Results 11 to 20 of about 142,006 (191)

Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213 [PDF]

open access: yesMATEC Web of Conferences, 2020
To safely and efficiently load the fuel assemblies of the VVER 440 / V 213 nuclear reactor, the relation between the temperature of the coolant at the outlet of the fuel assembly, measured by a thermocouple in the assembly’s axis, and the mean coolant ...
Mlynár Peter   +4 more
doaj   +1 more source

Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K

open access: yesNuclear Engineering and Technology, 2021
This paper addresses the uncertainty quantification and sensitivity analysis of a depleted light-water fuel assembly of the Turkey Point-3 benchmark. The uncertainty of the fuel assembly decay heat and isotopic densities is quantified with respect to ...
Jaerim Jang   +5 more
doaj   +1 more source

Conceptual design of neutron measurement system for input accountancy in pyroprocessing

open access: yesNuclear Engineering and Technology, 2020
One of the possible options for spent-fuel management in Korea is pyroprocessing, which is a process for electrochemical recycling of spent nuclear fuel. Nuclear material accountancy is considered to be a safeguards measure of fundamental importance, for
Chaehun Lee   +3 more
doaj   +1 more source

Manufacturing Features and Characteristics of Uranium Dioxide Pellets for Subcritical Assembly Fuel Rods

open access: yesEast European Journal of Physics, 2022
The influence of technological processes and manufacturing of uranium dioxide fuel pellets for fuel elements for experimental fuel assembly (FA-X) which was designed as an alternative fuel for the nuclear research installation (NRI) "Neutron Source ...
Igor Chernov   +3 more
doaj   +1 more source

Modelling nuclear fuel assembly with thermal-hydraulic feedback and burnup using WIMS-PANTHER-Serpent

open access: yesJournal of Physics: Conference Series, 2020
State-of-the-art deterministic code sequence WIMS-PANTHER and Monte Carlo particle transport code Serpent are employed in this work for computationally modelling the UK EPR nuclear reactor core’s fuel assembly with and without thermal-hydraulic feedback,
Jinfeng Li
semanticscholar   +1 more source

Optimization of a Fuel Assembly for Supercritical Water-Cooled Reactor CSR1000

open access: yesFrontiers in Energy Research, 2021
As one of the Generation IV nuclear reactors, the SCWR (supercritical water-cooled reactor) has high economy and safety margin, good mechanical properties for its high thermal efficiency, and simplified structure design.
Fawen Zhu   +8 more
doaj   +1 more source

Thermo-hydraulic Simulation of AP1000 Nuclear Reactor Fuel Assembly

open access: yesVetor, 2021
One of the challenges of future nuclear power is the development of safer and more efficient nuclear reactor designs. The AP1000 reactor based on the PWR concept of generation III + has several advantages, which can be summarized as: a modular ...
Leonardo Acosta Martínez   +3 more
doaj   +5 more sources

KYLIN-V2.0 CODE CALCULATION ABILITY VERIFICATION BASED ON VERA BENCHMAR [PDF]

open access: yesEPJ Web of Conferences, 2021
Virtual Environmental for Reactor Analysis (VERA) benchmark was released by the Consortium for Advanced Simulation of Light water reactors (CASL) project in 2012.
Wang Dongyong   +5 more
doaj   +1 more source

Semi-analytical modeling of the flow redistribution upstream from the mixing grids in a context of nuclear fuel assembly bow

open access: yes, 2020
Fuel assembly bow is a phenomenon that has drawn a significant attention over the last decades, due to its role in several issues related to nuclear core management.
Stanislas de Lambert   +5 more
semanticscholar   +1 more source

Time stamped list mode data from gamma-ray spectroscopic measurements on 47 nuclear fuel assemblies performed at Clab, Sweden, September 2016 through March 2019

open access: yesData in Brief, 2020
Using a high-purity Germanium gamma-ray energy spectroscopic detector system, time-stamped list-mode data sets were acquired during axial scanning of 19 boiling water reactor (BWR) and 28 pressurized water reactor (PWR) type of nuclear fuel assemblies ...
Peter Jansson   +5 more
doaj   +1 more source

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