Zobrazeno 1 - 10
of 55
pro vyhledávání: '"R.A. Markley"'
Publikováno v:
Proceedings of the 24th Intersociety Energy Conversion Engineering Conference.
The primary heat transport system (PHTS) equipment for the SP-100 ground engineering system (GES) nuclear assembly test to be conducted is discussed. The heat transport system functions as a nonprototypical lithium primary system, transferring reacto
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d94163eb652059b018923fe442621a78
https://doi.org/10.1109/iecec.1989.74635
https://doi.org/10.1109/iecec.1989.74635
Publikováno v:
Nuclear Engineering and Design. 68:337-345
Core transient design methods of analyzing the dynamic effects of core assembly bowing, localized power perturbations and pellet-to-cladding gap conductance are described. The approaches developed have successfully been applied for design and safety
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::726b29e3ac6bfe86d71256c1b1d0f38d
https://doi.org/10.1016/0029-5493(82)90252-7
https://doi.org/10.1016/0029-5493(82)90252-7
Publikováno v:
Nuclear Engineering and Design. 62:295-321
An investigation of the hydraulic behavior of wire-wrapped fuel and blanket assemblies was conducted in an air flow test facility. The test section was a large scale sector (slightly more than one-sixth) of prototypic fuel and blanket assemblies of t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e61339a0b5ca5bb359f416d07eccb3ea
https://doi.org/10.1016/0029-5493(80)90035-7
https://doi.org/10.1016/0029-5493(80)90035-7
Publikováno v:
Nuclear Engineering and Design. 62:365-369
The coupled energy and momentum equations were solved for fully developed vertical upward laminar flow in a cylindrical tube. A simple engineering correlation which agreed well with the analytical solution was obtained. In addition, an L D effect was
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b49406c1bf24a592443562db8c63b925
https://doi.org/10.1016/0029-5493(80)90040-0
https://doi.org/10.1016/0029-5493(80)90040-0
Publikováno v:
Nuclear Engineering and Design. 52:1-13
An analysis was made and a correlation developed to determine the reduction in heat transfer caused by entrained inert gas in sodium-cooled liquid metal systems. A 1% void fraction (1.62% volumetric flow rate of inert gas) is calculated to reduce the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::90f9d1a28476b60c34fd3a4021e58eb9
https://doi.org/10.1016/0029-5493(79)90002-5
https://doi.org/10.1016/0029-5493(79)90002-5
Publikováno v:
Nuclear Science and Engineering. 69:290-296
Laminar, transition, and turbulent parallel flow pressure drop across wire-wrapped hexagonal rod bundles positioned inside a duct were determined in tests using water, sodium, and air. A smooth transition region from turbulent to laminar flow that oc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::378076090df23309957dd9c723a1f32d
https://doi.org/10.13182/nse79-a20618
https://doi.org/10.13182/nse79-a20618
Publikováno v:
Nuclear Engineering and Design. 68:323-336
The verification of the LMFBR core transient performance code, FORE-2M, was performed in two steps. Different components of the computation (individual models) were verified by comparing with analytical solutions and with results obtained from other
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f2084bb94b7b9d6dc3a6f06a19724cf0
https://doi.org/10.1016/0029-5493(82)90251-5
https://doi.org/10.1016/0029-5493(82)90251-5
Publikováno v:
Nuclear Engineering and Design. 62:335-347
This paper describes results of an experimental program to reduce uncertainties associated with the thermal-hydraulic design and analysis of LMFBR blanket assemblies. These assemblies differ significantly from fuel assemblies in design detail and ope
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6c05a18cd81a25ea3ba52aaefdfc2ab3
https://doi.org/10.1016/0029-5493(80)90037-0
https://doi.org/10.1016/0029-5493(80)90037-0
Autor:
F.C. Engel, R.A. Markley
Publikováno v:
Nuclear Engineering and Design. 68:347-357
The peak temperature rise results obtained from sodium tests of a full sized, electrically heated simulated blanket rod bundle were related to operating parameters. They were found to be related to geometry, heat input gradient, coolant flow rate at
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c12e407ff0e8a88dfdfb10a30a748354
https://doi.org/10.1016/0029-5493(82)90253-9
https://doi.org/10.1016/0029-5493(82)90253-9
Publikováno v:
Nuclear Engineering and Design. 62:181-198
Analytical model requirements for core natural convection analyses are reviewed. Then results from current modeling on intra-assembly flow and heat redistribution are compared with several sources of experimental data. Also, data are described on low
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::992a7c9f04e85ad4de4ca33fed7b92fa
https://doi.org/10.1016/0029-5493(80)90028-x
https://doi.org/10.1016/0029-5493(80)90028-x