Results 21 to 30 of about 142,204 (279)
Geometry Optimization of Dispersed UMo Fuel for Light Water Reactors
Nuclear Engineering and Technology, 2023 The Uranium/Molybdenum metallic fuel has been proposed as promising advanced fuel concept especially in the dispersed fuel geometry. The fuel is manufactured in the form of small fuel droplets (particles) placed in a fuel pin covered by a matrix.
Ondrej Novak +3 more
doaj +1 more source
Small Modular Nuclear Reactors
, 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 +2 more sources
Testing of the ABBN-RF multigroup data library in photon transport calculations
EPJ Web of Conferences, 2017 Gamma radiation is produced via both of nuclear fuel and shield materials. Photon interaction is known with appropriate accuracy, but secondary gamma ray production known much less. The purpose of this work is studying secondary gamma ray production data
Koscheev Vladimir +3 more
doaj +1 more source
EPJ Web of Conferences, 2017 System of test tasks is presented with the fast reactor BN-1200 with nitride fuel as prototype. The system of test tasks includes three test based on different geometric models.
Tikhomirov Georgy +5 more
doaj +1 more source
A simple model of reactor cores for reactor neutrino flux calculations for the KamLAND experiment [PDF]
, 2006 KamLAND is a reactor neutrino oscillation experiment with a very long baseline. This experiment successfully measured oscillation phenomena of reactor antineutrinos coming mainly from 53 reactors in Japan. In order to extract the results, it is necessary
A. Suzuki +10 more
core +2 more sources
EPJ Web of Conferences, 2017 The neutron transmission experiments are one of the main sources of information about the neutron cross section resonance structure and effect in the self-shielding. Such kind of data for niobium and silicon nuclides in energy range 7 keV to 3 MeV can be
Andrianova Olga +2 more
doaj +1 more source
Heat transfer characteristics for multi-silicon ingots irradiation in a typical research reactor
International Journal of Thermofluids, 2023 A computational fluid dynamics (CFD) study is conducted for silicon ingot irradiation facility in a typical material testing reactor (MTR). The ingots are placed inside the irradiation device in staggered and in-line bundles.
Said M.A. Ibrahim +2 more
doaj +1 more source
Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage
EPJ Web of Conferences, 2017 Decay heat power of actinides and fission products from spent nuclear fuel of power VVER-1000 type reactors at long-term storage is calculated. Two modes of storage are considered: mode in which single portion of actinides or fission products is loaded ...
Ternovykh Mikhail +3 more
doaj +1 more source
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
New measurement of the 242Pu(n,γ) cross section at n-TOF-EAR1 for MOX fuels : Preliminary results in the RRR [PDF]
, 2016 The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability ...
A. Brown +142 more
core +12 more sources