Development and validation of Burn-up Calculation Code IMPC-Burnup2.0 for accelerator-driven sub-critical system

Abstract

Fuel depletion analysis is important for the evolutionary behavior of nuclear materials in the reactor. For the accelerator-driven sub-critical system (ADS), the main research focuses on the transmutation of minor actinides (MA) and long-lived fission products (LLFP). To perform nuclide inventory calculation of ADS, a new nuclide point-depletion code IMPC-Depletion has been developed by utilizing Chebyshev Rational Approximation Method (CRAM) and Transmutation Trajectory Analysis method (TTA) to solve the Bateman equation. Besides, a new burnup code system named IMPC-Burnup2.0 which couples the OpenMC neutron transport code and IMPC-Depletion is also developed to perform burnup behavior analysis of ADS sub-critical system. Finally, the decay of Np237 and fixed neutron flux irradiation of 3.4% UO2 are calculated and compared with other reference results to verify IMPC-Depletion. Moreover, IAEA-ADS and OECD/NEA ADS Minor Actinide Burner benchmark are calculated using IMPC-Burnup2.0 to testing the capability for burnup analysis for ADS sub-critical core. Numerical results show that IMPC-Burnup2.0 is reliable when compared with reference values and it can be used to solve burnup problem of ADS.