Results 11 to 20 of about 308 (180)
There have been recent efforts to establish methods for high-fidelity and multi-physics simulation with coupled thermal–hydraulic (T/H) and neutronics codes for the entire core of a light water reactor under accident conditions. Considering the computing
Seok Jong Yoon +4 more
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Simulation codes allow one to reduce the high conservativism in nuclear reactor design improving the reliability and sustainability associated with nuclear power.
Sebastian Davies +8 more
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MULTI-PHYSICS TRANSIENT SIMULATIONS WITH TRIPOLI-4® [PDF]
In this work, we present the first dynamic calculations performed with the Monte Carlo neutron transport code TRIPOLI-4R with thermal-hydraulics feedback.
Faucher Margaux +2 more
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In order to solve the problems of complexity and poor error adaptability in the blind recognition of standard non-punctured polarization codes, the theorems and propositions that could characterize the relationship between the code length and code rate ...
Yao WANG +3 more
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In order to assess the accuracy and validity of subchannel, system, and computational fluid dynamics codes, the Paul Scherrer Institut has participated in the OECD/NRC PSBT benchmark with the thermal-hydraulic system code TRACE5.0 developed by US NRC ...
Taewan Kim +3 more
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MIXED CORE SUBCHANNEL MODEL FOR SUBCAL AND COUPLING WITH ANDREA
This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisting of fuel assemblies with non-identical spacing grids.
Vojtěch Caha, Jiří Čížek
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In order to join efforts to develop high-fidelity multi-physics tools for research reactor analysis, the KIT is conducting studies to modify the coupled multi-physics codes developed for power reactors.
Juan Carlos Almachi +2 more
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EFFECT OF ENERGY DEPOSITION MODELLING IN COUPLED STEADY STATE MONTE CARLO NEUTRONICS/THERMAL HYDRAULICS CALCULATIONS [PDF]
In coupled calculations with Monte Carlo neutronics and thermal hydraulics the Monte Carlo code is used to produce a power distribution which in practice means tallying the energy deposition.
Tuominen Riku +4 more
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DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)
Understanding and optimizing the relation between nuclear reactor components or physical phenomena allows us to improve the economics and safety of nuclear reactors, deliver new nuclear reactor designs, and educate nuclear staff.
Sebastian Davies +7 more
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Benchmark of Subchannel Code VIPRE-W with PSBT Void and Temperature Test Data
This paper summarizes comparisons of VIPRE-W thermal-hydraulic subchannel code predictions with measurements of fluid temperature and void from pressurized water reactor subchannel and bundle tests. Using an existing turbulent mixing model, the empirical
Y. Sung +5 more
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