nuclear fuel rods
Recently Published Documents


TOTAL DOCUMENTS

114
(FIVE YEARS 21)

H-INDEX

12
(FIVE YEARS 3)

2021 ◽  
pp. 153415
Author(s):  
Yonglin Li ◽  
Wenxi Tian ◽  
Ronghua Chen ◽  
Tangtao Feng ◽  
Suizheng Qiu ◽  
...  

2021 ◽  
Vol 9 ◽  
Author(s):  
Mingfei Gu ◽  
Dagui Huang ◽  
Dongbao Yu ◽  
Hui Tang ◽  
Yongli Zhu

To ensure that fuel rods operate in nuclear reactors safely and reliably, UO2 pellets with different enrichment levels of 235U in the same production line are manufactured in batches and divisionally managed to avoid confusion or the potential misloading of UO2 pellets with different enrichment levels. At the same time, nondestructive tests for their enrichment levels and loading uniformity and all UO2 pellets must be nondestructively tested during production. By studying the enrichment detection mechanism of the UO2 pellets of 235U, the design of an integral standard rod was carried out, and a single integral standard rod was used to achieve the calibration of the enrichment measurement curve, as well as the detection and calibration of abnormal pellets. This study undertook a comparison test of 235U enrichment between the neutron activation method and the array multi-probe passive method. The test results showed that the array multi-probe passive method had higher detection efficiency and equal accuracy.


2021 ◽  
Vol 42 (1) ◽  
pp. 86-94
Author(s):  
CHEN Hongyuan ◽  
◽  
◽  
XU Xiaojin ◽  
PANG Jingzhu ◽  
...  

2021 ◽  
Vol 7 (3) ◽  
pp. 30568-30584
Author(s):  
Filipi Gil Cardoso ◽  
Daniele de Azevedo Baêta ◽  
Dionísio José Rodrigues da Costa ◽  
Neil de Medeiros

Author(s):  
Prabakaran Balasubramanian ◽  
Giovanni Ferrari ◽  
Giulio M. Franchini ◽  
Marco Amabili ◽  
Kostas Karazis ◽  
...  

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.


Sign in / Sign up

Export Citation Format

Share Document