Results 21 to 30 of about 2,419,768 (239)

Upsampling Monte Carlo Reactor Simulation Tallies in Depleted Sodium-Cooled Fast Reactor Assemblies Using a Convolutional Neural Network

Energies
The computational demand of neutron Monte Carlo transport simulations can increase rapidly with the spatial and energy resolution of tallied physical quantities.
Jessica Berry, Paul Romano, Andrew Osborne   +2 more
doaj   +2 more sources

Minor actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor [PDF]

Nukleonika, 2015
An analysis of the influence of addition of minor actinides (MA) to the fast reactor fuel on the most important safety characteristics was performed.
Darnowski Piotr, Uzunow Nikolaj
doaj   +2 more sources

Nuclear data uncertainty on generation IV fast reactors criticality calculations analysis comparison [PDF]

Nuclear Energy and Technology, 2023
The new calculation code capabilities are applied in the current work as well as important fast reactor criticality parameters uncertainty assessment articles’ results based on different nuclear data libraries and covariance matrices.
Dimitar G. Chereshkov, Mikhail Yu. Ternovykh, Georgiy V. Tikhomirov, Alexander A. Ryzhkov   +3 more
doaj   +3 more sources

Determining the Sensitivity of Reactor Parameters in a Sodium Cooled Fast Reactor

, 2020
The sensitivity of two operational output parameters, criticality and isotopic composition during burnup, to specific design and operational reactor parameters in a Sodium Cooled Fast Reactor, is investigated. The computational simulation tool Serpent is used.
Palfelt, Alexander, Thunberg, Wilhelm, Winka, Anders   +2 more
core   +4 more sources

Condition monitoring of an advanced gas-cooled nuclear reactor core [PDF]

, 2007
A critical component of an advanced gas-cooled reactor station is the graphite core. As a station ages, the graphite bricks that comprise the core can distort and may eventually crack.
Giovanini, L., Grimble, M.J., Monari, M., Pang, Y.   +3 more
core   +4 more sources

Monitoring a gas-cooled nuclear reactor core integrity [PDF]

, 2008
This work concerns with the problem of monitoring an Advanced Gas-cooled Nuclear Reactor (AGR) core. In the world wide context of energy production, the advanced gas-cooled reactor (AGR) nuclear power stations are approaching the end of their predicted ...
Grimble, Michael J., Monari, Mattia, Bonivento, Claudio, Giovanini, Leonardo, Paoli, Andrea   +4 more
core   +4 more sources

Monte Carlo-Based Simulation of Reactivity and Transmutation in the CEFR Sodium-Cooled Fast Reactor

Applied Sciences
As a representative Generation IV sodium-cooled fast reactor (Gen-IV SFR), neutron physics characteristics studies of the China Experimental Fast Reactor (CEFR) core are crucial for its safety case.
Jianquan Liu, Rongbin Shang, Jie Tan, Rui Zhang, Yuqian Meng, Yubo Chen, Lin Li   +6 more
doaj   +2 more sources

Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV reactor systems

EPJ Nuclear Sciences & Technologies, 2023
Five Euratom projects launched since 2017 in support of the development of ESNII/Generation-IV reactor systems are briefly presented in the paper in terms of key objectives, results, and recommendations for the future.
Mikityuk Konstantin, Ferreira Miguel, Hatala Branislav, Kloosterman Jan Leen, Šípová Monika   +4 more
doaj   +1 more source

Conceptual issues of the cold filter trap development for the sodium coolant purification in fast-neutron reactors [PDF]

Nuclear Energy and Technology, 2020
The paper presents the results of studying the peculiarities of heat and mass exchange in cold traps for the sodium purification of impurities in fast reactor circuits both in dedicated test areas simulating various trap components (isothermal sump ...
Viktor V. Alekseev, Yuliya A. Kuzina, Aleksandr P. Sorokin   +2 more
doaj   +3 more sources

A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

, 2022
International audienceThe Euratom Horizon-2020 project European sodium fast reactor safety measures assessment and research tools (ESFR-SMART) aims to enhance the safety and performance of the European sodium-cooled fast reactor (ESFR) considering safety
Tsige-Tamirat, Haileyesus, Laborde, Laurent, Péniguel, Christophe, Perez-Martin, Sara, Mikityuk, Konstantin, Pfrang, Werner, Anderhuber, Marine, Gerschenfeld, Antoine, Mimouni, Stephane   +8 more
core   +1 more source