An integrated model of tritium transport and corrosion in Fluoride Salt-Cooled High-Temperature Reactors (FHRs) – Part I: Theory and benchmarking
Authors:
- John D. StempienJSJohn D. Stempien
- Ronald G. BallingerRBRonald G. Ballinger
- Charles W. ForsbergCFCharles W. Forsberg
- 1 December 2016
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 310, 258-272
Abstract
No abstract availableFunding Information
- Department of Energy (DOE) Nuclear Energy University Program (NEUP) (NEUP14-7476)
- University of Wisconsin-Madison
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