Overview of component testing requirements for a small fluoride-salt-cooled high-temperature reactor

Sacit M. Cetiner, David E. Holcomb, George F. Flanagan, Fred J. Peretz, Graydon L. Yoder

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

Abstract

This article summarizes the information necessary to provide reasonable assurance that components for a small fluoride-salt-cooled high-temperature reactor will meet their functional requirements. In support of the analysis of testing requirements, a simplified, conceptual description of the systems, structures, and components specific to this reactor class was developed. These reactor system elements were divided into major categories based on their functions: (1) reactor core systems, (2) heat transport system, (3) reactor auxiliary cooling system, and (4) instrumentation and controls system. An assessment of technical maturity for each element was made, and a gap analysis was performed to identify specific areas that require further testing. A prioritized list of the testing requirements was then developed. The prioritization was based on both the relative importance of the system to reactor viability, and performance and time requirements to perform the testing. Four types of testing are envisioned: small-scale performance tests at the subcomponent level, functional testing at the component level, functional testing at the system level, and long-duration endurance testing. Fluidic diodes, salt-to-high pressure gas heat exchangers, and coolant siphon breakers are the highest-priority component tests required for demonstrating the viability offluoride-salt-cooled high-temperature reactors.

Original languageEnglish
Title of host publicationInternational Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
Pages766-777
Number of pages12
StatePublished - 2010
EventInternational Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 - San Diego, CA, United States
Duration: Jun 13 2010Jun 17 2010

Publication series

NameInternational Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
Volume1

Conference

ConferenceInternational Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
Country/TerritoryUnited States
CitySan Diego, CA
Period06/13/1006/17/10

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