Evaluation of variability on the thermomechanical response of nitride nuclear fuels through microstructurally explicit models

Manuel Parra Garcia, Sung Ho Park, Kirk Wheeler, Pedro Peralta, Ken McClellan

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

Abstract

A two-dimensional (2D) thermo-mechanical finite element model of a cylindrical fuel pellet seen from the longitudinal plane has been run to investigate variability of the thermo-mechanical response (stress field, strain field, grain boundary interaction, temperature distribution) due to microstructure heterogeneity within a Representative Volume Element (RVE). Microstructural information was obtained from sintered ZrN, as a surrogate for PuN, processed under conditions similar to those used in actinide bearing fuels. The 2D RVE obtained from microstructural characterization via Orientation Imaging Microscopy (OIM), which includes pore and grain geometry as well as grain orientation, is surrounded by "effective material" and located at the center of the model to evaluate the effect of stress and temperature gradients on the local fields. This effort is directed towards the formulation of a framework that can be translated into characterization and modeling of actual fuels to improve simulations of fuel performance. Work supported under the Global Nuclear Energy Partnership (GNEP) and the Advanced Fuel Cycle Initiative (AFCI), DOE/NE Agreement # DE-FC07-05ID14654.

Original languageEnglish (US)
Title of host publicationTMS2008 - 137th Annual Meeting and Exhibition Supplemental Proceedings
Subtitle of host publicationMaterials Processing and Properties
Pages471-476
Number of pages6
StatePublished - 2008
EventTMS 2008 Annual Meeting Supplemental: Materials Processing and Properties - New Orleans, LA, United States
Duration: Mar 9 2008Mar 13 2008

Publication series

NameTMS Annual Meeting
Volume1

Other

OtherTMS 2008 Annual Meeting Supplemental: Materials Processing and Properties
Country/TerritoryUnited States
CityNew Orleans, LA
Period3/9/083/13/08

Keywords

  • Finite element modeling
  • Heat capacity
  • Linear thermal expansion coeffiecient
  • Microstructure
  • Nuclear fuel surrogate
  • Orientation imaging microscopy
  • Representative volume element
  • Thermo-mechanical
  • Volumetric heat generation

ASJC Scopus subject areas

  • Condensed Matter Physics
  • Mechanics of Materials
  • Metals and Alloys

Fingerprint

Dive into the research topics of 'Evaluation of variability on the thermomechanical response of nitride nuclear fuels through microstructurally explicit models'. Together they form a unique fingerprint.

Cite this