Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Zeses Karoutas"'
Autor:
Guanyu Su, Tiago Moreira, Dong Hwi Lee, Anupam Jena, Guoqiang Wang, William Byers, Bren Phillips, Zeses Karoutas, Mark H. Anderson, Matteo Bucci
Publikováno v:
Applied Thermal Engineering. 216:119018
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c94c7edeac82282340ad335f530bccbb
https://doi.org/10.1016/j.applthermaleng.2022.119018
https://doi.org/10.1016/j.applthermaleng.2022.119018
Publikováno v:
Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation.
Crud has been observed on the fuel rod surfaces in a variety of fuel designs around the world, and in some limited situations fuel performance was compromised due to crud-induced power shift (CIPS) and/or crud-induced localized corrosion (CILC). It i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4af87caa9089cb2cea436a47b15a514d
https://doi.org/10.1115/icone28-66793
https://doi.org/10.1115/icone28-66793
Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development
Publikováno v:
Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics.
When departure from nucleate boiling (DNB) occurs, the critical heat flux (CHF) must be accurately determined for different conditions in order to maintain reasonable margin to CHF during the operation of a pressurized water reactor (PWR). Cladding s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6da01d5e4da025d3833204a827cceb22
https://doi.org/10.1115/icone28-66591
https://doi.org/10.1115/icone28-66591
Autor:
J. Deshon, William A. Byers, Michael Y. Young, Zeses Karoutas, Guoqiang Wang, Robert L. Oelrich
Publikováno v:
Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications.
This paper describes a laboratory test program to measure the thermal conductivity of corrosion product deposits on the surface of a Pressurized Water Reactor (PWR) fuel rod under a variety of thermal hydraulic conditions. This thermal conductivity i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7802ede6cbc200b2c5ddd3de42c84c35
https://doi.org/10.1115/icone21-16655
https://doi.org/10.1115/icone21-16655
Publikováno v:
Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes.
Current Pressurized Water Reactors (PWR) fuel assembly thermal-hydraulic (T/H) analyses are performed on a subchannel basis that neglects detailed heat transfer and flow distributions surrounding fuel rods. Subchannel codes such as VIPREW require inp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::404e0210cd9eb89eb67d136d6c46037c
https://doi.org/10.1115/icone21-15345
https://doi.org/10.1115/icone21-15345
Publikováno v:
Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control.
This paper presents a computational fluid dynamics (CFD) modeling methodology that has been developed to provide predictions of very local heat transfer variation in fuel rod assemblies. Results from the CFD analysis are used in HIDUTYDRV and other a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3bc0f0c7eb76184114d1388c2632e3a8
https://doi.org/10.1115/icone17-75710
https://doi.org/10.1115/icone17-75710
Autor:
Zeses Karoutas, Paul F. Joffre
Publikováno v:
Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy.
An experimental investigation was performed to compare the axial velocity profiles occurring downstream of the inlet nozzle region of nuclear PWR fuel assemblies for two bottom nozzle designs. Axial velocities were measured in a 3.763:1 over-scale ai
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1d9c7b7aa7a24ee018a62c6340d41ad
https://doi.org/10.1115/icone14-89325
https://doi.org/10.1115/icone14-89325
Autor:
Yiban Xu, Michael Y. Young, Robert L. Oelrich, Zeses Karoutas, Guoqiang Wang, William A. Byers
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :ICONE1943-ICONE1943
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e9f2f9d7c517287145b376ec74e5d4dd
https://doi.org/10.1299/jsmeicone.2011.19._icone1943_252
https://doi.org/10.1299/jsmeicone.2011.19._icone1943_252