Integrated radiation transport and nuclear fuel performance for assembly-level simulations

Steven Hamilton, Kevin Clarno, Bobby Philip, Mark Berrill, Rahul Sampath, Srikanth Allu

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

8 Scopus citations

Abstract

The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting the temperature and strain within a nuclear fuel assembly to evaluate the performance of existing and advanced nuclear fuel bundles within nuclear reactors. AMPFuel was extended to include an integrated nuclear fuel assembly capability for (one-way) coupled radiation transport and nuclear fuel assembly thermo-mechanics. This capability is the initial step toward incorporating an improved predictive nuclear fuel assembly modeling capability to accurately account for source-terms (i.e. neutron flux distribution, coolant conditions, and assembly mechanical stresses) of traditional nuclear fuel performance simulations. A novel scheme is introduced for transferring the power distribution from the SCALE/Denovo (Denovo) radiation transport code (structured, Cartesian mesh with smeared materials within each cell) to AMPFuel (unstructured, hexagonal mesh with a single material within each cell), allowing the use of a relatively coarse spatial mesh for the radiation transport and a fine spatial mesh for thermo-mechanics with very little loss of accuracy. With this new capability, AMPFuel was used to model an entire 17x17 pressurized water reactor fuel assembly with many of the features resolved in three dimensions (for thermo-mechanics and/or neutronics). A full assembly calculation was executed on Jaguar using 40,000 cores in under 10 hours to model over 160 billion degrees of freedom for 10 loading steps. The single radiation transport calculation required about 50% of the time required to solve the thermo-mechanics with a single loading step, which demonstrates that it is feasible to incorporate, in a single code, a high-fidelity radiation transport capability with a high-fidelity nuclear fuel thermo-mechanics capability and anticipate acceptable computational requirements. The results of the full assembly simulation clearly show the axial, radial, and azimuthal variation of the power, temperature, and deformation of the assembly, highlighting behavior that is neglected in traditional axisymmetric fuel performance codes that do not account for assembly features, such as guide tubes and control rods.

Original languageEnglish
Title of host publicationInternational Conference on the Physics of Reactors 2012, PHYSOR 2012
Subtitle of host publicationAdvances in Reactor Physics
Pages2166-2180
Number of pages15
StatePublished - 2012
EventInternational Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012 - Knoxville, TN, United States
Duration: Apr 15 2012Apr 20 2012

Publication series

NameInternational Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics
Volume3

Conference

ConferenceInternational Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012
Country/TerritoryUnited States
CityKnoxville, TN
Period04/15/1204/20/12

Keywords

  • Multiphysics
  • Nuclear fuel performance
  • Thermo-mechanics

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