Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Yousef M. Farawila"'
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 6, Pp 1532-1539 (2019)
This paper analyzes a new method for reducing boiling water reactor fuel temperature during a Loss of Coolant Accident (LOCA). The method uses a device called Reverse Flow Restriction Device (RFRD) at the inlet of fuel bundles in the core to prevent
Externí odkaz:
https://doaj.org/article/7a9573c07ce242859c6df4ad25e43777
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 6, Pp 1532-1539 (2019)
This paper analyzes a new method for reducing boiling water reactor fuel temperature during a Loss of Coolant Accident (LOCA). The method uses a device called Reverse Flow Restriction Device (RFRD) at the inlet of fuel bundles in the core to prevent
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::315ea0991f27b830f4f29c72f576b9d8
http://www.sciencedirect.com/science/article/pii/S1738573318308465
http://www.sciencedirect.com/science/article/pii/S1738573318308465
Publikováno v:
Nuclear Science and Engineering. 184:321-333
Numerical solutions for transient fluid flow in nuclear systems often suffer from the effects of numerical diffusion and damping making the assessment of system stability rather difficult. Efforts for coping with this problem include research and dev
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2e0ffbe7ed8706b527502a4f3a711462
https://doi.org/10.13182/nse16-24
https://doi.org/10.13182/nse16-24
Autor:
Yousef M. Farawila, Douglas W. Pruitt
Publikováno v:
Nuclear Science and Engineering. 154:316-327
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::947d0f5bbd6e0e505b49d0a774db78dd
https://doi.org/10.13182/nse06-a2636
https://doi.org/10.13182/nse06-a2636
Autor:
Yousef M. Farawila, Douglas W. Pruitt
Publikováno v:
Nuclear Science and Engineering. 154:302-315
A study of the nonlinear behavior of growing density-wave oscillations is presented in the framework of a reduced-order model. Nonlinear effects are included in both the hydraulic and neutron kinetics equations, where both were found to contribute to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::867656f26f7c52aeb6be333fa05ec11c
https://doi.org/10.13182/nse06-a2635
https://doi.org/10.13182/nse06-a2635
Autor:
Yousef M. Farawila, Douglas W. Pruitt
Publikováno v:
Nuclear Science and Engineering. 143:211-225
The response of the critical power ratio to boiling water reactor (BWR) power oscillations is essential to the methods and practice of mitigating the effects of unstable density waves. Previous methods for calculating generic critical power response
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0d29388fc6e04668e0f7d993ce783bf3
https://doi.org/10.13182/nse03-a2331
https://doi.org/10.13182/nse03-a2331
Autor:
Yousef M. Farawila
Publikováno v:
Nuclear Science and Engineering. 129:261-272
A modal neutron kinetics method was developed and applied to new problems with boiling water reactor oscillations. The modal method is uniquely suited for such problems because the oscillation components, in-phase and out-of-phase, correspond directl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6fd91ff6139726dcf08f0f6267682ee2
https://doi.org/10.13182/nse98-a1980
https://doi.org/10.13182/nse98-a1980