Zobrazeno 1 - 10
of 23
pro vyhledávání: '"George L. Mesina"'
Publikováno v:
Annals of Nuclear Energy. 122:366-377
The coolant systems of nuclear power plants are modeled with system codes. The results of the system code calculations are necessary not only to develop new power plants, but also in the licensing and analysis of existing power plants. Therefore, it
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6a81b927d616e9759409abc0db9de093
https://doi.org/10.1016/j.anucene.2018.09.003
https://doi.org/10.1016/j.anucene.2018.09.003
Publikováno v:
Nuclear Science and Engineering. 182:83-95
RELAP5-3D is typically used to model stationary, land-based reactors. However, it can also model reactors in other inertial and accelerating frames of reference. By changing the magnitude of the gravitational vector through user input, RELAP5-3D can
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f931f20807b365583d25d6c375b64eb7
https://doi.org/10.13182/nse15-3
https://doi.org/10.13182/nse15-3
Publikováno v:
Nuclear Science and Engineering. 182:1-12
Large computer programs like RELAP5-3D solve complex systems of governing, closure and special process equations to model the underlying physics of nuclear power plants. Further, these programs incorporate many other features for physics, input, outp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::332d076039bc15821d91bd0cf841b1cd
https://doi.org/10.13182/nse14-151
https://doi.org/10.13182/nse14-151
Publikováno v:
ASME 2017 Nuclear Forum.
Modeling of two phase flows in nuclear power plants is very important for design, licensing, and operator training and therefore must be performed accurately. As requirements have increased, the form and accuracy of the models and computer codes have
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fe51c11b44f682a969c86d97f2b3f266
https://doi.org/10.1115/nuclrf2017-3515
https://doi.org/10.1115/nuclrf2017-3515
Autor:
George L. Mesina, Nolan Anderson
Publikováno v:
ASME 2017 Nuclear Forum.
Condensation of steam on the primary side of a steam generator in a pressurized water reactor (PWR) is one means of removing decay heat during some accident scenarios, including small break loss of coolant accident (SBLOCA). However, when noncondensa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bb2aeee6c907d35140ab07324124a2a7
https://doi.org/10.1115/nuclrf2017-3401
https://doi.org/10.1115/nuclrf2017-3401
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 3
The Nuclear Regulatory Commission (NRC) has considered revision of 10-CFR-50.46C rule (Borchard and Johnson, 2013, “10 CFR 50.46c Rulemaking: Request to Defer Draft Guidance and Extension Request for Final Rule and Final Guidance,” U.S. Nuclear R
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e21b3d20a4d73c8ca77daae2e397ba4a
https://doi.org/10.1115/1.4035851
https://doi.org/10.1115/1.4035851
Publikováno v:
Volume 3: Thermal-Hydraulics.
The Nuclear Regulatory Commission (NRC) has considered revising the 10 CFR 50.46C rule [1] for analyzing reactor accident scenarios to take the effects of burn-up rate into account. Both maximum temperature and oxidation of the cladding must be cast
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c6848b4382f128b7894b45763ba34e9a
https://doi.org/10.1115/icone24-61045
https://doi.org/10.1115/icone24-61045
Autor:
Humberto E. Garcia, Richard Boardman, George L. Mesina, Rob Hovsapian, Cristian Rabiti, Robert Kinoshita, Shannon Bragg-Sitton
The purpose of this report is to establish a strategy for modeling and simulation of candidate hybrid energy systems. Modeling and simulation is necessary to design, evaluate, and optimize the system technical and economic performance. Accordingly, t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c1111dd1cd6355d03e402557491f6a15
https://doi.org/10.2172/1213628
https://doi.org/10.2172/1213628
Autor:
Nolan Anderson, George L. Mesina
The state-of-the-art nuclear reactor system safety analysis computer program developed at the Idaho National Laboratory (INL), RELAP5-3D, continues to adapt to changes in computer hardware and software and to develop to meet the ever-expanding needs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dcf0a37abe4f85212c24fd7ec4e9563a
https://doi.org/10.2172/1173070
https://doi.org/10.2172/1173070