Results 21 to 30 of about 15,615 (306)

Assessment of the Radiotoxicity of Spent Nuclear Fuel from a Fleet of PWR Reactors

open access: yesEnergies, 2021
The paper presents the methodology for the estimation of the long-term actinides radiotoxicity and isotopic composition of spent nuclear fuel from a fleet of Pressurized Water Reactors (PWR).
Mikołaj Oettingen
doaj   +1 more source

VHTR, ADS, and PWR Spent Nuclear Fuel Analysis [PDF]

open access: yes, 2016
The aim of this study is to analyze and compare the discharged-spent fuel of three types of nuclear systems: a Very High-Temperature Gas Reactor (VHTR), a lead-cooled Accelerator-Driven System (ADS) and a standard Pressurized Water Reactor (PWR). The two
Carlos Eduardo Velasquez Cabrera   +5 more
core   +1 more source

Recovery of actinides from actinide-aluminium alloys by chlorination: Part I [PDF]

open access: yes, 2011
Pyrochemical processes in molten LiCl–KCl are being developed in ITU for recovery of actinides from spent nuclear fuel. The fuel is anodically dissolved to the molten salt electrolyte and actinides are electrochemically reduced on solid aluminium ...
J.-P. Glatz   +13 more
core   +1 more source

HEAT EXCHANGE CONDITIONS IN THE DRY STORAGE CONTAINER FOR SPENT NUCLEAR FUEL OF POWER REACTORS

open access: yesElektrotehnìka ta Elektroenergetika, 2018
Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizhska NPP dry storage facility operation by carrying out of numerical study of the thermal processes inside dry storage container. Methodology. Mathematical
S.V. Alyokhina
doaj   +1 more source

Experimental Approaches for Manufacturing of Simulated Cladding and Simulated Fuel Rod for Mechanical Decladder

open access: yesScience and Technology of Nuclear Installations, 2020
We are developing a practical-scale mechanical decladder that can slit nuclear spent fuel rod-cuts (hulls + pellets) on the order of several tens of kgf of heavy metal/batch to supply UO2 pellets to a voloxidation process.
Young-Hwan Kim   +2 more
doaj   +1 more source

Compounding of Spent Nuclear Fuel

open access: yesJournal of Siberian Federal University. Engineering & Technologies, 2016
Изложены результаты исследований процессов извлечения из хранилищ и отверждения жидких радиоактивных отходов низкого и среднего уровней активности в неорганические вяжущие (процесс цементирования). Образующийся при цементировании продукт обладает целым рядом достоинств: имеет высокую механическую прочность, является негорючим, радиационно и химически ...
Kulagina, Tatyana A.   +2 more
openaire   +3 more sources

Potential of serpent-openFOAM coupled codes for spent nuclear fuel analysis [PDF]

open access: yes, 2021
Operation of future district heating source Teplator with spent nuclear fuel assemblies requires deep analyses. The present article focus on a potential use of coupled neutronics and thermal-hydraulics codes for simulations with the spent fuel.
Lovecký, Martin   +3 more
core  

Fatigue life curves of alloy 617 in the temperature range of 800–950 °C

open access: yesNuclear Engineering and Technology, 2023
The cyclical behavior of Alloy 617 was examined at 25 °C and high temperatures of 800, 850, 900, and 950 °C in air to obtain its fatigue life curves.
Injin Sah, Jaehwan Park, Eung-Seon Kim
doaj   +1 more source

Long-Term Radiotoxicity Evaluation of PWR Spent Uranium and MOX Fuel and Highly Active Waste [PDF]

open access: yesE3S Web of Conferences, 2020
One of the main concerns related to nuclear power production is the generation and accumulation of spent nuclear fuel. Currently most of the spent fuel is stored in interim storage facilities awaiting final disposal or reprocessing.
Paunov Petar, Naydenov Ivaylo
doaj   +1 more source

DEEP DISPOSAL OF SPENT NUCLEAR FUEL [PDF]

open access: yesWIT Transactions on Ecology and the Environment, 2018
An alternative but still untested approach is to dispose of highly radioactive waste in very deep boreholes, a concept being considered in the UK and the US.
ROLAND PUSCH   +4 more
openaire   +1 more source

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