Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Sule Ergun"'
Autor:
Sule Ergun, Veda Duman Kantarcioglu
Publikováno v:
Proceedings of the 30th European Safety and Reliability Conference and 15th Probabilistic Safety Assessment and Management Conference.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c2fcd299c606651d6683dcba3f189b73
https://doi.org/10.3850/978-981-14-8593-0_4284-cd
https://doi.org/10.3850/978-981-14-8593-0_4284-cd
Publikováno v:
Annals of Nuclear Energy. 35:1663-1670
In the case of a postulated loss of coolant accident (LOCA) in a nuclear reactor, an accurate prediction of clad temperature is needed to determine the safety margins. During the reflood phase of the LOCA, when the local void fraction is greater than
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b14c83b7f9a451a819e98e0efa9674fd
https://doi.org/10.1016/j.anucene.2008.02.013
https://doi.org/10.1016/j.anucene.2008.02.013
Publikováno v:
Annals of Nuclear Energy. 35:1671-1676
In the first part of the paper, the modifications performed to improve the dispersed flow film boiling model in COBRA-TF have been described. The improvements were achieved by adding a small droplet field to the code’s solution scheme. The conserva
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d5149513ef4a01ae923629367489bc46
https://doi.org/10.1016/j.anucene.2008.02.014
https://doi.org/10.1016/j.anucene.2008.02.014
Autor:
Marek Stempniewicz, Lawrence E. Hochreiter, Marcel Slootman, Jason G. Williams, Hergen Wiersema, Sule Ergun
Publikováno v:
Nuclear Technology. 163:273-284
In this study, calculations were performed to simulate a postulated large-break loss-of-coolant accident for the High Flux Reactor (HFR) cooling system using the COBRA-TF computer code. COBRA- TF has been chosen for this analysis since it has suitabl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e2a73b9e54b165a03b3e508873cc9a00
https://doi.org/10.13182/nt08-a3987
https://doi.org/10.13182/nt08-a3987
Autor:
Lawrence E. Hochreiter, Marek Stempniewicz, Sule Ergun, Marcel Slootman, Jason G. Williams, Hergen Wiersema
Publikováno v:
Nuclear Technology. 156:69-74
Critical heat flux (CHF) at a natural boiling condition is an important phenomenon for a research reactor having a small-hydraulic-diameter geometry under a large-break loss-of-coolant accident condition. Accurately predicting the CHF under this cond
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f698fb4f5ecf336ec4b85a83965f885f
https://doi.org/10.13182/nt06-a3774
https://doi.org/10.13182/nt06-a3774
Autor:
Birol Aktas, Sule Ergun
Publikováno v:
10th International Conference on Nuclear Engineering, Volume 2.
A deficiency has been identified with the use of boron concentration for formulating reactivity feedback while the power of a PWR in response to boron injection in the aftermath of a scram failure was simulated. The US NRC Consolidated Code (TRAC-M)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5656a14ca1998aa4ed8c38fd98da0da8
https://doi.org/10.1115/icone10-22298
https://doi.org/10.1115/icone10-22298