Results 21 to 30 of about 651,068 (302)

Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo

EPJ Nuclear Sciences & Technologies, 2023
SFC is a work package in Eurad that investigates issues related to the properties of the spent nuclear fuel in the back-end of the nuclear fuel cycle. Decay heat, nuclide inventory, and fuel integrity (mechanical and otherwise), and not least the related
Sjöland Anders, Christensen Petra, Evins Lena Zetterström, Bosbach Dirk, Duro Lara, Farnan Ian, Metz Volker, Zencker Uwe, Ruiz-Hervias Jesus, Rodríguez-Villagra Nieves, Király Márton, Schillebeeckx Peter, Rochman Dmitri, Seidl Marcus, Dagan Ron, Verwerft Marc, Herranz Puebla Luis Enrique, Hordynskyi Dmitri, Feria Francisco, Vlassopoulos Efstathios   +19 more
doaj   +1 more source

Safety Concerning Transportation of Spent Fuel [PDF]

Journal of Nuclear Science and Technology, 1989
The Central Research Institute of Electric Power Industry (CRIEPI) has been conducting, under contract with the Science and Technology Agency of Japan, the spent fuel transport cask reliability dem...
NAGAKURA, Tadashi, ABE, Hirotoshi, ESASHI, Yasuyuki, SHIOMI, Satoshi, ONUMA, Hiroshi, MAKI, Yasuro   +5 more
openaire   +1 more source

Comparison of numerical simulation results for transport and thermodynamic properties of the solid fuels combustion products with experimental data

EPJ Web of Conferences, 2012
Comparison of calculation results of transport properties of the solid fuels combustion products was made with known experimental data. Calculation was made by means of the modified program TETRAN developed in G.M.
Samujlov Eugueny, Shmelkov Yuriy
doaj   +1 more source

Fuels—An International and Interdisciplinary Scientific Open Access Journal

, 2020
Fuels are deeply entrenched in every aspect of our daily life [...
Fuels Editorial Office Fuels Editorial Office
core   +1 more source

Microbiological approaches for the treatment of spent catalysts

TIP Revista Especializada en Ciencias Químico-Biológicas, 2020
Homogeneous and heterogeneous catalysts are widely used for diverse industrial processes in order to produce clean fuels and many other valuable products, being spent hydroprocessing catalysts the major solid wastes of the refinery industries and the ...
Andrea M. Rivas-Castillo, Norma G. Rojas-Avelizapa   +1 more
doaj   +1 more source

Effects of Relative Humidity on Crevice Corrosion Behavior of 304L Stainless-Steel Nuclear Material in a Chloride Environment

Metals, 2019
In the dry cask storage of spent nuclear fuels, a stainless-steel canister acts as an important barrier for encapsulating spent fuels. As a result, local corrosion behavior of 304L stainless steel has become an issue of concern in the wet coastal region ...
Chun-Ping Yeh, Kun-Chao Tsai, Jiunn-Yuan Huang   +2 more
doaj   +1 more source

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

EPJ Nuclear Sciences & Technologies, 2018
This paper presents a study of the impact of the nuclear data (cross sections, neutron emission and spectra) on different quantities for spent nuclear fuels (SNF) from Swiss power plants: activities, decay heat, neutron and gamma sources and isotopic ...
Rochman Dimitri A., Vasiliev Alexander, Dokhane Abdelhamid, Ferroukhi Hakim   +3 more
doaj   +1 more source

SACSESS – the EURATOM FP7 project on actinide separation from spent nuclear fuels

Nukleonika, 2015
Recycling of actinides by their separation from spent nuclear fuel, followed by transmutation in fast neutron reactors of Generation IV, is considered the most promising strategy for nuclear waste management. Closing the fuel cycle and burning long-lived
Bourg Stéphane, Geist Andreas, Narbutt Jerzy   +2 more
doaj   +1 more source

Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process [PDF]

EPJ Web of Conferences
In the context of the development of generation IV reactors, solvent extraction process is under development for the reprocessing of spent nuclear fuels. A monoamide extractant was found to be a suitable replacement for TBP.
Michaud Solenne, Duterme Amandine, Costenoble Sylvain, Lengrand Fabien, Vanel Vincent, Moeyaert Pauline, Sarrat Pierre, Sorel Christian, Miguirditchian Manuel   +8 more
doaj   +1 more source

Estimation of the vitrified canister production for a PWR fleet with the CLASS code

EPJ Nuclear Sciences & Technologies, 2021
This article presents an assessment of fuel cycle parameter impact on waste production through the prism of vitrified container and minor actinide masses, using a scenario simulated with the CLASS code.
Tillard Léa, Doligez Xavier, Senentz Gérald, Ernoult Marc, Liang Jiali, Thiollière Nicolas   +5 more
doaj   +1 more source