Výsledky vyhledávání - "Wade R. Marcum"

Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment

Autor: Guillaume P.H. Mignot, Alexander Duenas, José N. Reyes, Wade R. Marcum, Daniel M. Wachs, Qiao Wu

Publikováno v: Nuclear Science and Engineering. 196:193-208

New fuel design and development currently require 20 to 25 years to be qualified for use by the nuclear power industry. The thermal-hydraulics community has taken advantage of scaling theory to des...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::1e818af1c9f8438ec031765e9c0c1c8e
https://doi.org/10.1080/00295639.2021.1955591

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A Novel Method for Predicting Power Transient CHF via the Heterogeneous Spontaneous Nucleation Trigger Mechanism

Autor: Yikuan Yan, Emory Brown, Wade R. Marcum

Publikováno v: Nuclear Technology. 206:1296-1307

Using the Laplace transform for solving a two-region (cladding/liquid) conduction problem with an exponentially increasing heat flux boundary condition, an analytic temperature profile has been fou...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::09cb96ecc3b6067d1805d9c8dee10286
https://doi.org/10.1080/00295450.2020.1724730

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Developing Separate Effects Transient Test Experiments Using an Out-of-Pile Flowing Water Loop

Autor: Daniel LaBrier, Nicolas E. Woolstenhulme, Wade R. Marcum, Yikuan Yan, Emory Brown

Publikováno v: Nuclear Technology. 206:895-910

In 2017 the Transient Reactor Test (TREAT) Facility was restarted after having been placed in a standby state in 1994. The TREAT reactor’s restart has since enabled the progressive development of n...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f9452d8fcf153e86e87ea4babeffce8d
https://doi.org/10.1080/00295450.2020.1720559

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Dispersion of Surrogate LWR Fuel Experiments Under LOCA Conditions

Autor: Wade R. Marcum, G. D. Latimer, W. F. Jones

Publikováno v: Nuclear Technology. 206:1374-1384

In this study a series of experiments were performed subjecting surrogate nuclear fuel rods to high-pressure transients to induce fuel dispersion representative of the expected conditions of a fuel...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::e9480e3f263e1291741ad688f12b8cd5
https://doi.org/10.1080/00295450.2020.1712158

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Benchmark Comparison of Experimental Data with Thermal-Hydraulic Codes RELAP5-3D and TRACE for a RIA Transient Scenario

Autor: Daniel LaBrier, Colby Jensen, Wade R. Marcum, Emory Brown, Yong-Joon Choi

Publikováno v: Nuclear Technology. 206:911-923

The effort to perform transient (TR) testing of nuclear fuel and materials in the United States took an important step in 2017 with the resumption of operations at the Transient Reactor Test (TREAT...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::fa6b88d898ee4d6ba1bb4a1cb87cecad
https://doi.org/10.1080/00295450.2020.1713673

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