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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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International Journal of Advanced Nuclear Reactor Design and TechnologyThe ballooning behavior of fuel rod cladding is an important issue of nuclear reactor, which may initiate a severe nuclear reactor accident. Based on COMSOL multi-physical module, this research established a thermo-mechanical coupling finite element ...
Xin Zhang +4 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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Frontiers in Energy Research, 2021 Using the finite element multiphysics modeling method, the performance of the thorium-based fuel with Cr-coated SiC/SiC composite cladding under both normal operating and accident conditions was investigated in this work.
Shengyu Liu +4 more
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Key factors affecting the thermal performance of annular fuel elements in LFR
He jishu, 2021 BackgroundThe key factors affecting the thermal performance of the lead-cooled fast reactor (LFR) annular fuel are very important to improve the core power density of LFR.PurposeThis study aims to analyze those key factors and provide guidance for ...
WANG Yuxuan +5 more
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Measurement of the spent fuel rod cladding temperature during the in-pile testing at 500–900°C [PDF]
Nuclear Energy and Technology, 2018 This paper deals with the problem of measuring the VVER-1000 burnup fuel cladding temperature in a 500–900°C range in the process of experiments in a channel of the MIR research reactor to obtain data on the fuel element behavior under the influence of ...
Oleg I. Dreganov +3 more
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Frontiers in Energy Research, 2021 Under loss-of-coolant conditions, the temperature on fuel cladding will increase rapidly (up to 1000–1500 K), which will not only cause a dramatic oxidation reaction of Zircaloy-4 and an increase in hydrogen concentration but also cause an allotropic ...
Wenjun Lu +3 more
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Examination of fuel elements irradiated in the reactor of the World’s First NPP after long-term storage [PDF]
Nuclear Energy and Technology, 2023 Examinations of fuel elements with two different fuel compositions, U-Mo+Mg and UO2+Mg, irradiated in the AM reactor after their long-term storage do not reveal any visible defects on the surface of their outer claddings.
Sergey N. Ivanov +5 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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Nuclear Engineering and Technology, 2020 Three-dimensional finite element simulations are implemented for the in-pile thermo-mechanical behavior in U–Mo/Al monolithic fuel plates with different thermal creep rates of cladding involved. The numerical results indicate that the thickness increment
Xiaobin Jian, Shurong Ding
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