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Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

  • Published:2015-12 Issue: Volume:467 Page:703-716
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Yamamoto Y.,Pint B.A.,Terrani K.A.,Field K.G.,Yang Y.,Snead L.L.

Funder

UT-Battelle, LLC

U.S. Department of Energy

DOE Public Access Plan

U.S. Department of Energy's Office of Nuclear Energy, Advanced Fuel Campaign of the Fuel Cycle R&D program

Scientific User Facilities Division, Office of Basic Energy Sciences, U.S. Department of Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference53 articles.

1. Current knowledge on core degradation phenomena, a review

2. NUREG-0630; U. S. Nuclear Regulatory Commission;Powers,1980

3. NUREG/CR-6967; U.S. NRC;Billone,2008

4. Oxidation of Zircaloy by steam

5. Synopsis and outcome of the QUENCH experimental program
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