already have an account? Click here to sign in.

Having issues? You can contact us here

Accelerating Research