Results 31 to 40 of about 38,641 (304)
Characteristics of iron and nickel diffusion in molten lead-bismuth eutectic
Mechanical Engineering Journal, 2015 The characteristics of iron (Fe) and nickel (Ni) diffusion in molten lead-bismuth eutectic (LBE) were investigated experimentally by using capillary method.
Yun GAO, Minoru TAKAHASHI, Masao NOMURA
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Consistent neutron-physical and thermal-physical calculations of fuel rods of VVER type reactors
EPJ Web of Conferences, 2017 For modeling the isotopic composition of fuel, and maximum temperatures at different moments of time, one can use different algorithms and codes. In connection with the development of new types of fuel assemblies and progress in computer technology, the ...
Tikhomirov Georgy +3 more
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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
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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
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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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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.
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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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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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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, 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
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