Results 1 to 10 of about 167,077 (303)

Prediction of the nuclear fuel rod abrasion

open access: yesApplied and Computational Mechanics, 2013
The paper is focused on calculation of the friction forces work in the contact of nuclear fuel rods with fuel assembly spacer grid cells. This friction work is deciding factor for the prediction of the fuel rod coating abrasion.
Zeman V., Hlaváč Z.
doaj   +1 more source

Experimental evaluation of fuel rod pattern analysis in fuel assembly using Yonsei single-photon emission computed tomography (YSECT)

open access: yesNuclear Engineering and Technology, 2022
The purpose of this study was to verify the possibility of fuel rod pattern analysis in a fresh fuel assembly using the Yonsei single-photon emission computed tomography (YSECT) system.
Hyung-joo Choi   +7 more
doaj   +1 more source

Development and evaluation of fuel performance analysis code FuSPAC

open access: yesInternational 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
doaj   +1 more source

Investigation on vibration response characteristics and influencing factors of the fuel rods of EPR

open access: yesFrontiers in Energy Research, 2022
First, the theory of wet modal analysis and vibration response analysis are introduced, and the semi-empirical vibration equation is derived in this article.
Naibin Jiang   +3 more
doaj   +1 more source

Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2021
Loss of Coolant Accident (LOCA) is one of the major design-basis accidents in LWRs. Fuel rod may fail due to the rupture of the cladding. By developing a LOCA simulation module, the steady-state fuel rod performance analysis code, FROBA-ROD, is now ...
Haoyu Liao   +7 more
doaj   +1 more source

Thermal behavior analysis of PWR fuel during RIA at various fuel burnups using modified theatre code [PDF]

open access: yesNuclear Technology and Radiation Protection, 2016
The fuel irradiation and burnup causes geometrical and dimensional changes in the fuel rod which affects its thermal resistance and ultimately affects the fuel rod behavior during steady-state and transient conditions. The consistent analysis of
Nawaz Amjad   +3 more
doaj   +1 more source

Study on In-Service Inspection of Nuclear Fuel Assembly Failure Using Ultrasonic Plate Wave

open access: yesSensors, 2022
As protection for nuclear power plants is quite necessary, the nuclear fuel is sealed in zirconium alloy thin wall cladding. During service, fuel rods might be damaged caused by wall-thickness thinning, cladding corrosion and cracking, etc.
Xiang Xiao   +4 more
doaj   +1 more source

Improved Radiation Heat Transfer Model in RELAP5 for Compact Fuel Rod Bundles by the Absorption Factor Modification

open access: yesFrontiers in Energy Research, 2022
Simulations of radiation heat transfer in fuel rod bundles are necessary for the thermal hydraulic design and safety analysis of open lattice gas-cooled reactors, which always operate at high temperatures.
Qian Sun, Yu Ji, Jun Sun
doaj   +1 more source

Describing VVER-1000 reactors fuel rod performance in the normal operation and high burn-up conditions [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2019
The main purpose of the work is to develop a valid physical model and an accurate numerical technique to describe the occurred phenomenon of the VVER-1000 fuel rod, during its lifetime, especially for high burn up conditions.
S Talebi
doaj   +1 more source

Numerical Simulation and Validation of Flow-Induced Vibration of the Specific Rod under Elastic Supports using One-Way Fluid-Solid Interaction [PDF]

open access: yesJournal of Applied Fluid Mechanics, 2023
The vibration induced by the cooling fluid flow around the fuel rods in the fuel Assembly of nuclear reactors causes the rods to be destroyed and eventually leak due to the fretting wear in the place of contact with their supports for a long time.
R. Amirian, G. R. Zarepoor, M. Talebi
doaj   +1 more source

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