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Title: MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6

Journal Article · · Progress in Nuclear Energy
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The Virtual Environment for Reactor Applications (VERA) core physics benchmark problem #6, 3D Hot Full Power (HFP) assembly, from the Consortium for Advanced Simulation of Light Water Reactors (CASL) was simulated using the MC21 continuous energy Monte Carlo code coupled with the COBRA-IE subchannel thermal-hydraulics code using the R5EXEC coupling framework. The converged MC21/COBRA-IE solution was compared to results from CASL's VERA-CS code system, MPACT coupled to COBRA-TF (CTF). MPACT is a three-dimensional (3D) whole core transport code, executed in a 2D/1D approach employing planar method of characteristics (MOC) solutions with SP3 in the axial direction, and CTF is a subchannel thermal-hydraulics code designed for Light Water Reactor analysis. Eigenvalues agreed within 63 pcm, axially-integrated normalized radial fission distributions agreed within ±0.2% (root mean square (RMS) difference of 0.1%), local volume-averaged fuel pin temperatures agreed within +8.8/-4.3 C (RMS difference of 3.9 C), and local subchannel coolant temperatures agreed within +0.8/-1.5 C (RMS difference of 0.5 C). A sensitivity study to guide tube heat transfer indicated that a statistically-significant increase in reactivity and shift in radial pin power distribution occurred within the assembly when guide tube heating was enabled.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility (OLCF)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1364065
Alternate ID(s):
OSTI ID: 1565664
Journal Information:
Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Vol. 101 Journal Issue: PC; ISSN 0149-1970
Publisher:
ElsevierCopyright Statement
Country of Publication:
United Kingdom
Language:
English
Citation Metrics:
Cited by: 12 works
Citation information provided by
Web of Science

References (9)

High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW journal September 2015
Coupled MCNP6/CTF code: Development, testing, and application journal October 2016
MC21 v.6.0 – A continuous-energy Monte Carlo particle transport code with integrated reactor feedback capabilities journal August 2015
Sub-step methodology for coupled Monte Carlo depletion and thermal hydraulic codes journal October 2016
Large-scale Monte Carlo neutron transport calculations with thermal hydraulic feedback journal October 2015
The Numerical Multi-Physics project (NUMPS) at VTT Technical Research Centre of Finland journal October 2015
Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR journal November 2015
Numerical Methods in Coupled Monte Carlo and Thermal-Hydraulic Calculations journal January 2017
Development of an Integrated Code System Using R5EXEC and RELAP5-3D journal January 2016

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Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Nuclear Science & Technology
Multiphysics
MC21
COBRA-IE
VERA
MPACT
CTF