VERA is a suite of multiphysics codes which uses MPACT to model neutron transport in light water reactors (LWRs) [1]. In this paper, we validate MPACT by modeling critical experiments conducted at the IPEN/MB-01 and B&W facilities. We modeled critical loading experiments with a variety of different fuel pins and materials placed in the core. The experiments were modeled in two dimensions using MPACT and an axial buckling term. Default mesh parameters exist in MPACT for modeling larger reactor cores, and a mesh convergence study was performed to find appropriate mesh parameters for modeling the smaller critical reactors. The keff results show a consistent bias and small standard deviation for the IPEN/MB-01 reactor and a small bias and small...
Continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ co...
In the framework of the McSAFE European Union project, Monte-Carlo-based multiphysics tools are bein...
This paper presents a verification and validation (V&V) study of the Monte Carlo neutron transpo...
VERA is a suite of multiphysics codes which uses MPACT to model neutron transport in light water rea...
The MPACT code, jointly developed by Oak Ridge National Laboratory and University of Michigan, is de...
MPACT is a state-of-the-art core simulator designed to perform high-fidelity analysis using whole-co...
The Virtual Environment for Reactor Applications (VERA) Core Physics Benchmark Progression Problems ...
This work is dedicated to the code verification of MPACT, which is developed under the Consortium fo...
This paper describes benchmark calculations for the APR1400 nuclear reactor performed using the high...
The Consortium for Advanced Simulation of Light Water Reactors (CASL) has developed the CASL toolset...
This paper presents the validation of UNIST in-house Monte Carlo code MCS used for the high-fidelity...
This paper presents the verification and validation elements of the UNIST in-house Monte Carlo code,...
Ongoing efforts are being made to improve the performance of MPACT as the deterministic neutron tran...
This paper presents the verification and validation of UNIST in-house Monte Carlo code MCS and multi...
The Consortium for Advanced Simulation of Light Water Reactors (CASL) Virtual Environment for Reacto...
Continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ co...
In the framework of the McSAFE European Union project, Monte-Carlo-based multiphysics tools are bein...
This paper presents a verification and validation (V&V) study of the Monte Carlo neutron transpo...
VERA is a suite of multiphysics codes which uses MPACT to model neutron transport in light water rea...
The MPACT code, jointly developed by Oak Ridge National Laboratory and University of Michigan, is de...
MPACT is a state-of-the-art core simulator designed to perform high-fidelity analysis using whole-co...
The Virtual Environment for Reactor Applications (VERA) Core Physics Benchmark Progression Problems ...
This work is dedicated to the code verification of MPACT, which is developed under the Consortium fo...
This paper describes benchmark calculations for the APR1400 nuclear reactor performed using the high...
The Consortium for Advanced Simulation of Light Water Reactors (CASL) has developed the CASL toolset...
This paper presents the validation of UNIST in-house Monte Carlo code MCS used for the high-fidelity...
This paper presents the verification and validation elements of the UNIST in-house Monte Carlo code,...
Ongoing efforts are being made to improve the performance of MPACT as the deterministic neutron tran...
This paper presents the verification and validation of UNIST in-house Monte Carlo code MCS and multi...
The Consortium for Advanced Simulation of Light Water Reactors (CASL) Virtual Environment for Reacto...
Continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ co...
In the framework of the McSAFE European Union project, Monte-Carlo-based multiphysics tools are bein...
This paper presents a verification and validation (V&V) study of the Monte Carlo neutron transpo...