Results 51 to 60 of about 2,115,275 (370)
UNCERTAINTY PROPAGATION FOR LWR BURNUP BENCHMARK USING SAMPLING BASED CODE SCALE/SAMPLER
Acta Polytechnica CTU Proceedings, 2018 Sampling based method is adopted in many fields of engineering and it is currently used to propagate uncertainties from physical parameters and from nuclear data, to integral indicators of nuclear systems.
Daniel Campolina, Jan Frybort
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Dynamical approach to isotopic-distribution of fission fragments from actinide nuclei
EPJ Web of Conferences, 2016 Measurements of the isotope distribution of fission fragments, often denoted as the primary fission yield (pre-neutron yield) or independent fission yield (post-neutron yield) are still challenging at low excitation energies, so that it is important to ...
Ishizuka Chikako +3 more
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POST CRITICAL HEAT TRANSFER AND FUEL CLADDING OXIDATION
Acta Polytechnica CTU Proceedings, 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 not reached, accidents where ...
Vojtěch Caha, Jakub Krejčí
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Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite
Science and Technology of Nuclear Installations, 2022 The article is dedicated to the safety assessment of mixed storage of irradiated graphite and other types of radioactive waste accumulated during the operation of uranium-graphite reactors.
Alexander O. Pavliuk +4 more
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Advanced Engineering Materials, EarlyView.This study proposes a new methodology for producing metal matrix nanocomposites in the solid state. The process involves the plasma‐assisted thermochemical treatment of metallic alloy powders. As a proof‐of‐concept, TiN nanoparticles are synthesized directly on the surface of FeTi intermetallic powder particles, enabling the development of the ...
Deivison Daros Paim +4 more
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Neutronic analysis of a heat-pipe cooled reactor
Acta Polytechnica CTU Proceedings, 2023 Heat-pipe cooled reactors belong to the group of nuclear reactors using heat pipes filled with liquid metals (such as sodium or potassium) to cool the core. Due to the passive heat removal system, there is no need to use closed loops with pumps, and the
Josef Sabol, Jan Frýbort
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Advanced Engineering Materials, EarlyView.Bimetallic (NiFe) and trimetallic (NiFeCr) nanoalloys (NAs) are synthesized using corresponding oxide mixtures using microwave hydrogen plasma within a few milliseconds. The process simultaneously 1) reduces metal oxides to metals; 2) downsizes the particles from micrometers to nanometers; and 3) blends the metals to form NAs.
Sachin Kumar +5 more
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Advanced Functional Materials, EarlyView.This study demonstrates an alternative method of creating charge‐stable negatively charged nitrogen vacancy (NV−) centers close to the diamond surface without high‐temperature annealing. By illuminating nitrogen‐implanted regions with a continuous‐wave 405 nm laser, NV− centers are induced, exhibiting electron spin coherence properties suitable for ...
Jens Fuhrmann +4 more
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Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor
Brazilian Journal of Radiation Sciences, 2022 This study aims to model the radiological consequences that result from loss of coolant accident in open pool research reactor of 22 MW power. The loss of coolant accident results from rupture in the cooling systems of the reactor and consequently ...
Amr Abdelhady
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Advanced Functional Materials, EarlyView.HKUST‐1/TiO2 composite materials show a very high photocatalytic hydrogen evolution rate which increases as a function of the irradiation time until reaching a plateau and even surpasses the performance of the 1%Pt/TiO2 material after three photocatalytic cycles.
Alisha Khan +9 more
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