Results 41 to 50 of about 10,212 (309)
Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases [PDF]
The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications.
Avramova, Maria, Cuervo Gómez, Diana
core +1 more source
High‐frequency (HF) welding of steel is limited by oxide inclusions that degrade weld quality. This study demonstrates, for the first time, the integration of a nonthermal Ar/H2 dielectric barrier discharge (DBD) plasma jet into HF welding. Local plasma treatment provides effective shielding and in‐situ oxide reduction, resulting in markedly fewer and ...
Viktor Udachin +4 more
wiley +1 more source
The assessment of hydrogen release, distribution, and mitigation measures in the containment of a nuclear power plant is increasingly based on code calculations. These calculations require state-of-the-art experiments to benchmark the codes against them.
R. Kapulla +4 more
doaj +1 more source
Quench front progression in a superheated porous medium: experimental analysis and model development [PDF]
In case of severe accident in a nuclear reactor, the fuel rods may be highly damaged and oxidized and finally collapse to form a debris bed. Removal of decay heat from a debris bed is a challenging issue because of the difficulty for water to flow inside.
Bachrata, Andrea +4 more
core
The presented study focuses on the fracture behaviour of carbon‐bonded magnesia MgO–C refractories, where environmentally friendly fructose, collagen and lignin serve as temporary binding agents. The partial substitution of the source material with recycled MgO–C reduces the fracture resistance, which can be counteracted by the additional introduction ...
Marc Neumann +6 more
wiley +1 more source
NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR. Analysis of neutronic and thermal-hydraulics parameters of whole operation cycle is very important for the safety of reactor operation.
Surian Pinem +2 more
doaj +1 more source
Development of dynamic motion models of SPACE code for ocean nuclear reactor analysis
Lately, ocean nuclear power plants have attracted attention as one of diverse uses of nuclear power plants. Because ocean nuclear power plants are movable or transportable, it is necessary to analyze the thermal hydraulics in a moving frame of reference,
Byoung Jae Kim, Seung Wook Lee
doaj +1 more source
Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis [PDF]
The aim of the research described in this paper is to perform consistent comparative analyses of two different approaches for coupling of two-scale, two-physics phenomena in reactor core calculations. The physical phenomena of interest are the neutronics
Avramova, Maria +3 more
core +1 more source
Thermal Hydraulics Design and Analysis Methodology for a Solid-Core Nuclear Thermal Rocket Engine Thrust Chamber [PDF]
Nuclear thermal propulsion is a leading candidate for in-space propulsion for human Mars missions. This chapter describes a thermal hydraulics design and analysis methodology developed at the NASA Marshall Space Flight Center, in support of the nuclear ...
Canabal, Francisco +4 more
core +3 more sources
Thermophysical Properties of the Desulphurization Slags With Various CaS and CaO/Al2O3 Ratio
This article investigates how CaS content and the CaO/Al2O3 ratio influence the thermophysical properties of desulphurization slags. Using experimental measurements and thermodynamic simulations, this study reveals complex effects on viscosity, surface tension, and density, providing new insight into slag structure and phase behavior under ...
Eldar Salpagarov +4 more
wiley +1 more source

