Abstract
The Fluoride High-Temperature Reactor (FHR) technology promises many benefits including passive safety, proliferation-resistant waste forms, and improved economics. However, selection of reliable structural materials and identification of the possible degradation mechanisms for these is important for the licensure and the safe operation of FHRs. In order to address this task, the Georgia Tech led Integrated Research Project (IRP) hosted a Phenomena Identification and Ranking Table (PIRT) panel of experts to address degradation mechanisms and other materials related issues of importance to the FHRs. Materials, ones that come in contact with FLiBe or FLiNaK molten salts or other related environments like high temperature steam etc., were considered in this PIRT. Focus of this PIRT was the metallic alloys, especially the ones that are permitted for the construction of elevated temperature Class A components by the ASME code. Degradation mechanisms considered in this PIRT included chemical degradation, mechanical degradation, radiation degradation, and synergistic effect of these mechanisms that may negatively impact operations or cause some safety concerns for the major structural components of FHRs. Main components which were considered included vessel and primary piping, primary heat exchangers, steam generator vessel, steam generator tubes, intermediate loop piping, valves and pumps. Welds in all structural components were identified as an important class of material, which varies in composition and properties, and needs more attention. Importance of impurity control in molten fluorides considered for FHR was highlighted throughout PIRT panel discussions. This paper gives a summary of important results from the PIRT panel discussions and report.
Original language | English |
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Pages (from-to) | 222-229 |
Number of pages | 8 |
Journal | Annals of Nuclear Energy |
Volume | 123 |
DOIs | |
State | Published - Jan 2019 |
Funding
This work was supported by NEUP Award Number DE-NE0008306. Any opinions, findings, conclusions, or recommendations expressed in this publication are those of the authors and do not necessarily reflect the views of the U.S. Department of Energy Office of Nuclear Energy. The work was also sponsored by the U.S. Department of Energy, under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed and operated by UTBattelle LLC, and under Contract No. DE-AC02-06CH11357 with Argonne National Laboratory, managed and operated by U. Chicago Argonne LLC. This manuscript has been co-authored by UT-Battelle LLC, under Contract No. DE-AC05-00OR22725, and by U. Chicago Argonne LLC under Contract No. DE-AC02-06CH11357, with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan: ( http://energy.gov/downloads/doepublic-access-plan ).
Keywords
- Corrosion
- Fluoride-Salt-Cooled High Temperature Reactors (FHR)
- Material degradation mechanisms
- Phenomena Identification and Ranking
- Structural materials