Results 31 to 40 of about 35,413 (308)
Nuclear Engineering and Technology, 2018 A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at the Primärkreislauf-Versuchsanlage (primary coolant loop test facility; PKL) facility in the framework of the OECD/NEA PKL-3 project.
Roman Mukin +3 more
doaj +1 more source
Open Research Europe, 2022 The aim of this work is to evaluate three methodologies regarding semi-empirical scroll compressor modeling for different refrigerants and conduct a comparative analysis of their results and accuracy.
George Meramveliotakis +2 more
doaj +1 more source
PERSPECTIVES IN SYSTEM THERMAL-HYDRAULICS [PDF]
Nuclear Engineering and Technology, 2012 The paper deals with three main topics: a) the definition of System Thermal-Hydraulics (SYS TH), b) a historical outline for SYS TH and, c) the description of elements for reflection when planning research projects or improvement activities, this last topic being the main reason for the paper.
openaire +2 more sources
Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility [PDF]
, 2019 CIRCE is a lead–bismuth eutectic alloy (LBE) pool facility aimed to simulate the primary system of a heavy liquid metal (HLM) cooled pool-type fast reactor.
Caruso G. +4 more
core +1 more source
Science and Technology of Nuclear Installations, 2014 To validate the performance and safety of an integral type reactor of SMART, a thermal-hydraulic integral effect test facility, VISTA-ITL, is introduced with a discussion of its scientific design characteristics.
Hyun-Sik Park +5 more
doaj +1 more source
Conceptual matrix for the biofuels of the future applicable to the Romanian economy [PDF]
E3S Web of Conferences, 2019 Romania is in a full process of development in regards to producing energy from renewable sources. Successes have been recorded in the wind and hydro sectors, however, challenges are still to be solved in the field of biofuels.
Lăzăroiu Gheorghe +5 more
doaj +1 more source
Science and Technology of Nuclear Installations, 2016 In order to investigate single bubble evolution, a boiling phase change model in subcooled flow boiling is proposed in this paper, and VOF model combined with phase change model is adopted to simulate the single bubble growth and movement. The effects of
De-wen Yuan +6 more
doaj +1 more source
The Best Estimate Plus Uncertainty approach in nuclear reactor safety and licensing: Brief history and the elements after licensing [PDF]
Nuclear Technology and Radiation Protection, 2019 The best estimate plus uncertainty is, at the same time, an approach, a procedure and a frame- work in nuclear thermal-hydraulics and nuclear reactor safety and licensing.
D’Auria Francesco S. +1 more
doaj +1 more source
Advanced Engineering Materials, EarlyView.The thermal diffusivity of MgO‐C refractories is highly sensitive to sample preparation and processing procedures. In this article, the effects of coking sequence, machining conditions, structural inhomogeneity, and graphite coating application on measurements using laser flash apparatus are systematically investigated.
Luyao Pan +4 more
wiley +1 more source
Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis [PDF]
, 2008 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