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Title: Materials challenges for nuclear systems

Journal Article · · Materials Today
 [1];  [2];  [3];  [3]
  1. Univ. of Wisconsin, Madison, WI (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)

The safe and economical operation of any nuclear power system relies to a great extent, on the success of the fuel and the materials of construction. During the lifetime of a nuclear power system which currently can be as long as 60 years, the materials are subject to high temperature, a corrosive environment, and damage from high-energy particles released during fission. The fuel which provides the power for the reactor has a much shorter life but is subject to the same types of harsh environments. This article reviews the environments in which fuels and materials from current and proposed nuclear systems operate and then describes how the creation of the Advanced Test Reactor National Scientific User Facility is allowing researchers from across the U.S. to test their ideas for improved fuels and materials.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1027874
Report Number(s):
INL/JOU-10-20131; PII: S1369702110702200; TRN: US1105284
Journal Information:
Materials Today, Vol. 13, Issue 12; ISSN 1369-7021
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 249 works
Citation information provided by
Web of Science

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Modeling of structural failure of Zircaloy claddings induced by multiple hydride cracks journal September 2018
Comparative Thermal Aging Effects on PM-HIP and Forged Inconel 690 journal March 2018
Effect of symmetrical and asymmetrical tilt grain boundaries on radiation-induced defects in zirconium journal June 2018
Solidification Map of a Nickel-Base Alloy journal December 2013
Nanoscale investigation of deformation characteristics in a polycrystalline silicon carbide journal December 2019
The Fabrication and Characterization of a TiB2/Ni Composite Using Spark Plasma Sintering journal July 2018
Thermal Stability and Mechanical Properties of Low-Activation Single-Phase Ti-V-Ta Medium Entropy Alloys journal August 2019
Thermal Aging and the Hall–Petch Relationship of PM-HIP and Wrought Alloy 625 journal May 2019
Surface modification of structural material for nuclear applications by electron beam melting: enhancement of microstructural and corrosion properties of Inconel 617 journal June 2019
Small scale mechanical testing of irradiated materials journal April 2015
Effect of symmetrical and asymmetrical tilt grain boundaries on the tensile deformation of zirconium bicrystals: a MD-based study journal October 2018
Influence of Metal Additives on Microstructure and Properties of Amorphous Metal–SiOC Composites journal April 2019
Listening to Radiation Damage In Situ: Passive and Active Acoustic Techniques journal November 2019
Core design of long‐cycle small modular lead‐cooled fast reactor journal October 2018
Comparative Study of Two Nanoindentation Approaches for Assessing Mechanical Properties of Ion-Irradiated Stainless Steel 316 journal September 2018
Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors journal December 2012