Results 21 to 30 of about 4,532 (263)

Improving the Neutronic Characteristics of a Boiling Water Reactor by Using Uranium Zirconium Hydride Fuel Instead of Uranium Dioxide Fuel

open access: yesNuclear Engineering and Technology, 2016
The present work discusses two different models of boiling water reactor (BWR) bundle to compare the neutronic characteristics of uranium dioxide (UO2) and uranium zirconium hydride (UZrH1.6) fuel. Each bundle consists of four assemblies.
Ahmed Abdelghafar Galahom
doaj   +1 more source

Investigation on vibration response characteristics and influencing factors of the fuel rods of EPR

open access: yesFrontiers in Energy Research, 2022
First, the theory of wet modal analysis and vibration response analysis are introduced, and the semi-empirical vibration equation is derived in this article.
Naibin Jiang   +3 more
doaj   +1 more source

Influence of grid-to-rod fit on fuel rod fretting

open access: yesPeriodica Polytechnica Mechanical Engineering, 2013
The fretting behavior of nuclear fuel assemblies is influenced by a number of parameters. One of these is the fit between the fuel rod and the spacer grid, which changes during the fuel residence time in the core. The influence of fit on fretting has been investigated by performing model tests on a typical fuel rod support configuration.
Szilárd Kovács   +3 more
openaire   +2 more sources

Research of Relationship Between Fuel Reliability and Iodine Isotope Activity Ratio 131I/133I in PWR Primary Coolant

open access: yesYuanzineng kexue jishu, 2022
During the normal operation of pressurized water reactor, fission products activity in the primary coolant will increase when failure of fuel rods happens.
FU Pengtao;LU Shengbo;LIANG Shan;YANG Xiaohuan;XU Jiehao;ZHOU Wenzhong;HAN Song
doaj  

Algorithm for estimating Cr coating thickness for accident tolerant fuel cladding using a pancake ECT sensor

open access: yesNuclear Engineering and Technology
The accident-tolerance of nuclear fuel rods has been a topic of continued interest since the Fukushima disaster. A notable advance in this area involves the development of Cr-coated nuclear fuel rods.
Jeong Won Park   +5 more
doaj   +1 more source

Experimental Investigation on Flow-Induced Vibration of Fuel Rods in Supercritical Water Loop

open access: yesScience and Technology of Nuclear Installations, 2014
The supercritical water-cooled reactor (SCWR) is one of the most promising Generation IV reactors. In order to make the fuel qualification test for SCWR, a research plan is proposed to test a small scale fuel assembly in a supercritical water loop.
Licun Wu, Daogang Lu, Yu Liu
doaj   +1 more source

Analysis of Radiation Heat Dissipation Characteristics of Helium-xenon Gas Cooled Small Reactor Fuel Rod

open access: yesYuanzineng kexue jishu
Space power nuclear systems require reactors to have characteristics such as compactness, miniaturization and efficiency. The combination of helium xenon mixture gas and the Brayton cycle is a good choice.
WANG Xianbo1,2, ZHAO Fulong1,2, XIE Lin1,2, TIAN Youyou1,2, BAO Hui3, TIAN Ruifeng1,2, TAN Sichao1,2
doaj   +1 more source

Development of numerical models for Monte Carlo simulations of Th-Pb fuel assembly

open access: yesE3S Web of Conferences, 2017
The thorium-uranium fuel cycle is a promising alternative against uranium-plutonium fuel cycle, but it demands many advanced research before starting its industrial application in commercial nuclear reactors.
Oettingen Mikołaj
doaj   +1 more source

Hydrogen‐Assisted Fracture of Iron‐Based Fe–Ni–Al Alloys

open access: yesAdvanced Engineering Materials, EarlyView.
Principal relations and fracture mechanisms of single‐phase and precipitate‐strengthened Fe–Ni–Al alloys subjected to prior electrochemical hydrogen charging are identified. The mechanisms of hydrogen effect on strength and microhardness are discussed, including hydrogen‐induced increase in microhardness and the role of hydrogen in fracture behavior ...
Nataliya Yadzhak   +3 more
wiley   +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

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