Results 31 to 40 of about 38,529 (305)
Acta Polytechnica CTU Proceedings, 2022 Current efforts to develop high-fidelity multi-physics tools for research reactors with IRT-4M fuel leads to the involvement of Monte-Carlo transport and subchannel thermo-hydraulic codes in the process of safety assessment.
Pavel Jíška, Jan Frýbort
doaj +1 more source
Elements of nuclear safety – Research reactors [PDF]
, 2019 This publication gives a global overview of the diversity and complementarity of research reactors, some of which have been or are still being used to conduct experiments that are essential for the development and operation of nuclear power reactors ...
Grolleau, Emmanuel +2 more
core +1 more source
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
doaj +1 more source
Radionuclides in United States commercial nuclear power reactors [PDF]
, 1994 In the next ten to twenty years, many of the commercial nuclear power reactors in the United States will be reaching their projected lifetime of forty years.
Bechtold, T. E., Dyer, N. C.
core +1 more source
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
Advanced Engineering Materials, Volume 27, Issue 6, March 2025.ErB4 and NdB4 nanostructured powders are produced by mechanochemical synthesis. 5 h mechanical alloying and 4 M HCl acid leaching are used in the production. ErB4 and NdB4 powders exhibit maximum magnetization of 0.4726 emu g−1 accompanied with an antiferromagnetic‐to‐paramagnetic phase transition at about TN = 18 K and 0.132 emu g−1 with a maximum at ...
Burçak Boztemur +5 more
wiley +1 more source
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
doaj +1 more source
Planar Solid‐State Nanopores Toward Scalable Nanofluidic Integration Based on CMOS Technology
Advanced Engineering Materials, EarlyView.We present a scalable silicon‐based fabrication strategy for planar solid‐state nanopores to enable their integration with complex nanofluidic systems. Prototype devices demonstrate normal voltage‐current characteristics, good noise performance, and appreciable streaming currents. Our CMOS‐compatible fabrication process offers precise geometric control
Ngan Hoang Pham +7 more
wiley +1 more source