An experimental study on the burst strength of fuel cladding tubes under loss of coolant accident conditions in water cooled power reactors

1965 ◽  
Vol 1 (4) ◽  
pp. 419-437 ◽  
Author(s):  
Y. Mishima ◽  
I. Katsura ◽  
K. Ono ◽  
H. Tanaka ◽  
S. Wakisaka ◽  
...  
Keyword(s):  
Experimental Study ◽  
Fuel Cladding ◽  
Burst Strength ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Accident Conditions

scholarly journals EXPERIMENTAL STUDY OF DAMAGED CR-COATED FUEL CLADDING IN POST-ACCIDENT CONDITIONS

2020 ◽  
Vol 28 ◽  
pp. 1-7
Author(s):  
Petr Červenka ◽  
Jakub Krejčí ◽  
Ladislav Cvrček ◽  
Vojtěch Rozkošný ◽  
František Manoch ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Experimental Methodology ◽  
Fuel Cladding ◽  
Loss Of Coolant Accident ◽  
Ring Compression ◽  
Loss Of Coolant ◽  
Accident Conditions ◽  
Cr Coating ◽  
The Impact ◽  
Positive Effect

To enhance the safety of nuclear power, the focus of researchers all around the world has recently mainly objected on the development of Accident Tolerant Fuels. Especially the Chromium coating of current Zirconium based cladding has been widely suggested and discussed for its immense positive effect on overall cladding properties. Nevertheless, it was observed that during the first stage of the Loss of Coolant Accident, cracks appear in the Cr coating due to its inability to tolerate higher plastic strain. Therefore, experimental methodology used in this article focuses on testing fuel cladding with damaged Cr coating after the high-temperature transient. The impact of cracks on degradation of cladding mechanical properties was observed using optical microscopy, ring compression test, microhardness, and evaluating hydrogen content and weight gain.

Behavior of plasma sprayed Cr coatings and FeCrAl coatings on Zr fuel cladding under loss-of-coolant accident conditions

2018 ◽  
Vol 344 ◽  
pp. 141-148 ◽  
Author(s):  
Yiding Wang ◽  
Wancheng Zhou ◽  
Qinlong Wen ◽  
Xingcui Ruan ◽  
Fa Luo ◽  
...  
Keyword(s):  
Fuel Cladding ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Accident Conditions ◽  
Plasma Sprayed

Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions

2016 ◽  
Vol 482 ◽  
pp. 75-82 ◽  
Author(s):  
Dong Jun Park ◽  
Hyun Gil Kim ◽  
Yang Il Jung ◽  
Jung Hwan Park ◽  
Jae Ho Yang ◽  
...  
Keyword(s):  
Fuel Cladding ◽  
Resistant Coating ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Oxidation Resistant ◽  
Accident Conditions

scholarly journals Coupled Modeling and Simulation of Phase Transformation in Zircaloy-4 Fuel Cladding Under Loss-of-Coolant Accident Conditions

2021 ◽  
Vol 9 ◽  
Author(s):  
Wenjun Lu ◽  
Libo Qian ◽  
Wenzhong Zhou
Keyword(s):  
Thermal Conductivity ◽  
Phase Transformation ◽  
Nuclear Fuel ◽  
Transformation Model ◽  
Fuel Cladding ◽  
Fuel Rod ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Accident Conditions ◽  
Enhanced Thermal Conductivity

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 phase transformation of Zircaloy-4 from hexagonal (α-pahse) to cubic (β-phase) crystal structure. As we all know, thermophysical properties have a close relationship with the microstructure of the material. Moreover, because of an important influence of the phase transformation on the creep resistance and the ductility of the fuel rod, studying the crystallographic phase transformation kinetics is pivotal for evaluating properties for fuel rod completeness. We coupled the phase transformation model together with the existing physical models for reactor fuel, gap, cladding, and coolant, based on the finite element analysis and simulation software COMSOL Multiphysics. The critical parameter for this transformation is the evolution of the volume fraction of the favored phase described by a function of time and temperature. Hence, we choose two different volume fractions (0 and 10%) of BeO for UO2-BeO enhanced thermal conductivity nuclear fuel and zircaloy cladding as objects of this study. In order to simulate loss-of-coolant accident conditions, five relevant parameters are studied, including the gap size between fuel and cladding, the temperature at the extremities of the fuel element, the coefficient of heat transfer, the linear power rate, and the coolant temperature, to see their influence on the behavior of phase transformation under non-isothermal conditions. The results show that the addition of 10vol%BeO in the UO2 fuel decreased the phase transformation effect a lot, and no significant phase transformation was observed in Zircaloy-4 cladding with UO2-BeO enhanced thermal conductivity nuclear fuel during existing loss-of-coolant accident conditions.

scholarly journals Burst Strength of Copper Barrier Fuel Cladding during Postulated Loss-of-Coolant Accident

1983 ◽  
Vol 20 (10) ◽  
pp. 868-870
Author(s):  
Hiromichi IMAHASHI ◽  
Keiichi KUNIYA ◽  
Kazuhiro SUZUKI ◽  
Kenji NORO ◽  
You HAYASHI
Keyword(s):  
Fuel Cladding ◽  
Burst Strength ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant
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