Neutronics analysis of improved accident tolerance LWR fuel by modifing Zircaloy cladding of fuel pins

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The present paper describes the progress of an IRP (Integrated Research Project) to evaluate a modified Zircaloy LWR (Light Water Reactor) cladding to improve accident tolerance of LWR fuels. Nuclear fuel pin cladding failure is a major problem in reactor off-normal operational events. This paper presents the results of reactor system neutronics analysis when coating is applied to the surface of the fuel cladding. Various materials are tested as coatings for the modified cladding with 100 micron coating thickness. Some of these materials are expected to prevent or delay the reaction of brittle exothermic oxide formation during steam exposure at increased fuel temperature. These materials are evaluated by their effects on the neutronics requirements of LWR fuel, as well as on the Doppler temperature and moderator void (density) coefficients. Despite only 100 micron coating thickness, some materials are found to have significant negative effect of reactivity of LWR fuel assemblies. In addition, Doppler, moderator temperature and void coefficients are unaffected by most of the coatings, except for some very neutron absorbing materials. This research is used to select materials for the next phase of IRP project, which involves cladding performance testing, and experimental and computational evaluation under normal and off-normal conditions.

Original languageEnglish (US)
Title of host publicationInternational Congress on Advances in Nuclear Power Plants, ICAPP 2014
PublisherAmerican Nuclear Society
Pages159-166
Number of pages8
ISBN (Print)9781632668264
StatePublished - Jan 1 2014
EventInternational Congress on Advances in Nuclear Power Plants, ICAPP 2014 - Charlotte, NC, United States
Duration: Apr 6 2014Apr 9 2014

Publication series

NameInternational Congress on Advances in Nuclear Power Plants, ICAPP 2014
Volume1

Other

OtherInternational Congress on Advances in Nuclear Power Plants, ICAPP 2014
CountryUnited States
CityCharlotte, NC
Period4/6/144/9/14

Fingerprint

Light water reactors
Accidents
Coatings
Moderators
Nuclear fuels
Temperature
Neutrons
Steam
Oxides
Testing

ASJC Scopus subject areas

  • Renewable Energy, Sustainability and the Environment

Cite this

Wu, X., Kozlowski, T., & Heuser, B. J. (2014). Neutronics analysis of improved accident tolerance LWR fuel by modifing Zircaloy cladding of fuel pins. In International Congress on Advances in Nuclear Power Plants, ICAPP 2014 (pp. 159-166). (International Congress on Advances in Nuclear Power Plants, ICAPP 2014; Vol. 1). American Nuclear Society.

Neutronics analysis of improved accident tolerance LWR fuel by modifing Zircaloy cladding of fuel pins. / Wu, Xu; Kozlowski, Tomasz; Heuser, Brent J.

International Congress on Advances in Nuclear Power Plants, ICAPP 2014. American Nuclear Society, 2014. p. 159-166 (International Congress on Advances in Nuclear Power Plants, ICAPP 2014; Vol. 1).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Wu, X, Kozlowski, T & Heuser, BJ 2014, Neutronics analysis of improved accident tolerance LWR fuel by modifing Zircaloy cladding of fuel pins. in International Congress on Advances in Nuclear Power Plants, ICAPP 2014. International Congress on Advances in Nuclear Power Plants, ICAPP 2014, vol. 1, American Nuclear Society, pp. 159-166, International Congress on Advances in Nuclear Power Plants, ICAPP 2014, Charlotte, NC, United States, 4/6/14.
Wu X, Kozlowski T, Heuser BJ. Neutronics analysis of improved accident tolerance LWR fuel by modifing Zircaloy cladding of fuel pins. In International Congress on Advances in Nuclear Power Plants, ICAPP 2014. American Nuclear Society. 2014. p. 159-166. (International Congress on Advances in Nuclear Power Plants, ICAPP 2014).
Wu, Xu ; Kozlowski, Tomasz ; Heuser, Brent J. / Neutronics analysis of improved accident tolerance LWR fuel by modifing Zircaloy cladding of fuel pins. International Congress on Advances in Nuclear Power Plants, ICAPP 2014. American Nuclear Society, 2014. pp. 159-166 (International Congress on Advances in Nuclear Power Plants, ICAPP 2014).
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