Experimental Study on Surrogate Nuclear Fuel Rods Under Reversed Cyclic Bending

2017 ◽  
pp. 19-36
Author(s):  
Hong Wang ◽  
Jy-An John Wang
Keyword(s):  
Experimental Study ◽  
Nuclear Fuel ◽  
Fuel Rods ◽  
Cyclic Bending ◽  
Nuclear Fuel Rods ◽  
Reversed Cyclic

scholarly journals Fatigue Behavior of Spent Nuclear Fuel Rods in Simulated Transportation Environment

2017 ◽  
Author(s):  
Hong Wang ◽  
Jy-an John Wang ◽  
Hao Jiang
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fatigue Behavior ◽  
The United States ◽  
Pressurized Water ◽  
Fuel Rods ◽  
Cyclic Bending ◽  
Oak Ridge ◽  
High Burnup ◽  
Reversed Cyclic

Nuclear fuel rod is composed of cladding tube and a specified number of fuel pellets contained. In the United States, spent nuclear fuel (SNF) is expected to be transported to at least one storage facility before permanent disposal. The fatigue behavior of spent nuclear fuel (SNF) rods under reversed cyclic bending must be understood in order to evaluate their vibration integrity in a transportation environment. This is especially important for high-burnup SNFs (>45 GWd/MTU). This report presents the experimental results related to Zircaloy (Zry)-4-based surrogate rods and high-burnup SNFs, based on recent work performed at Oak Ridge National Laboratory (ORNL). The surrogate rod was made of Zry-4 cladding and alumina pellets, and high-burnup fuel rods were discharged from H.B. Robinson pressurized water reactor. The reversed cyclic bending testing was conducted at 5 Hz under loading control. The effect of pre-hydriding and burnup or irradiation on the flexural rigidity and fatigue life of cladding-pellet system were discussed. The fatigue data obtained are extremely useful to the future certification of SNF storage and transportation cask.

Inspection of domestic nuclear fuel rods using neutron radiography at the Tehran Research Reactor

2016 ◽  
Vol 58 (9) ◽  
pp. 763-766 ◽  
Author(s):  
Mohammad Hosein Choopan Dastjerdi ◽  
Hossein Khalafi ◽  
Yaser Kasesaz ◽  
Amir Movafeghi
Keyword(s):  
Nuclear Fuel ◽  
Research Reactor ◽  
Neutron Radiography ◽  
Fuel Rods ◽  
Tehran Research Reactor ◽  
Nuclear Fuel Rods

Uncertainty Analysis and Thermal Stored Energy Calculations in Nuclear Fuel Rods

1980 ◽  
Vol 47 (3) ◽  
pp. 457-467 ◽  
Author(s):  
Mitchel E. Cunningham ◽  
Courtney R. Hann ◽  
Anthony R. Olsen
Keyword(s):  
Uncertainty Analysis ◽  
Nuclear Fuel ◽  
Stored Energy ◽  
Fuel Rods ◽  
Energy Calculations ◽  
Nuclear Fuel Rods

Nonlinear Vibrations of Model PWR Fuel Assemblies: Part 2 — Interpretation of Results Using Bilinear Stiffness Model

2020 ◽  
Author(s):  
Prabakaran Balasubramanian ◽  
Giovanni Ferrari ◽  
Giulio M. Franchini ◽  
Marco Amabili ◽  
Kostas Karazis ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Zirconium Alloy ◽  
Nonlinear Boundary ◽  
Nonlinear Boundary Conditions ◽  
Hysteresis Model ◽  
Fuel Rods ◽  
Spacer Grids ◽  
Nuclear Fuel Rods ◽  
Rigid Rod ◽  
Force Displacement

Abstract The experimental response of fuel rods with spacer grids was interpreted using a bilinear hysteresis model. Nonlinear experimental responses of two configurations of rods made out of Zirconium alloy tubes were considered in this paper: one configuration with a single beam and the second configuration with a cluster of beams (stacked in a 3 × 3 matrix formulation). These two configurations were designed to emulate part of the nuclear fuel assembly in Pressurized Water Reactors (PWR). Both configurations were supported by spacer girds at their extremities and were immersed in still water. Spacer grids are grid-like structures made out of thin Zirconium alloy sheets with 17 × 17 cells arranged in a square pattern. Spacer grids provide mechanical support and reduce flow-induced vibration of nuclear fuel rods. They also improve the heat transfer between nuclear fuel rods and the surrounding coolant. The spacer grids impose nonlinear boundary conditions to the beams at the contact points/surface. Specifically, spacer grids present bilinear hysteresis due to their inherent complexity. The bilinear hysteresis shown by spacer grids was measured in terms of force-displacement loops by testing rigid rod inserted in one of its cells. The rigid rod was then excited by external harmonic excitation with excitation frequencies ranging from 5 Hz to 50 Hz in steps of 5 Hz. The bilinear hysteresis model, first studied by Caughey, was modified to include viscous damping and was used to interpret the experimental results. The method of slowly varying parameters was used to solve the equation of motion. First, the measured force-displacement loops of spacer grids were fitted with the numerical model described in the current analysis. Good agreement between the model response and measured loops was found, and the identified parameters allowed the characterization of the nonlinear boundary conditions imposed by spacer grids. Finally, the nonlinear responses of the two configurations under study were interpreted using the bilinear hysteresis model. Excellent agreement between numerical and experimental results was obtained for both configurations.

Research on the nuclear fuel rods melting behaviors by alternative material experiments

2021 ◽  
pp. 153415
Author(s):  
Yonglin Li ◽  
Wenxi Tian ◽  
Ronghua Chen ◽  
Tangtao Feng ◽  
Suizheng Qiu ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Fuel Rods ◽  
Alternative Material ◽  
Nuclear Fuel Rods

Surface Crack Size Detection in Nuclear Fuel Rods Based on Line Structured Light

2020 ◽  
Vol 57 (22) ◽  
pp. 221013
Author(s):  
咸凯强 Xian Kaiqiang ◽  
庞静珠 Pang Jingzhu ◽  
胡俊 Hu Jun
Keyword(s):  
Nuclear Fuel ◽  
Surface Crack ◽  
Structured Light ◽  
Crack Size ◽  
Fuel Rods ◽  
On Line ◽  
Nuclear Fuel Rods

Development of Disassembly Tool for Intermediate Examination of Nuclear Fuel Rods

2014 ◽  
Vol 38 (4) ◽  
pp. 443-449 ◽  
Author(s):  
Jintae Hong ◽  
Sung-Ho Heo ◽  
Ka-Hye Kim ◽  
Sung-Jae Park ◽  
Chang-Young Joung
Keyword(s):  
Nuclear Fuel ◽  
Fuel Rods ◽  
Nuclear Fuel Rods

Evolution of grid-to-rod fretting of nuclear fuel rods during burnup

2018 ◽  
Vol 108 ◽  
pp. 160-168 ◽  
Author(s):  
Š. Dyk ◽  
V. Zeman
Keyword(s):  
Nuclear Fuel ◽  
Fuel Rods ◽  
Nuclear Fuel Rods
Sign in / Sign up

Export Citation Format

Share Document