Simulations of the BEAVRS PWR with SCALE and PARCS (NUREG/IA-0529)

On this page:

• Publication Information
• Abstract

Download complete document

• NUREG/IA-0529 (PDF - 4.53 MB)

Publication Information

Manuscript Completed: December 2021
Date Published: December 2022

Prepared by:
Piotr Darnowski, Michal Pawluczyk

Warsaw University of Technology,
Faculty of Power and Aeronautical Engineering,
Institute of Heat Engineering,
Nowowiejska 21/25,
00-665 Warsaw, Poland

K. Tien

Division of Systems Analysis
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Prepared as part of
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Availability Notice

Abstract

The first fuel cycle of the BEAVRS PWR benchmark was simulated and analyzed. Models were prepared using the SCALE package, TRITON depletion sequence and NEWT as a lattice physics solver. A set of branch and burnup calculations were prepared, and group constants in the form of PMAXS libraries were generated using GenPMAXS for PARCS nodal diffusion core simulator. The hot zero power reactor physics measurement data and hot full power data were used to perform model validation simulations for the 1^st fuel cycle. The core inventories for the BOC and EOC were calculated on the basis of PARCS and TRITON results with a dedicated computer code and compared with ORIGEN-ARP point burnup calculations.