Validation of Light Water Reactor Ex-Core Calculations with VERA
- 1 November 2021
- journal article
- research article
- Published by Taylor & Francis Ltd in Nuclear Technology
- Vol. 208 (5), 794-810
- https://doi.org/10.1080/00295450.2021.1957660
Abstract
The Consortium for Advanced Simulation of Light Water Reactors (CASL) Virtual Environment for Reactor Applications (VERA) is a reactor simulation software. It offers unique capabilities by combining high-fidelity in-core radiation transport with temperature feedback by using MPACT (a deterministic neutron transport code) and COBRA-TF (a thermal-hydraulic code) with follow-on, fixed-source transport calculations using the Shift Monte Carlo code to calculate ex-core quantities of interest. In these coupled calculations, MPACT provides Shift with the fission source for follow-on ex-core calculations. These ex-core simulations can be set up to calculate detector responses, as well as the flux and fluence in ex-core regions of interest, such as the reactor pressure vessel, nozzle, and irradiated capsules. A Watts Bar Nuclear Plant Unit 1 (WBN1) ex-core model was developed, as described in this paper, and this model was used to perform coupon calculations. The results for the coupon flux calculations show close agreement with the reference values for cycle 1 produced by the two-dimensional Discrete Ordinates Transport (DORT) code and presented in a BWXT Services Inc. report. However, differences in the results (10%) seen in cycles 2 and 3 and the reasons for these differences are discussed in this paper. The VERA WBN1 model was also used to perform a vessel fluence calculation for cycle 1. Additionally, a collaboration between CASL and Duke Energy led to the first code-to-code validation of VERA for reactor ex-core applications that used a model for the Shearon Harris reactor. Results from this collaboration show excellent agreement between VERA and the Monte Carlo N-Particle Transport Code for the detector response calculations. The work performed under this collaboration is also detailed in this paper.Keywords
This publication has 12 references indexed in Scilit:
- Nuclide depletion capabilities in the Shift Monte Carlo codeAnnals of Nuclear Energy, 2018
- Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACTJournal of Computational Physics, 2016
- The Virtual Environment for Reactor Applications (VERA): Design and architectureJournal of Computational Physics, 2016
- Implementation, capabilities, and benchmarking of Shift, a massively parallel Monte Carlo radiation transport codeJournal of Computational Physics, 2016
- The Serpent Monte Carlo code: Status, development and applications in 2013Annals of Nuclear Energy, 2015
- FW-CADIS Method for Global and Regional Variance Reduction of Monte Carlo Radiation Transport CalculationsNuclear Science and Engineering, 2014
- ADVANTG An Automated Variance Reduction Parameter GeneratorPublished by Office of Scientific and Technical Information (OSTI) ,2013
- Denovo: A New Three-Dimensional Parallel Discrete Ordinates Code in SCALENuclear Technology, 2010
- Automated Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint FunctionNuclear Science and Engineering, 1998
- Evaluated Nuclear Data File, ENDF/B-VIPublished by Springer Science and Business Media LLC ,1992