<abstract xmlns="http://www.w3.org/1999/xhtml"><p>This paper presents an analysis of the Benchmark for Evaluation And Validation of Reactor Simulations (BEAVRS) performed using SCALE 6.1.2 and PARCS 3.2 computer codes. The benchmark specification contains a detailed design, operational data and measurements for a real 4-loop Westinghouse pressurized water reactor (PWR). The lattice physics simulations were prepared using TRITON depletion sequence and NEWT neutron transport solver (SCALE package). The 238-neutron group library based on evaluated nuclear data file – ENDF/B-VII nuclear data libraries was applied. A set of branch and burnup calculations was prepared, and group constants in the form of PMAXS files were generated with GenPMAXS. The full-core models were prepared using the PARCS nodal-diffusion core simulator. The PMAXS libraries were used with PARCS to investigate the core operation. The hot zero power measurement data, including control rod worths and critical boron concentrations, were compared using simulations, and satisfactory results were achieved. The first fuel cycle was simulated, and acceptable agreement with boron letdown curve and measurements were obtained. Finally, conclusions and recommendations for future research were presented.</p></abstract>

This paper presents an analysis of the Benchmark for Evaluation And Validation of Reactor Simulations (BEAVRS) performed using SCALE 6.1.2 and PARCS 3.2 computer codes. The benchmark specification contains a detailed design, operational data and measurements for a real 4-loop Westinghouse pressurized water reactor (PWR). The lattice physics simulations were prepared using TRITON depletion sequence and NEWT neutron transport solver (SCALE package). The 238-neutron group library based on evaluated nuclear data file – ENDF/B-VII nuclear data libraries was applied. A set of branch and burnup calculations was prepared, and group constants in the form of PMAXS files were generated with GenPMAXS. The full-core models were prepared using the PARCS nodal-diffusion core simulator. The PMAXS libraries were used with PARCS to investigate the core operation. The hot zero power measurement data, including control rod worths and critical boron concentrations, were compared using simulations, and satisfactory results were achieved. The first fuel cycle was simulated, and acceptable agreement with boron letdown curve and measurements were obtained. Finally, conclusions and recommendations for future research were presented.

Analysis of the BEAVRS PWR benchmark using SCALE and PARCS

Institute of Heat Engineering, Faculty of Power and Aeronautical Engineering

Nukleonika

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

{"article-title":"Analysis of the BEAVRS PWR benchmark using SCALE and PARCS"}

This paper presents an analysis of the Benchmark for Evaluation And Validation of Reactor Simulations (BEAVRS) performed using SCALE 6.1.2 and PARCS 3.2...

Analysis of the BEAVRS PWR benchmark using SCALE and PARCS

Publicado en línea: 18 jul 2019

Páginas: 87 - 96

Recibido: 21 sept 2017

Aceptado: 21 mar 2019

DOI: https://doi.org/10.2478/nuka-2019-0011

Palabras clave
BEAVRS, nuclear reactor, PARCS, PWR, SCALE, TRITON

© 2019 Piotr Darnowski et al., published by Sciendo

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

Analysis of the BEAVRS PWR benchmark using SCALE and PARCS

Publicado en línea: 18 jul 2019

Páginas: 87 - 96

Recibido: 21 sept 2017

Aceptado: 21 mar 2019

DOI: https://doi.org/10.2478/nuka-2019-0011

Palabras claveBEAVRS, nuclear reactor, PARCS, PWR, SCALE, TRITON

© 2019 Piotr Darnowski et al., published by Sciendo

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

Palabras clave
BEAVRS, nuclear reactor, PARCS, PWR, SCALE, TRITON