Accident tolerant fuels for LWRs: A perspective

S. J. Zinkle; K. A. Terrani; J. C. Gehin; L. J. Ott; L. L. Snead

doi:10.1016/j.jnucmat.2013.12.005

Accident tolerant fuels for LWRs: A perspective

S. J. Zinkle
, K. A. Terrani
, J. C. Gehin
, L. J. Ott
, L. L. Snead

Materials Science and Engineering

Oak Ridge National Laboratory
University of Tennessee

Research output: Contribution to journal › Article › peer-review

1131 Scopus citations

Abstract

The motivation for exploring the potential development of accident tolerant fuels in light water reactors to replace existing Zr alloy clad monolithic (U, Pu) oxide fuel is outlined. The evaluation includes a brief review of core degradation processes under design-basis and beyond-design-basis transient conditions. Three general strategies for accident tolerant fuels are being explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr alloy cladding with an alternative oxidation-resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.

Original language	English
Pages (from-to)	374-379
Number of pages	6
Journal	Journal of Nuclear Materials
Volume	448
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2013.12.005
State	Published - May 2014

Access to Document

10.1016/j.jnucmat.2013.12.005

Cite this

@article{0540224ec2a14e73ace2880cbe2f7d5d,

title = "Accident tolerant fuels for LWRs: A perspective",

abstract = "The motivation for exploring the potential development of accident tolerant fuels in light water reactors to replace existing Zr alloy clad monolithic (U, Pu) oxide fuel is outlined. The evaluation includes a brief review of core degradation processes under design-basis and beyond-design-basis transient conditions. Three general strategies for accident tolerant fuels are being explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr alloy cladding with an alternative oxidation-resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.",

author = "Zinkle, \{S. J.\} and Terrani, \{K. A.\} and Gehin, \{J. C.\} and Ott, \{L. J.\} and Snead, \{L. L.\}",

year = "2014",

month = may,

doi = "10.1016/j.jnucmat.2013.12.005",

language = "English",

volume = "448",

pages = "374--379",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

number = "1-3",

}

TY - JOUR

T1 - Accident tolerant fuels for LWRs

T2 - A perspective

AU - Zinkle, S. J.

AU - Terrani, K. A.

AU - Gehin, J. C.

AU - Ott, L. J.

AU - Snead, L. L.

PY - 2014/5

Y1 - 2014/5

N2 - The motivation for exploring the potential development of accident tolerant fuels in light water reactors to replace existing Zr alloy clad monolithic (U, Pu) oxide fuel is outlined. The evaluation includes a brief review of core degradation processes under design-basis and beyond-design-basis transient conditions. Three general strategies for accident tolerant fuels are being explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr alloy cladding with an alternative oxidation-resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.

AB - The motivation for exploring the potential development of accident tolerant fuels in light water reactors to replace existing Zr alloy clad monolithic (U, Pu) oxide fuel is outlined. The evaluation includes a brief review of core degradation processes under design-basis and beyond-design-basis transient conditions. Three general strategies for accident tolerant fuels are being explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr alloy cladding with an alternative oxidation-resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.

UR - https://www.scopus.com/pages/publications/84899648832

U2 - 10.1016/j.jnucmat.2013.12.005

DO - 10.1016/j.jnucmat.2013.12.005

M3 - Article

AN - SCOPUS:84899648832

SN - 0022-3115

VL - 448

SP - 374

EP - 379

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3

ER -

Accident tolerant fuels for LWRs: A perspective

Abstract

Access to Document

Other files and links

Fingerprint

Cite this