Results 11 to 20 of about 139,532 (201)
Neutronic Simulation of Fuel Assembly Vibrations in a Nuclear Reactor [PDF]
The mechanical vibrations of core internals as fuel assemblies cause oscillations in the neutron ux that require, in some circumstances, to operate nuclear power plants at a reduced power level. This work simulates and analyses the changes of the neutron ux throughout a nuclear core due to the oscillation of a single fuel assembly without considering ...
A. Vidal-Ferràndiz +4 more
openaire +3 more sources
Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K
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
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
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
Optimization of a Fuel Assembly for Supercritical Water-Cooled Reactor CSR1000
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
An anisotropic numerical model for thermal hydraulic analyses: application to liquid metal flow in fuel assemblies [PDF]
A CFD analysis has been carried out to study the thermal–hydraulic behavior of liquid metal coolant in a fuel assembly of triangular lattice. In order to obtain fast and accurate results, the isotropic two-equation RANS approach is often used in nuclear
Caruso, Gianfranco +3 more
core +1 more source
KYLIN-V2.0 CODE CALCULATION ABILITY VERIFICATION BASED ON VERA BENCHMAR [PDF]
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
Condition monitoring of an advanced gas-cooled nuclear reactor core [PDF]
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.
Dempster A. +6 more
core +1 more source
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
The plate-type fuel assembly adopted in nuclear research reactor suffers from complicated effect induced by non-uniform irradiation, which might affect stress conditions, mechanical behaviors and thermal-hydraulic performance of the fuel assembly.
Yuanming Li +8 more
doaj +1 more source

