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Title: Materials challenges for nuclear systems

Abstract

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.

Authors:
 [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)
Publication Date:
Research Org.:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1027874
Report Number(s):
INL/JOU-10-20131
Journal ID: ISSN 1369-7021; PII: S1369702110702200; TRN: US1105284
Grant/Contract Number:  
AC07-05ID14517
Resource Type:
Accepted Manuscript
Journal Name:
Materials Today
Additional Journal Information:
Journal Volume: 13; Journal Issue: 12; Journal ID: ISSN 1369-7021
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CONSTRUCTION; FISSION; LIFETIME; NUCLEAR POWER; TEST REACTORS; challenges; degradation; fuels; LWR; materials

Citation Formats

Allen, Todd, Busby, Jeremy, Meyer, Mitch, and Petti, David. Materials challenges for nuclear systems. United States: N. p., 2010. Web. doi:10.1016/S1369-7021(10)70220-0.
Allen, Todd, Busby, Jeremy, Meyer, Mitch, & Petti, David. Materials challenges for nuclear systems. United States. https://doi.org/10.1016/S1369-7021(10)70220-0
Allen, Todd, Busby, Jeremy, Meyer, Mitch, and Petti, David. Fri . "Materials challenges for nuclear systems". United States. https://doi.org/10.1016/S1369-7021(10)70220-0. https://www.osti.gov/servlets/purl/1027874.
@article{osti_1027874,
title = {Materials challenges for nuclear systems},
author = {Allen, Todd and Busby, Jeremy and Meyer, Mitch and Petti, David},
abstractNote = {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.},
doi = {10.1016/S1369-7021(10)70220-0},
journal = {Materials Today},
number = 12,
volume = 13,
place = {United States},
year = {Fri Nov 26 00:00:00 EST 2010},
month = {Fri Nov 26 00:00:00 EST 2010}
}

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Works referenced in this record:

Cladding and duct materials for advanced nuclear recycle reactors
journal, January 2008


Materials Challenges for Generation IV Nuclear Energy Systems
journal, June 2008

  • Allen, T. R.; Sridharan, K.; Tan, L.
  • Nuclear Technology, Vol. 162, Issue 3
  • DOI: 10.13182/NT08-A3961

Advanced Structural Materials and Cladding
journal, January 2009

  • Allen, T.; Burlet, H.; Nanstad, R. K.
  • MRS Bulletin, Vol. 34, Issue 1
  • DOI: 10.1557/mrs2009.8

Radiation damage concerns for extended light water reactor service
journal, July 2009


Final Report Inspection of Aged/Degraded Containments Program.
report, September 2005

  • Naus, Dan J.; Ellingwood, B. R.; Oland, C. Barry
  • Research Gate
  • DOI: 10.2172/974576

Report on aging of nuclear power plant reinforced concrete structures
report, March 1996

  • Naus, D. J.; Oland, C. B.; Ellingwood, B. R.
  • Semantic Scholar
  • DOI: 10.2172/219361

Nuclear fuels – Present and future
journal, May 2009


Failure Thresholds of High Burnup BWR Fuel Rods under RIA Conditions
journal, January 2004

  • Nakamura, Takehiko; Fuketa, Toyoshi; Sugiyama, Tomoyuki
  • Journal of Nuclear Science and Technology, Vol. 41, Issue 1
  • DOI: 10.1080/18811248.2004.9715455

Hydride fuel for LWRs—Project overview
journal, August 2009


The DOE advanced gas reactor fuel development and qualification program
journal, September 2010


Thirty years of fuels and materials information from EBR-II
journal, April 1999


History of fast reactor fuel development
journal, September 1993


The EFTTRA-T4 experiment on americium transmutation
journal, December 2000


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Modeling of structural failure of Zircaloy claddings induced by multiple hydride cracks
journal, September 2018

  • Liu, Ruijie; Mostafa, Ahmed; Liu, Zhijun
  • International Journal of Fracture, Vol. 213, Issue 2
  • DOI: 10.1007/s10704-018-0312-9

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

  • Singh, Divya; Parashar, Avinash
  • Journal of Physics D: Applied Physics, Vol. 51, Issue 26
  • DOI: 10.1088/1361-6463/aac561

Solidification Map of a Nickel-Base Alloy
journal, December 2013

  • Blecher, J. J.; Palmer, T. A.; DebRoy, T.
  • Metallurgical and Materials Transactions A, Vol. 45, Issue 4
  • DOI: 10.1007/s11661-013-2149-1

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journal, December 2019


The Fabrication and Characterization of a TiB2/Ni Composite Using Spark Plasma Sintering
journal, July 2018

  • Wang, Miao; Wang, Wen-xian; Zhou, Jun
  • Transactions of the Indian Institute of Metals, Vol. 71, Issue 10
  • DOI: 10.1007/s12666-018-1366-0

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journal, August 2019


Thermal Aging and the Hall–Petch Relationship of PM-HIP and Wrought Alloy 625
journal, May 2019


Small scale mechanical testing of irradiated materials
journal, April 2015

  • Hosemann, P.; Shin, C.; Kiener, D.
  • Journal of Materials Research, Vol. 30, Issue 9
  • DOI: 10.1557/jmr.2015.26

Effect of symmetrical and asymmetrical tilt grain boundaries on the tensile deformation of zirconium bicrystals: a MD-based study
journal, October 2018

  • Singh, Divya; Parashar, Avinash; Kedharnath, A.
  • Journal of Materials Science, Vol. 54, Issue 4
  • DOI: 10.1007/s10853-018-3032-7

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

  • Nguyen, Tung Dong Cao; Choe, Jiwon; Ebiwonjumi, Bamidele
  • International Journal of Energy Research, Vol. 43, Issue 1
  • DOI: 10.1002/er.4258

Comparative Study of Two Nanoindentation Approaches for Assessing Mechanical Properties of Ion-Irradiated Stainless Steel 316
journal, September 2018

  • Saleh, Michael; Zaidi, Zain; Hurt, Christopher
  • Metals, Vol. 8, Issue 9
  • DOI: 10.3390/met8090719

Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors
journal, December 2012

  • Anderoglu, Osman; Byun, Thak Sang; Toloczko, Mychailo
  • Metallurgical and Materials Transactions A, Vol. 44, Issue S1
  • DOI: 10.1007/s11661-012-1565-y