Murray Paige, Werth Harmony, Sullivan Sean, Riley Brian J, Simpson Michael, Lonergan Charmayne, Carlson Krista
Department of Chemical and Materials Engineering, University of Nevada, 1664 N Virginal St, Reno, Nevada 89557, United States.
Pacific Northwest National Laboratory, 902 Battelle Boulevard, Richland, Washington 99352, United States.
ACS Omega. 2024 Apr 16;9(17):19395-19400. doi: 10.1021/acsomega.4c00542. eCollection 2024 Apr 30.
Electrochemical processing of spent nuclear fuel in molten chloride salts results in radioactive salt waste. Chlorine removal from the salt has been identified as an effective and efficient first step in the management of high-level waste. In this work, a simple salt was dechlorinated with a phosphoric acid phosphate precursor, resulting in a glassy dechlorinated product. The dechlorination efficacy was evaluated in air and argon environments. This work serves as an initial step to advance the Technological Readiness Level of HPO-based dechlorination step toward implementation of iron phosphate waste forms to immobilize electrochemical fuel reprocessing salt waste streams.
在熔融氯化物盐中对乏核燃料进行电化学处理会产生放射性盐废物。从盐中去除氯已被确定为管理高放废物的有效第一步。在这项工作中，一种简单的盐用磷酸磷酸盐前驱体进行脱氯，得到一种玻璃状的脱氯产物。在空气和氩气环境中评估了脱氯效果。这项工作是迈向提高基于磷酸氢盐脱氯步骤的技术就绪水平的第一步，该步骤旨在实施磷酸铁废物形式以固定电化学燃料后处理盐废物流。
