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Recent advances in the U.S. fuel cycle R&D Program

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The US Fuel Cycle Research and Development program is investigating advanced nuclear fuel recycle technologies. These technologies must be cost effective, allow for safeguarding of fissile material, and generate minimal waste volumes to enable a sustainable nuclear energy future. The program aims to reduce the long-term radiotoxicity of the used fuel, by separation and transmutation of actinides, so that the majority of the fuel requires management on engineering time scales rather than geologic time scales. Particular emphasis is placed on the separation of americium and curium from the lanthanide elements. An overview of recent results, along with examples of research into innovative technologies, is presented. This is an abstract of a paper presented at the 2010 Spring National Meeting (San Antonio, TX 3/21-25/2010).

Original languageEnglish
Title of host publication10AIChE - 2010 AIChE Spring Meeting and 6th Global Congress on Process Safety
StatePublished - 2010
Event2010 AIChE Spring Meeting and 6th Global Congress on Process Safety, 10AIChE - San Antonio, TX, United States
Duration: Mar 21 2010Mar 25 2010

Publication series

Name10AIChE - 2010 AIChE Spring Meeting and 6th Global Congress on Process Safety

Conference

Conference2010 AIChE Spring Meeting and 6th Global Congress on Process Safety, 10AIChE
Country/TerritoryUnited States
CitySan Antonio, TX
Period03/21/1003/25/10

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