Results 31 to 40 of about 1,590,279 (298)

Proposal of point-wise power reconstruction for IRT-4M fuel assemblies in coupled Monte-Carlo calculations

open access: yesActa 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

POST CRITICAL HEAT TRANSFER AND FUEL CLADDING OXIDATION

open access: yesActa 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

Scientific workshop "Advanced stability analysis for nuclear reactors" (Workshop in fall 2012 in Dresden, Germany)

open access: yes, 2014
Hennig, D.; Demaziere, C.; Verdú Martín, GJ.; Lange, C. (2014). Scientific workshop "Advanced stability analysis for nuclear reactors" (Workshop in fall 2012 in Dresden, Germany). Annals of Nuclear Energy. 67:1-3.
Hennig, Dieter   +3 more
core   +1 more source

Advances in Transient Thermal-Hydraulics in Water Cooled Nuclear Reactors: Main Outcomes of the OECD/NEA Specialist Meeting

open access: yes, 2023
Nuclear reactor thermal-hydraulics (NTH) has developed over the past 60 years as an important discipline for nuclear reactor design, safety analysis and operational support. Despite the achievements in the field, certain issues remain.
Mascari, Fulvio   +7 more
core   +1 more source

UNCERTAINTY PROPAGATION FOR LWR BURNUP BENCHMARK USING SAMPLING BASED CODE SCALE/SAMPLER

open access: yesActa 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

open access: yesScience 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

Small Modular Nuclear Reactors

open access: yes, 2020
Small modular reactors (SMRs) encompass a large number of technologies at different stages of development. A key challenge for SMR stakeholders is the evaluation of SMR competitiveness with respect to large reactors (LRs). SMRs are usually considered less competitive than LRs because of a misguided application of the economy of scale principle. However,
Locatelli, G, Mignacca, B
openaire   +3 more sources

Spent nuclear fuel discharges from U.S. reactors 1994 [PDF]

open access: yes, 1996
Spent Nuclear Fuel Discharges from US Reactors 1994 provides current statistical data on fuel assemblies irradiated at commercial nuclear reactors operating in the US.

core   +1 more source

Mechanochemical Synthesis and Characterization of Nanostructured ErB4 and NdB4 Rare‐Earth Tetraborides

open access: yesAdvanced 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

Dynamical approach to isotopic-distribution of fission fragments from actinide nuclei

open access: yesEPJ 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

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