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Validating the Need to Validate Code [PDF]
Physics Today, 2005 © 2005 American Institute of Physics, S-0031-9228-0508-220-7 Validating the Need to Validate Code T article “Computational Science Demands a New Paradigm” by Douglass Post and Lawrence Votta (PHYSICS TODAY, January 2005, page 35) makes some good points about the pitfalls of believing computed physics.
Douglass E. Post, Lawrence G. Votta
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Development and validation of ARSAC-CORTH coupling code based on a generic coupling architecture
Frontiers in Energy ResearchReactor thermal-hydraulic codes can be categorized into system codes, sub-channel codes and CFD (computational fluid dynamics) codes according to the spatial discretization and simplification methods. As a traditional reactor system safety analysis code,
Xiaoyu Wang +9 more
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Energies, 2018 To investigate turbulent reacting flows, a low-Mach number large-eddy simulation (LES) code called ‘LESsCoal’ has been developed in our group. This code employs the Germano dynamic sub-grid scale (SGS) model and the steady flamelet/progress variable ...
Yingzu Liu +4 more
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Validation of the code package MCPV [PDF]
Ядерна фізика та енергетика, 2009 The results of the validation of the code package MCPV that is used in the radiation exposure determination methodology for the pressure vessels of the VVER type reactors of Ukrainian NPPs are presented.
V. N. Bukanov +4 more
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CORE SIM+ SIMULATIONS OF COLIBRI FUEL RODS OSCILLATION EXPERIMENTS AND COMPARISON WITH MEASUREMENTS [PDF]
EPJ Web of Conferences, 2021 At EPFL, the CROCUS reactor has been used to carry out experiments with vibrating fuel rods. The paper presents a first attempt to employ the measured data to validate CORE SIM+, a neutron noise solver developed at Chalmers University of Technology.
Mylonakis A. G. +12 more
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FIRST STEPS TO COUPLED HYDRAULIC AND MECHANICAL CALCULATIONS WITHIN A PARAMETER STUDY TO DEFINE POSSIBLE CORE DESIGNS FOR THE CONVERSION OF FRM II [PDF]
EPJ Web of Conferences, 2021 The Forschungs-Neutronenquelle Heinz Meier-Leibnitz (FRM II) is actively participating in the worldwide efforts on developing high-density uranium fuels in order to reduce the enrichment of fuels used in high flux research reactors.
Shehu Kaltrina +4 more
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Validation of the burnup code MOTIVE with respect to fuel assembly decay heat data
Frontiers in Energy Research, 2023 The burn-up code MOTIVE is a 3D code for fuel assembly inventory determination developed at GRS in recent years. It modularly couples an external Monte Carlo neutron transport code to the in-house inventory code VENTINA.
Volker Hannstein +3 more
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Validation of an in-house system analysis code for heat pipe cooled reactor
He jishu, 2023 BackgroundThe kilowatt reactor using stirling technology (KRUSTY) is a heat-pipe-cooled reactor experimental system that uses a Stirling engine to convert thermal energy to electricity, it is the only one published experimental data for heat-pipe-cooled ...
WU Pan +3 more
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Applied Sciences, 2021 The experimental investigation of a prototypical set-up simulating a loss of flow accident in a helium-cooled breeding blanket first wall mock-up under typical heat load conditions is presented.
Bradut-Eugen Ghidersa +6 more
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Validation of time-dependent shift using the pulsed sphere benchmarks
Frontiers in Nuclear Engineering, 2023 The detailed behavior of neutrons in a rapidly changing time-dependent physical system is a challenging computational physics problem, particularly when using Monte Carlo methods on heterogeneous high-performance computing architectures.
Camille J. Palmer +3 more
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