Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

Conference · Sun Jan 01 00:00:00 EST 2012

OSTI ID:1039625

Hamilton, Steven P ^[1]; Clarno, Kevin T ^[1]; Philip, Bobby ^[1]; Berrill, Mark A ^[1]; Sampath, Rahul S ^[1]; Allu, Srikanth ^[1]

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1. ORNL

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 and safety of existing and advanced nuclear fuel bundles within existing and advanced 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, such as neutron flux distribution, coolant conditions and assembly mechanical stresses, of traditional (single-pin) nuclear fuel performance simulation. 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 (10 million elements) for the radiation transport and a fine spatial mesh (3.3 billion elements) for thermo-mechanics with very little loss of accuracy. With this novel capability, AMPFuel was used to model an entire 1717 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 neutron flux, 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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1039625
• Resource Relation: Conference: PHYSOR 2012, Knoxville, TN, USA, 20120415, 20120420
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ACCURACY
CONTROL ELEMENTS
COOLANTS
DEFORMATION
DEGREES OF FREEDOM
DIMENSIONS
DISTRIBUTION
GUIDE TUBES
NEUTRON FLUX
NUCLEAR FUELS
PERFORMANCE
POWER DISTRIBUTION
PWR TYPE REACTORS
RADIATION TRANSPORT
REACTORS
SAFETY
SIMULATION
SOURCE TERMS
STRAINS
STRESSES
multiphysics
nuclear fuel performance
thermomechanics