Preliminary coupling of the Thermal/Hydraulic solvers in the Monte Carlo code MCS for practical LWR analysis. (August 2018)

• Record Type: Journal Article
• Authors: Yu, Jiankai; Lee, Hyunsuk; Kim, Hanjoo; Zhang, Peng; Lee, Deokjung
• Is Part Of: Annals of nuclear energy. Volume 118(2018)
• Page Start: 317
• Page End: 335
• Publication Date: 2018-08
• Subjects: Multi-physics Coupling -- MCS -- CTF -- TH1D; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2018.03.043
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: A one-dimensional Thermal/Hydraulic solver has been coupled in UNIST in-house Monte Carlo neutron code – MCS. Cobra-TF (CTF) has been also fully coupled in UNIST in-house Monte Carlo code – MCS. A very detailed comparison of fuel temperature, coolant temperature and density has been conducted to ensure the efficiency and accuracy based on a pin cell model. This MCS based N-T/H coupling system has been preliminary applied in BEAVRS full core simulation at BOC of Cycle 1. Abstract: A Thermal/Hydraulic (T/H) coupling interface has been developed in the Monte Carlo code MCS for coupling with different T/H solvers. The single channel T/H solver TH1D and the Sub-Channel T/H solver COBRA-TF (CTF) both have been coupled to MCS through this interface. A fixed-point iteration scheme is applied in this coupling interface to enable the T/H feedback to be fully updated for Monte Carlo neutron simulation. This paper describes in detail the single rod case to demonstrate the accuracy and efficiency of these two coupled T/H solvers, with the discussion of the results for fuel temperature, coolant temperature and coolant density distributions. On the other hand, the paper also depicts the preliminary application of MCS T/H coupling in BEAVRS whole core benchmark to demonstrate the feasibility of this coupling system for use in practical LWRs multi-physics coupling analysis.