Development of a full-core reactivity equivalence for FeCrAl enhanced accident tolerant fuel in BWRs

Nathan M. George, Jeffrey J. Powers, G. Ivan Maldonado, Andrew Worrall, Kurt A. Terrani

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

4 Scopus citations

Abstract

The impact of replacing Zircaloy with a candidate iron-chromium-aluminum (FeCrAl) -enhanced accident-tolerant fuel (ATF) cladding material was evaluated for modern 10x10 boiling water reactor (BWR) fuel bundles. The primary objective was to establish fuel design parameters for FeCrAl that match the reactivity lifetime requirements of standard Zircaloy bundles. To compare the neutronic effects of these fuel alterations against standard U02/Zircaloy fuel, a method based on 2D lattice physics was established to estimate excess reactivity at the completion of each reactor operating cycle using a weighted fuel batch scheme. The methodology allows rapid scoping studies to be performed prior to full-core simulations. An additional paper [1] presents the lattice physics and 3D full-core results verifying the reactivity equivalence method for the alternate cladding fuel bundles.

Original languageEnglish
Title of host publication5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015
Subtitle of host publicationAdvances in Nuclear Fuel Management V
PublisherAmerican Nuclear Society
Pages19-30
Number of pages12
ISBN (Electronic)9781510808034
StatePublished - 2015
Event5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015 - Hilton Head, United States
Duration: Mar 29 2015Apr 1 2015

Publication series

Name5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V

Conference

Conference5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015
Country/TerritoryUnited States
CityHilton Head
Period03/29/1504/1/15

Keywords

  • 3D
  • Accident Tolerant Fuel
  • Alternate Cladding
  • BWR
  • FeCrAl

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