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PROTON RADIOGRAPHY WITH THE PIXEL DETECTOR TIMEPIX
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
This article presents the processing of radiographic data acquired using the position-sensitive hybrid semiconductor pixel detector Timepix. Measurements were made on thin samples at the medical ion-synchrotron HIT [1] in ...
POST CRITICAL HEAT TRANSFER AND FUEL CLADDING OXIDATION
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
The knowledge of heat transfer coefficient in the post critical heat flux region in nuclear reactor safety is very important. Although the nuclear reactors normally operate at conditions where critical heat flux (CHF) is ...
THERMAL-HYDRAULIC ANALYSIS OF IRT-4M IN REACTIVITY INSERTION ACCIDENT AT VR-1 REACTOR
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
The paper deals with thermal-hydraulic analysis during reactivity insertion accident, i.e. a step increase of nuclear system reactivity by 0.7 eff, at VR-1 Reactor. The reactor utilizes IRT-4M type of fuel assemblies, and ...
STUDY OF IDENTIFICATION OF TWO-PHASE FLOW PARAMETERS BY PRESSURE FLUCTUATION ANALYSIS
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
This paper deals with identification of parameters of simple pool boiling in a vertical rectangular channel by analysis of pressure fluctuation. In this work is introduced a small experimental facility about 9 kW power, ...
ASSESSMENT OF BURNABLE ABSORBER FUEL DESIGN BY UWB1 DEPLETION CODE
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
UWB1 depletion code is being developed as a fast computational tool for the study of burnable absorbers in University of West Bohemia in Pilsen, Czech Republic. Research of fuel depletion aims at development and introduction ...
QUENCH FRONT PROPAGATION IN THE ANNULAR CHANNEL
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
Understanding the quench front propagation during bottom core reflooding is crucial for the effective cooling during the LOCA accident. The results presented in this paper were obtained on an experimental loop with an ...
PARCS/TRACE COUPLING METHODOLOGY FOR ROD EJECTION ON VVER 1000 REACTOR
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
The rod ejection (RE) is a design basis accident in accordance with NUREG-0800 and usually studied using point kinetics. In this paper a methodology and a 3D kinetic model is prepared (PARCS), coupled with a thermal hydraulic ...
EVALUATION METRICS APPLIED TO ACCIDENT TOLERANT FUEL CLADDING CONCEPTS FOR VVER REACTORS
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
Enhancing the accident tolerance of LWRs became a topic of high interest in many countries after the accidents at Fukushima-Daiichi. Fuel systems that can tolerate a severe accident for a longer time period are referred ...
IMPACT OF THE CHEMICAL FORM OF IN-CONTAINMENT SOURCE ON FISSION PRODUCT RELEASE FROM WWER-1000/V-320 TYPE NPP CONTAINMENT DURING LOCA
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
Nuclear power plant accidents may be followed by a release of fission products into the environment. This release is dependent on several phenomena, such as chemistry, pressure, type of the accident etc. The aim of this ...
SELF-ABSORPTION CORRECTIONS BASED ON MONTE CARLO SIMULATIONS
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)
The main aim of this article is to demonstrate how Monte Carlo simulations are implemented in our gamma spectrometry laboratory at the Department of Dosimetry and Application of Ionizing Radiation in order to calculate the ...