Development of an Integrated Performance Model for TRISO-Coated Gas Reactor Particle Fuel Metadata

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Title

  • Main Title Development of an Integrated Performance Model for TRISO-Coated Gas Reactor Particle Fuel

Creator

  • Author: Petti, David Andrew
    Creator Type: Personal
  • Author: Miller, Gregory Kent
    Creator Type: Personal
  • Author: Martin, David George
    Creator Type: Personal
  • Author: Maki, John Thomas
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization

Publisher

  • Name: Idaho National Laboratory
    Place of Publication: [Idaho Falls, Idaho]
    Additional Info: Idaho National Laboratory (INL)

Date

  • Creation: 2005-05-01

Language

  • English

Description

  • Content Description: The success of gas reactors depends upon the safety and quality of the coated particle fuel. The understanding and evaluation of this fuel requires development of an integrated mechanistic fuel performance model that fully describes the mechanical and physico-chemical behavior of the fuel particle under irradiation. Such a model, called PARFUME (PARticle Fuel ModEl), is being developed at the Idaho National Engineering and Environmental Laboratory. PARFUME is based on multi-dimensional finite element modeling of TRISO-coated gas reactor fuel. The goal is to represent all potential failure mechanisms and to incorporate the statistical nature of the fuel. The model is currently focused on carbide, oxide nd oxycarbide uranium fuel kernels, while the coating layers are the classical IPyC/SiC/OPyC. This paper reviews the current status of the mechanical aspects of the model and presents results of calculations for irradiations from the New Production Modular High Temperature Gas Reactor program.

Subject

  • Keyword: Gas Cooled Reactor, Nuclear Technology
  • Keyword: Fuel Particles
  • Keyword: Irradiation
  • STI Subject Categories: 99 - General And Miscellaneous//Mathematics, Computing, And Information Science
  • Keyword: Ineel
  • Keyword: Simulation
  • Keyword: Oxides
  • Keyword: Production
  • Keyword: Nuclear Fuels
  • Keyword: Safety
  • Keyword: Uranium Gas Cooled Reactor, Nuclear Technology
  • Keyword: Oxycarbides
  • Keyword: Coatings
  • Keyword: Evaluation
  • Keyword: Performance

Source

  • Conference: HTR 2002 Conference,Petten, Netherlands,04/22/2002,04/24/2002

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Report No.: INEEL/CON-01-01553
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 911072
  • Archival Resource Key: ark:/67531/metadc889643
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