Effects of control blade history, axial coolant density profiles, and axial burnup profiles on BWR Burnup Credit

Brian J. Ade, William J. Marshall, Stephen M. Bowman, Jesus S. Martinez

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

2 Scopus citations

Abstract

A technical basis for peak reactivity boiling water reactor (BWR) burnup credit (BUC) methods was recently generated, and the technical basis for extended BWR BUC beyond peak reactivity is now being developed. In this paper, a number of effects related to extended BWR BUC are analyzed, including three major operational effects in BWRs: the coolant density axial distribution, the use of control blades during operation, and the axial burnup profile. Specifically, uniform axial coolant density profiles are analyzed and compared to results for realistic coolant density profiles taken from operating data. A new temporal fidelity study was performed for the coolant density profile change as a function of operating time by consecutively simulating the coolant density profiles first-, second-, and third-cycle fuel assemblies. Realistic control blade histories and their impact on cask reactivity are also analyzed. Preliminary analysis of the axial burnup profile is also provided.

Original languageEnglish
Title of host publicationPhysics of Reactors 2016, PHYSOR 2016
Subtitle of host publicationUnifying Theory and Experiments in the 21st Century
PublisherAmerican Nuclear Society
Pages2856-2871
Number of pages16
ISBN (Electronic)9781510825734
StatePublished - 2016
EventPhysics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016 - Sun Valley, United States
Duration: May 1 2016May 5 2016

Publication series

NamePhysics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century
Volume5

Conference

ConferencePhysics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016
Country/TerritoryUnited States
CitySun Valley
Period05/1/1605/5/16

Keywords

  • BWR
  • Burnup credit
  • Spent nuclear fuel
  • Storage
  • Transportation

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