Results 331 to 340 of about 2,311,049 (401)
Some of the next articles are maybe not open access.
Experimental and CFD analysis of the effects of debris deposition across the fuel assemblies
Nuclear Engineering and Design, 2018During a loss of coolant accident (LOCA) or a main steam line break accident (MSLB) in a pressurize water reactor (PWR), debris of different sorts like particulate, latent fiber or chemical nature might be generated due to jet impingement or ensuing, hot,
M. Azam, F. Niu, Da Wang, Weiqian Zhuo
semanticscholar +1 more source
2017
Superphenix fuel sub-assembly was presenting three main differences compared to Phenix one: Sub-assembly dimensions more important. 30 % increase in the clad diameter, which led to choose annular pellets so as to limit the fuel heart temperature.
Joël Guidez, Gérard Prêle
openaire +1 more source
Superphenix fuel sub-assembly was presenting three main differences compared to Phenix one: Sub-assembly dimensions more important. 30 % increase in the clad diameter, which led to choose annular pellets so as to limit the fuel heart temperature.
Joël Guidez, Gérard Prêle
openaire +1 more source
CAP1400 Fuel Assembly Development and PWR Fuel Assembly Technology Progress in China
Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, 2017In 1990s the first generation of PWR fuel assembly FA300 was developed in China. With constantly design improvements over the following 20 years, three types of FA300 fuel assemblies have been developed with max fuel assembly average burnup reach 40000 MWd/tU and successfully used in 300MWe PWRs.
Libing Zhu +10 more
openaire +1 more source
Thermal hydraulic investigations of ALLEGRO ceramic fuel assemblies
Annals of Nuclear Energy, 2018Gas-cooled Fast Reactor (GFR) is one of the generation IV reactor concepts. Fast neutron spectrum and high outlet temperature of the coolant make this reactor type a contributor to sustainability of nuclear technology.
G. Orosz, S. Tóth
semanticscholar +1 more source
Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management, 2013
NUKEM monitor FAMOS is designed to measure the burn up of fuel assemblies (FA’s) and allows the calculation of the content of fissile material and other actinides. The knowledge of the isotopic composition and activities of FA’s is required for a safe handling and storage of the elements.
M. Sokcic-Kostic +3 more
openaire +1 more source
NUKEM monitor FAMOS is designed to measure the burn up of fuel assemblies (FA’s) and allows the calculation of the content of fissile material and other actinides. The knowledge of the isotopic composition and activities of FA’s is required for a safe handling and storage of the elements.
M. Sokcic-Kostic +3 more
openaire +1 more source
Energy, 2019
The use of platinum as a catalyst and the nonuniform distribution of current density inside a membrane electrode assembly result in high cost and low durability, which strongly hinders the wide adoption of proton exchange membrane fuel cells.
L. Xing +6 more
semanticscholar +1 more source
The use of platinum as a catalyst and the nonuniform distribution of current density inside a membrane electrode assembly result in high cost and low durability, which strongly hinders the wide adoption of proton exchange membrane fuel cells.
L. Xing +6 more
semanticscholar +1 more source
Fuel Cycle Economy of Accident Tolerant Fuel Assemblies
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018Taking the large commercial pressurized water reactor and its mature fuel assembly as reference, this paper has analyzed economic performance of two accident tolerant fuel (ATF) designs based on once-through fuel cycle. The results show that the fuel cycle costs of both AT F designs have grown due to application of BeO powder, which is expensive.
Xu Duoting, Liu Tong, Huang Heng
openaire +1 more source
PWR Fuel Assembly Damping Characteristics
Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 2006PWR fuel assembly damping is a key parameter in seismic/LOCA safety analysis. The damping coefficients of a fuel assembly in air, still water and flowing water are significantly different. Several researchers and engineers have published their results and methods in the past.
Roger Y. Lu, David D. Steel
openaire +1 more source
Seismic tests of fuel assemblies
Russian Engineering Research, 2012Seismic tests of full-scale mockups of fuel assemblies from the VVER-1000 reactor permit the determination of the transfer characteristics between the stimulus (acceleration of the supports) and the response of the fuel assemblies. No resonant responses of the fuel assemblies to seismic loads are observed.
Yu. N. Drozdov +6 more
openaire +1 more source
Fuel Assembly Nonlinear Dynamic Model
10th International Conference on Nuclear Engineering, Volume 1, 2002Fuel assembly finite-element dynamic models are developed to perform the core seismic analysis. The fuel assembly is modeld by a single vertical beam, which represents the cross-sectional inertias of the fuel rods, guide thimbles and instrument thimble, and a series of rotational springs.
S. J. Shah, B. Brenneman
openaire +1 more source