13th International Conference on CANDU Fuel - 2016 Aug. 15-18

Presented at:
13th International Conference on CANDU Fuel
2016 Aug. 15-18
Kingston, ON Canada
Session Title:
Session 7: Modelling & Computer Code Development - Fuel Performance

R. Liu (City University of Hong Kong)
W. Zhou (City University of Hong Kong)
A. Prudil (Canadian Nuclear Laboratories)
P. Chan (Royal Military College of Canada)


Light water fuels operate in an environment that involves complex multiphysics phenomena, and the multiphysics behavior is often tightly coupled. A fuel performance code called CityU Advanced Multiphysics Nuclear Fuels Performance with User-defined Simulations (CAMPUS) was developed to predict light water reactor fuel behavior. CAMPUS code considers heat generation and conduction, oxygen diffusion, thermal expansion, elastic strain, densification, and fission product swelling, grain growth, fission gas production and release, gap heat transfer, mechanical contact, gap/plenum pressure with plenum volume, fuel thermal and irradiation creep, cladding thermal and irradiation creep and oxidation. All the equations are implemented into COMSOL Multiphysics ?nite-element platform with a 2D axisymmetric geometry of a fuel pellet with cladding. Comparisons of critical fuel performance parameters for UO2 fuel using CAMPUS are similar to those obtained from BISON, ABAQUS and FRAPCON. The capabilities of the CAMPUS code were further demonstrated by simulating the performance of oxide fuel (UO2), mixed oxide fuel ((Th0.9,U0.1)O2), and accident tolerant fuels, for example, enhanced thermal conductivity UO2-BeO, UO2-SiC and U3Si2 fuels, under normal operation conditions. These demonstrate that CAMPUS is a practical tool not only for the existing LWR fuel performance modeling but also for new fuel design, development and behavior prediction.

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