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Monitoring of Fuel and Cladding Elongation in a Nuclear Fuel Rod [PDF]
한국정밀공학회지, 2017 To evaluate the performance of nuclear fuel, it is necessary to measure the fission gas release, fuel temperature, fuel stack elongation, cladding elongation, fuel rod inner pressure, coolant temperature, and neutron flux during irradiation tests. Linear
Jintae Hong +3 more
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SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis
Energies, 2022 The aim of this study is to investigate the potential improvement of accident-tolerant fuels in pressurized water reactors for replacing existing reference zircaloy (Zr) fuel-cladding systems.
Mohammad Alrwashdeh, Saeed A. Alameri
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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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He jishu, 2021 BackgroundLarge-grained UO2 pellet and coated zirconium cladding are the most practical fuel pellet and cladding material scheme for accident tolerant fuel (ATF) solutions, which are expected to be commercially available in the next few years.
YOU Yan, GONG Xin, LI Cong
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OXIDE LAYER CHARACTERIZATION OF AlMg2 CLADDING OF IRRADIATED U3Si2/Al FUEL WITH 4,8 gU/cm3 DENSITY
Urania, 2022 OXIDE LAYER CHARACTERIZATION OF AlMg2 CLADDING OF IRRADIATED U3Si2/Al FUEL WITH 4,8 gU/cm3 DENSITY. To investigate the performance of AlMg2 cladding in the U3Si2/Al dispersion fuel, oxide layer characterization of AlMg2 cladding of the irradiated U3Si2 ...
Juan Carlos Sihotang +4 more
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Nuclear Engineering and Technology, 2022 Cladding ballooning and rupture are the important phenomena at the early stage of a severe accident. Most severe accident analysis codes determine the cladding rupture based on simple parameter models.
Pengcheng Gao +3 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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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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Development and evaluation of fuel performance analysis code FuSPAC
International Journal of Advanced Nuclear Reactor Design and Technology, 2022 The nuclear fuel rod should maintain self-sustainable nuclear fission, as the first safety barrier to prevent the leakage of radioactive products. The fuel rod performance analyses are essential to ensure reliable long-term operation of fuel rod. In this
Tenglong Cong +4 more
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Investigation of residual stress changes and formation of hydride phase in production stages of Zr-1%Nb alloy [PDF]
مجله علوم و فنون هستهای, 2022 Zr-1%Nb alloy is the most common alloy used as nuclear fuel cladding in Russian reactors. In producing a nuclear fuel cladding, the cold rolling (pilger) and the final straightening lead to the creation of residual stresses and a change in the ...
S.A. Miresmaeili Hafdani +2 more
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