Coupled neutronics and thermal-hydraulic solution of a full-core PWR using VERA-CS

Scott Palmtag, Kevin Clarno, Greg Davidson, Tom Evans, John Turner, Kenneth Belcourt, Russell Hooper, Rod Schmidt

Research output: Contribution to conferencePaperpeer-review

28 Scopus citations

Abstract

The Consortium for Advanced Simulation of Light Water Reactors (CASL) is developing a core simulator called VERA-CS to model operating pressurized water reactors (PWRs) with high resolution. This paper describes how the development of VERA-CS is being driven by a set of progression benchmark problems that specify the delivery of useful capability in discrete steps. As part of this development, this paper will describe the current capability of VERA-CS to perform a multiphysics simulation of an operating PWR at Hot Full Power (HFP) conditions using a set of existing computer codes coupled together in a novel method. Results for several single-assembly cases are shown that demonstrate coupling for different boron concentrations and power levels. Finally, high-resolution results are shown for a full-core PWR reactor modeled in quarter-symmetry.

Original languageEnglish
StatePublished - 2014
Event2014 International Conference on Physics of Reactors, PHYSOR 2014 - Kyoto, Japan
Duration: Sep 28 2014Oct 3 2014

Conference

Conference2014 International Conference on Physics of Reactors, PHYSOR 2014
Country/TerritoryJapan
CityKyoto
Period09/28/1410/3/14

Funding

This research was supported by the Consortium for Advanced Simulation of Light Water Reactors (www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725. This research used resources of the Oak Ridge Leadership Computing Facility at the Oak Ridge National Laboratory, which is supported by the Office of Science of the U.S. Department of Energy under Contract No. DE-AC05-00OR22725. This research also used resources of the High Performance Computing Center at the Idaho National Laboratory. This manuscript has been co-authored by the Oak Ridge National Laboratory, managed by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the US Department of Energy. The US Government retains and the publisher, by accepting the article for publication, acknowledges that the US Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US Government purposes.

Keywords

  • Core Simulator
  • Multiphysics
  • Neutron Transport
  • Subchannel Thermal-Hydraulics

Fingerprint

Dive into the research topics of 'Coupled neutronics and thermal-hydraulic solution of a full-core PWR using VERA-CS'. Together they form a unique fingerprint.

Cite this