Results 11 to 20 of about 1,923 (185)
CALCULATION OF STRESS AND DEFORMATION IN FUEL ROD CLADDING DURING PELLET-CLADDING INTERACTION
Acta Polytechnica, 2015 The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main function of cladding is hermetic separation of nuclear fuel from coolant.
Dávid Halabuk, Jiří Martinec
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Automated system for control of VVER-1000 fuel properties considering fuel cladding damage parameter. [PDF]
Trudy Odesskogo Politehničeskogo Universiteta, 2018 An automated system for control of VVER-1000 reactor fuel properties considering fuel element cladding damage parameter, fuel burnup and axial offset has been proposed.
Pelykh S. +3 more
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He jishu, 2022 BackgroundUranium dioxide fuel elements of fast neutron reactor operate under the conditions of high burnup, high neutron fluence rate, high line power and high temperature.
CHEN Qidong, GAO Fuhai
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Energies, 2023 Using the BISON fuel-performance code, simulations were conducted of an automated process to read initial and operating conditions from the Pacific Northwest National Laboratory (PNNL) database and reports, which contain metallic-fuel data from the Fast ...
Kyle M. Paaren +4 more
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A model of the nitride pellet – cladding axial interaction in a fast reactor due to jamming [PDF]
Nuclear Energy and TechnologyIn the process of a post-irradiation examination of nitride pins irradiated as part of experimental BN-600 reactor fuel assemblies, a noticeable elongation and a higher ovality of nitride pins cladding were observed as compared with oxidefuel pins.
Vladimir I. Folomeev +4 more
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Three-Dimensional Modeling of Thermal-Mechanical Behavior of Accident Tolerant Fuels
Frontiers in Energy Research, 2021 Considering the safety issues of the traditional UO2-Zr fuel, a variety of accident-tolerant fuel (ATF) candidates have been proposed in recent years.
Zitao Zeng +9 more
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Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes
Nuclear Engineering and Technology, 2021 The mechanical interaction between the fuel pellet and the cladding tube of a nuclear fuel rod is a very important for safety studies as this phenomenon could lead to fuel failure and release of radioactivity.
Márton Király +4 more
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Metals, 2018 The thermophysical performance and solid mechanics behavior of UO2-36.4vol % BeO fuel pellets cladded with Zircaloy, SiC, and FeCrAl, and Zircaloy cladding materials coated with SiC and FeCrAl, are investigated based on simulation results obtained by the
Wei Zhou, Wenzhong Zhou
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Nuclear Engineering and Technology, 2021 The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for the improvement of fuel pin performance codes, in particular the enhancement of their predictive capabilities towards uranium-plutonium mixed oxide fuels ...
L. Luzzi +13 more
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Radiographic Inspection of Fueled Clads [PDF]
, 2005 Five general purpose heat source (GPHS) fueled clads were radiographically inspected at the Idaho National Laboratory (INL). The girth weld region of each clad had previously passed visual examination, ring gauge test, and leak test but showed “positive” indications on the ultrasonic (UT) test.
Roney, Timothy J., Wendt, Karen M.
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