Results 51 to 60 of about 9,237 (168)

Two-way coupling of subchannel T/H code CUPID-RV with neutronics and fuel performance codes for multi-physics simulations of pin-wise PWR core analysis

open access: yesNuclear Engineering and Technology
Recent efforts have focused on developing high-fidelity, multi-physics safety analysis methods to better assess realistic safety margins. However, conservatism remains due to simplified safety analysis, such as applying hot-pin conditions uniformly ...
Yeong Hun Lee   +4 more
doaj   +1 more source

Investigation on Electron Energy Distribution in Multi- Component Plasma in Nuclear Fuel Rod Gap [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2014
The electron energy distribution function in fuel rod gap of Busheher’s VVER-1000 nuclear reactor was investigated using the Fokker-Planck equation. In this regard, the Fokker-Planck equation was solved by using the Runge-Kutta numerical method, and the ...
Fereshteh Golian   +2 more
doaj  

Brightness fusion and multi-scale optimized enhancement algorithm for fuel rod DR images

open access: yesHe jishu
BackgroundA fuel rod is a fundamental unit of a fuel assembly, and it directly impacts the safe operation of nuclear reactors. To efficiently detect internal defects in fuel rods, a high-resolution visual nondestructive testing method, X-ray imaging, i.e.
HUANG Fan   +5 more
doaj   +1 more source

High-fidelity numerical investigation on structural integrity of SFR fuel cladding during design basis events

open access: yesNuclear Engineering and Technology
A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs).
Seo-Yoon Choi   +3 more
doaj   +1 more source

MELTING AND FORMING OF SER FUEL RODS [PDF]

open access: yes, 1960
Sixty-one metal alloy reds were fabricated for the SNAP Experimental Reactor (SER), a compact nuclear power source. These rads were 1 in. in diameter by 10 in. long and consisted of an alloy containing 7 wt.% highly enriched uranium and 93 wt.% zinconium. Melting of the alloy was done by generally accepted consumable-arc meltiag techniques.
openaire   +2 more sources

Research on radiological consequences analysis of reactor control rod ejection accident based on peak radial average fuel enthalpy rise

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology
The fission products residing in the fuel rod void volume (plenum and pellet-to-cladding gap) are available for release upon cladding breach, and the fission products release fraction is a key parameter for analyzing the radiological consequences of ...
Jie Mao   +5 more
doaj   +1 more source

Hybrid burnable absorber design based on ATF and application in 24-month long cycle fuel management

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology
In order to meet the requirement of reactivity control for 24-month long cycle, an optimization design of burnable absorber based on accident tolerant fuel (ATF) is carried out.
Hong Cao, Wenhua Zhang
doaj   +1 more source

Hardness and Young's Modulus of Intact and Leak PWR Fuel Rods

open access: yesYuanzineng kexue jishu
The region from cladding to pellet of the leak rod with the burnup of 41 GW·d/tU and the intact rod with the burnup of 45 GW·d/tU was characterized by nanoindentation, metallurgical microscope, and Raman spectroscopy.
YANG Qinke, WANG Huacai, CHENG Huanlin, TANG Qi, SONG Wulin, WANG Wei, GUO Yifan
doaj   +1 more source

Analysis of calculation of fuel rods for strength under transient and steady-state operating conditions

open access: yesNuclear Materials and Energy
The operating conditions are analyzed, mechanical characteristics are calculated pertaining to the 4-year cycle fuel rods of VVER-1000. The fuel rod strength characteristics are considered as applied to steady-state and transient conditions of reactor ...
Stepan Lys, Alexandr Kanyuka
doaj   +1 more source

Flow-induced vibration of fuel rods.

open access: yesJournal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1986
A study on flow-induced vibration of fuel rods in a reactor was first reported by Bergreen in 1958. Since then theoretical and experimental researches have been made by many investigators. This is a review of the studies on vibration of the fuel rod excited by axial flow.
openaire   +2 more sources

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