4.7 Article

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 448, Issue 1-3, Pages 420-435

Publisher

ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2013.06.041

Keywords

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Funding

  1. Advanced Fuels Campaign of the Fuel Cycle R&D program in the Office of Nuclear Energy, U.S. Department of Energy
  2. Laboratory Directed RD funds at ORNL

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Application of advanced oxidation-resistant iron alloys as light water reactor fuel cladding is proposed. The motivations are based on specific limitations associated with zirconium alloys, currently used as fuel cladding, under design-basis and beyond-design-basis accident scenarios. Using a simplified methodology, gains in safety margins under severe accidents upon transition to advanced oxidation-resistant iron alloys as fuel cladding are showcased. Oxidation behavior, mechanical properties, and irradiation effects of advanced iron alloys are briefly reviewed and compared to zirconium alloys as well as historic austenitic stainless steel cladding materials. Neutronic characteristics of iron-alloy-clad fuel bundles are determined and fed into a simple economic model to estimate the impact on nuclear electricity production cost. Prior experience with steel cladding is combined with the current understanding of the mechanical properties and irradiation behavior of advanced iron alloys to identify a combination of cladding thickness reduction and fuel enrichment increase (similar to 0.5%) as an efficient route to offset any penalties in cycle length, due to higher neutron absorption in the iron alloy cladding, with modest impact on the economics. (C) 2013 Elsevier B.V. All rights reserved.

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