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Tru-Fueled VHTRs: Design, Performance, and Applications
GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
  • P. V. Tsvetkov
  • D. E. Ames, II
  • M. L. Pritchard
  • Ayodeji Babatunde Alajo, Missouri University of Science and Technology
  • T. G. Lewis, III
Abstract

The Very High Temperature Reactor (VHTR) is the nearest Generation IV concept. This paper presents results of the U.S. DOE NERI Project on utilization of higher actinides (TRUs and partitioned MAs) as a fuel component for extended-life VHTR configurations. The idea is to approach autonomous operation on a single fuel loading that would allow marketing power units with VHTRs as nuclear batteries for worldwide deployment. The research focus is on possible designs and their advantages and limitations. The project is currently within its third year of studies. Although indicating some technical limitations and challenges, studies of VHTRs with TRUs/MAs definitely suggest promising performance and possibility to utilize the core configurations with TRUs/MAs gaining prolonged operation and self-sustainability.

Meeting Name
GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
Department(s)
Nuclear Engineering and Radiation Science
Document Type
Article - Conference proceedings
Document Version
Citation
File Type
text
Language(s)
English
Rights
© 2007 American Nuclear Society (ANS), All rights reserved.
Publication Date
1-1-2007
Publication Date
01 Jan 2007
Disciplines
Citation Information
P. V. Tsvetkov, D. E. Ames, M. L. Pritchard, Ayodeji Babatunde Alajo, et al.. "Tru-Fueled VHTRs: Design, Performance, and Applications" GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems (2007)
Available at: http://works.bepress.com/ayodeji-alajo/96/