Assessment of PCMI Simulation Using the Multidimensional Multiphysics BISON Fuel Performance Code Metadata

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Title

  • Main Title Assessment of PCMI Simulation Using the Multidimensional Multiphysics BISON Fuel Performance Code

Creator

  • Author: Novascone, Stephen R.
    Creator Type: Personal
  • Author: Hales, Jason D.
    Creator Type: Personal
  • Author: Spencer, Benjamin W.
    Creator Type: Personal
  • Author: Williamson, Richard L.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Office of Nuclear Energy, Science, and Technology.
    Contributor Type: Organization
    Contributor Info: DOE - NE

Publisher

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

Date

  • Creation: 2012-09-01

Language

  • English

Description

  • Content Description: Since 2008, the Idaho National Laboratory (INL) has been developing a next-generation nuclear fuel performance code called BISON. BISON is built using INL’s Multiphysics Object-Oriented Simulation Environment, or MOOSE. MOOSE is a massively parallel, finite element-based framework to solve systems of coupled non-linear partial differential equations using the Jacobian-FreeNewton Krylov (JFNK) method. MOOSE supports the use of complex two- and three-dimensional meshes and uses implicit time integration, which is important for the widely varied time scales in nuclear fuel simulation. MOOSE’s object-oriented architecture minimizes the programming required to add new physics models. BISON has been applied to various nuclear fuel problems to assess the accuracy of its 2D and 3D capabilities. The benchmark results used in this assessment range from simulation results from other fuel performance codes to measurements from well-known and documented reactor experiments. An example of a well-documented experiment used in this assessment is the Third Risø Fission Gas Project, referred to as “Bump Test GE7”, which was performed on rod ZX115. This experiment was chosen because it allows for an evaluation of several aspects of the code, including fully coupled thermo-mechanics, contact, and several nonlinear material models. Bump Test GE7 consists of a base-irradiation period of a full-length rod in the Quad-Cities-1 BWR for nearly 7 years to a burnup of 4.17% FIMA. The base irradiation test is followed by a “bump test” of a sub-section of the original rod. The bump test takes place in the test reactor DR3 at Risø in a water-cooled HP1 rig under BWR conditions where the power level is increased by about 50% over base irradiation levels in the span of several hours. During base irradiation, the axial power profile is flat. During the bump test, the axial power profile changes so that the bottom half of the rod is at approximately 50% higher power than at the base irradiation level, while the power at the top of the rod is at about 20% of the base irradiation power level. 2D BISON simulations of the Bump Test GE7 were run using both discrete and smeared pellet geometry. Comparisons between these calculations and experimental measurements are presented for clad diameter and elongation after the base irradiation and clad profile along the length of the test section after the bump test. Preliminary comparisons between calculations and measurements are favorable, supporting the use of BISON as an accurate multiphysics fuel simulation tool.

Subject

  • STI Subject Categories: 97 Mathematics And Computing
  • Keyword: Code Assessment
  • STI Subject Categories: 22 General Studies Of Nuclear Reactors Code Assessment
  • Keyword: Nuclear Fuels
  • Keyword: Pellet Clad Mechanical Interaction (Pcmi)
  • Keyword: Multiphysics Simulation

Source

  • Conference: Top Fuel: Reactor Fuel Performance 2012,Manchester, United Kingdom,09/02/2012,09/06/2012

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.: INL/CON-12-24744
  • Grant Number: DE-AC07-05ID14517
  • Office of Scientific & Technical Information Report Number: 1055826
  • Archival Resource Key: ark:/67531/metadc844984