Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Atul A. Karve"'
Autor:
Atul A. Karve, Russ M. Fawcett
Publikováno v:
Progress in Nuclear Energy. 53:571-582
The Economic Simplified Boiling Water Reactor (ESBWR) is GEH’s next evolution of advanced BWR technology. There are 1132 fuel bundles in the core and the thermal power is 4500 MWt. As part of design simplification it uses natural circulation flow w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ed5bd2c13795479da05f11a1666c639
https://doi.org/10.1016/j.pnucene.2011.01.008
https://doi.org/10.1016/j.pnucene.2011.01.008
Publikováno v:
Nuclear Technology. 151:60-69
A recent cycle of a General Electric boiling water reactor performed two beginning-of-cycle local cold criticals. The eigenvalues estimated by the core simulator were 0.99826 and 1.00610. The large spread in them (= 0.00784) is a source of concern, a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d825e651b9e7d6ab2801dd92cb242e24
https://doi.org/10.13182/nt05-a3631
https://doi.org/10.13182/nt05-a3631
Autor:
Atul A. Karve, Paul J. Turinsky
Publikováno v:
Nuclear Technology. 135:241-251
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ec4d7740167d99f3b38df370c95eedf2
https://doi.org/10.13182/nt01-a3219
https://doi.org/10.13182/nt01-a3219
Autor:
Atul A. Karve, Paul J. Turinsky
Publikováno v:
Nuclear Technology. 131:48-68
The computational capability to determine optimal core loading patterns (LPs) for boiling water reactors (BWRs) given a reference control rod program has been developed. The design and fidelity of the reference BWR core simulator are presented. The p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::92144d05b2da25a20404fbd24be18f7c
https://doi.org/10.13182/nt00-a3104
https://doi.org/10.13182/nt00-a3104
Publikováno v:
Nuclear Technology. 123:121-129
Axial power shapes that develop during power-maneuvering simulations in pressurized water reactors must be analyzed to ensure that an adequate margin to avoid departure from nucleate boiling (DNB) is maintained during these transients. To reduce the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3945af3d23f89edaf5fcf1155cf04239
https://doi.org/10.13182/nt98-a2886
https://doi.org/10.13182/nt98-a2886
Publikováno v:
Nuclear Engineering and Design. 177:155-177
A simple mathematical model is developed to describe the dynamics of the nuclear-coupled thermal-hydraulics in a boiling water reactor (BWR) core. The model, which incorporates the essential features of neutron kinetics and single-phase and two-phase
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ea657e77a415176dd2e71e8d409fbc59
https://doi.org/10.1016/s0029-5493(97)00192-1
https://doi.org/10.1016/s0029-5493(97)00192-1
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