VERA Core Simulator Methodology for PWR Cycle Depletion
This paper describes the methodology developed and implemented in MPACT for performing high-fidelity pressurized water reactor (PWR) multi-cycle core physics calculations. MPACT is being developed primarily for application within the Consortium for the Advanced Simulation of Light Water Reactors (CASL) as one of the main components of the VERA Core Simulator, the others being COBRA-TF and ORIGEN. The methods summarized in this paper include a methodology for performing resonance self-shielding and computing macroscopic cross sections, 2-D/1-D transport, nuclide depletion, thermal-hydraulic feedback, and other supporting methods. These methods represent a minimal set needed to simulate high-fidelity models of a realistic nuclear reactor. Results demonstrating this are presented from the simulation of a realistic model of the first cycle of Watts Bar Unit 1. The simulation, which approximates the cycle operation, is observed to be within 50 ppm boron (ppmB) reactivity for all simulated points in the cycle and approximately 15 ppmB for a consistent statepoint. The verification and validation of the PWR cycle depletion capability in MPACT is the focus of two companion papers.
- University of Michigan
- Core Physics, Inc.
- Publication Date:
- OSTI Identifier:
- DOE Contract Number:
- Resource Type:
- Resource Relation:
- Conference: ANS MC2015 - Joint International Conference on Mathematics and Computation, Nashville, TN, USA, 20150419, 20150419
- Research Org:
- Oak Ridge National Laboratory (ORNL); Oak Ridge Leadership Computing Facility (OLCF); Consortium for Advanced Simulation of LWRs (CASL)
- Sponsoring Org:
- Country of Publication:
- United States
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Enter terms in the toolbar above to search the full text of this document for pages containing specific keywords.