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THE USA’S ADVANCED REACTOR TECHNOLOGIES (ART) GRAPHITE R&D PROGRAM

Research output: Contribution to conferencePaperpeer-review

Abstract

The USA DOE Advanced Reactor Technologies (ART) graphite R&D program supporting HTR design is one of the longest running nuclear graphite R&D programs. Significant progress has been made in several areas of research within this extensive program including unirraidated and irradiated testing of nuclear graphite, oxidation results and modeling, fracture behavior, irradiation damage studies, and several international collaboration studies. The latest results in these research areas as well as a discussion of a new direction in nuclear graphite irradiation for the USA program will be presented. Recently, the USA made a decision to support moderate to high dose irradiation of nuclear graphite (0.5 to 15 dpa). This will provide irradiation data for graphite HTR core components up to 15 dpa for numerous nuclear graphite grades. The irradiation plan and a tentative schedule for this new irradiation direction will be presented in detail.
Original languageEnglish
StatePublished - Feb 22 2019
Event4th GIF Symposium - Paris, France
Duration: Oct 16 2018Oct 17 2018

Conference

Conference4th GIF Symposium
Country/TerritoryFrance
CityParis
Period10/16/1810/17/18

INL Publication Number

  • INL/JOU-18-52272

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