Prototype Tests for the Recovery and Conversion of UF6 Chemisorbed in NaF Traps for the Molten Salt Reactor Remediation Project

Del Cul, G.D. ; Icenhour, A.S. ; Simmons, D.W.

Oak Ridge National Laboratory

关键词: Charcoal;    Molten Salt Reactors;    Storage;    Removal;    Oxides;   

DOI  :  10.2172/768805
RP-ID  :  ORNL/TM-2000/92
RP-ID  :  AC05-00OR22725
RP-ID  :  768805

美国|英语

来源: UNT Digital Library

【 摘 要 】

The remediation of the Molten Salt Reactor Experiment (MSRE) site includes the removal of about 37 kg of uranium. Of that inventory, about 23 kg have already been removed from the piping system and chemisorbed in 25 NaF traps. This material is being stored in Building 3019. The planned recovery of -11 kg of uranium from the fuel salt will generate another 15 to 19 NaF traps. The remaining 2 to 3 kg of uranium are present in activated charcoal beds, which are also scheduled to be removed from the reactor site. Since all of these materials (NaF traps and the uranium-laden charcoal) are not suitable for long-term storage, they will be converted to a chemical form [uranium oxide], which is suitable for long-term storage. This document describes the process that will be used to recover and convert the uranium in the NaF traps into a stable oxide for long-term storage. Included are a description of the process, equipment, test results, and lessons learned. The process was developed for remote operation in a hot cell. Lessons learned from the prototype testing were incorporated into the process design.