Prohlížení Acta Polytechnica CTU Proceedings. 2016, vol. 4 dle názvu
Zobrazují se záznamy 1-19 z 19
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ACTIVATION ANALYSIS OF HISTORICAL SAMPLES AND NEUTRON SPECTRUM DETERMINATION AT VR-1 TRAINING REACTOR
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)Vertical irradiation channel of the VR-1 training reactor of the Department of Nuclear Reactors CTU was used for activation analysis of historical samples from the 14th to the 19th century. For determination of mass fractions ... -
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 ... -
CFD SIMULATION OF UPWARD SUBCOOLED BOILING FLOW OF FREON R12
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)Subcooled flow boiling under forced convection occurs in many industrial applications of purpose to maximize heat removal from the heat source by the very large heat transfer coefficient. This work deals with CFD simulations ... -
COMPARISON OF S-CO2 POWER CYCLES FOR NUCLEAR ENERGY
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)The supercritical carbon dioxide (S-CO2) is a possible cooling system for the new generations of nuclear reactors and fusion reactors. The S-CO2 power cycles have several advantages over other possible coolants such as ... -
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 ... -
HYDROGEN CHARGING OF FUEL CLADDING METHODOLOGY
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)Hydrogen content is a very important parameter for mechanical properties of fuel cladding, especially after LOCA transients. Therefore, it is necessary to take into account the amount of hydrogen absorbed in the fuel ... -
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 ... -
ION SOURCE FOR A SINGLE PARTICLE ACCELERATOR
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)This paper proposes a method to obtain very low beam current on the injection side of an particle accelerator. By using a combination of a well known ion source type and a short photo-emissive laser pulse, very low amount ... -
MEASUREMENT OF NEUTRON SPATIAL DISTRIBUTION OF THE BNCT EPITHERMAL BEAM AT THE REACTOR LVR-15
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)In this study, a measurements of neutron field using a special positioning device with a 6Li + Si detector and image plate is described. The measurements were provided for Boron Neutron Capture Therapy (BNCT) channel of ... -
MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)This paper describes materials made of zirconium-based alloys used for nuclear fuel cladding fabrication. It is focused on corrosion problems their theoretical description and modeling in nuclear engineering. -
NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)The paper describes a new numerical code for multigroup transient analyses with thermal feedback. The code is developed at Institute of Nuclear and Physical Engineering. It is necessary to carefully investigate transient ... -
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 ... -
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 ... -
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 ... -
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 ... -
RADIATION DEGRADATION OF PCBS IN SEDIMENTS: COMPARISON OF TWO METHODS
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)Polychlorinated biphenyls are toxic compounds which have accumulated in river sediments in Eastern Slovakia. Bioaccumulation could cause even cancer. Radiation degradation with electrons is new and perspective method to ... -
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 ... -
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, ... -
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 ...