Challenges and Solutions for Fast Neutron Irradiation of Bulk Material Specimens

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

Abstract

Reactor developers continue to recognize opportunities for further enhancing fast spectrum reactor designs with advanced core materialsMaterials, but all the materialMaterials test reactors currently available to the United States are thermal spectrum designs. Fortunately, the Advanced Test Reactor and High Flux Isotope Reactor are versatile high flux facilities where spectral modification strategies can be used to reduce undesirable thermal neutron capture transmutation damage and augment fast flux delivered to specimens. New opportunities to leverage high flux regions and specially designed fast flux boosting experiment configurations can be used to achieve meaningful fast fluences on large specimens in ATR. New optimizationOptimization potentials can be employed to achieve even higher fluences, albeit for smaller specimens, using thermal neutron filters in HFIR test positions. These capabilities, while not true fast reactors, can provide highly relevant environments for researchers needing to study the effects of fast neutron damageFast neutron damage in bulk materialMaterials specimens.

Original languageEnglish
Title of host publicationTMS 2024 153rd Annual Meeting and Exhibition Supplemental Proceedings
PublisherSpringer Science and Business Media Deutschland GmbH
Pages1499-1513
Number of pages15
ISBN (Print)9783031503481
DOIs
StatePublished - 2024
Event153rd Annual Meeting and Exhibition of The Minerals, Metals and Materials Society, TMS 2024 - Orlando, United States
Duration: Mar 3 2024Mar 7 2024

Publication series

NameMinerals, Metals and Materials Series
ISSN (Print)2367-1181
ISSN (Electronic)2367-1696

Conference

Conference153rd Annual Meeting and Exhibition of The Minerals, Metals and Materials Society, TMS 2024
Country/TerritoryUnited States
CityOrlando
Period03/3/2403/7/24

Keywords

  • Fast neutron damage
  • Fast neutron irradiation
  • Fast reactor cladding
  • Irradiation testing
  • Nuclear fuel and materials

INL Publication Number

  • INL/CON-23-74461

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