Results 21 to 30 of about 203,114 (300)
Modeling of Pore Coarsening in the Rim Region of High Burn-up UO2 Fuel
Nuclear Engineering and Technology, 2016 An understanding of the coarsening process of the large fission gas pores in the high burn-up structure (HBS) of irradiated UO2 fuel is very necessary for analyzing the safety and reliability of fuel rods in a reactor.
Hongxing Xiao, Chongsheng Long
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A study into the propagation of the uncertainties in nuclear data to the nuclear concentrations of nuclides in burn-up calculations [PDF]
Nuclear Energy and Technology, 2020 The key papers on estimating the uncertainties in nuclear data deal with the influence of these uncertainties on the effective multiplication factor by introducing the so-called sensitivity factors and only some of these are concerned with the influence ...
Alexander N. Pisarev, Valerii V. Kolesov
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EPJ Web of Conferences, 2016 Paper describes the new approach of fitting axial fuel burn-up patterns in peripheral fuel assemblies of VVER-1000 type reactors, on the base of ex-core neutron leakage measurements, neutron-physical calculations and in-core SPND measured data.
Borodkin Pavel +2 more
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Horizontal flight trajectory optimization considering RTA constraints [PDF]
MATEC Web of Conferences, 2020 The increasing of flights around the world has led to various problems for the aeronautical industry such as saturated air space and higher levels of fossil fuel consumption.
Murrieta-Mendoza Alejandro +2 more
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Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils
Nuclear Materials and Energy, 2023 In this study we compared the microstructure evolution of U-Mo fuel foils produced with and without heat treatment at low burn-up via advanced post-irradiation examination.
F.G. Di Lemma +7 more
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Study of Neptunium, Americium and Protactinium Addition for 300MWth GFR with Uranium Carbide Fuel
Computational and Experimental Research in Materials and Renewable Energy, 2019 A study of Neptunium, Americium, and Protactinium addition for GFR 300MWth with Uranium Carbide fuel has been performed. The purpose of this study was to determine the characteristics of addition Neptunium, Americium, and Protactinium in a 300MWth Gas ...
Ratna Dewi Syarifah, Alvi Nur Sabrina
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HIGH BURN-UP TESTS OF U-Al FUEL ELEMENTS [PDF]
, 1964 A series of irradiation tests were performed on the High Flux Beam Reactor fuel elements. The U--Al fuel elements contained 30 to 40 wt% U and 3% Si. Burnup ranged from 20 to 50%. A summary of the results is given. (C.E.S.)
Weeks, J. R. +2 more
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Local Burn-Up Effects in the NBSR Fuel Element [PDF]
, 2013 This study addresses the over-prediction of local power when the burn-up distribution in each half-element of the NBSR is assumed to be uniform. A single-element model was utilized to quantify the impact of axial and plate-wise burn-up on the power distribution within the NBSR fuel elements for both high-enriched uranium (HEU) and low-enriched uranium (
Brown, N. R. +2 more
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A STUDY ON THE INITIAL CHARACTERISTICS OF DOMESTIC SPENT NUCLEAR FUELS FOR LONG TERM DRY STORAGE
Nuclear Engineering and Technology, 2013 During the last three decades, South Korean nuclear power plants have discharged about 5,950 tons of spent fuel and the maximum bum-up reached 55 GWd/MTU in 2002.
JUSEONG KIM +3 more
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Nukleonika, 2014 Decrease of the economically accessible uranium resources and the inherent proliferation resistance of thorium fuel motivate its application in nuclear power systems.
Gholamzadeh Zohreh +5 more
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