Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1
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Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1

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Published by Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Available from Supt. of Docs., U.S. G.P.O., National Technical Information Service [distributor in Washington, DC, Springfield, VA .
Written in English

Subjects:

  • Boiling water reactors -- Accidents -- Computer simulation.,
  • Nuclear reactor accidents -- Spain -- Computer simulation.

Book details:

Edition Notes

Statementprepared by F. Castrillo, A. Gomez, I. Gallego.
SeriesInternational agreement report -- NUREG/IA-0120.
ContributionsGomez, A., Gallego, I., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Unidad Eléctrica S.A.
The Physical Object
FormatMicroform
Pagination1 v. (various pagings)
ID Numbers
Open LibraryOL17678570M

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This report presents the results of the assessment of TRAC-BF1 (GiJ1) code with the model of the C.N. Cofrentes for simulation of the transient originated by the manual trip of one pump. Buy Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1 (SuDoc Y 3.N /) by Castrillo, F. (ISBN:) from Amazon's Book Store. Everyday low prices and free delivery on eligible : F. Castrillo. Assessment of the turbine trip transient in cofrentes NPP with TRAC-BF1 / by: Castrillo, F.,, et al. Published: () Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version /. |a Assessment of the "one feedwater pump trip transient" in Cofrentes Nuclear Power Plant with TRAC-BF1 / |c prepared by F. Castrillo, A.G. Navarro, I. Gallego. 3 |a Assessment of the "1 feedwater pump trip transient" in Cofrentes Nuclear Power Plant with TRAC-BF1.

Request PDF | Peach bottom transients analysis with TRAC/BF1-VALKIN | The TRAC/BF1-VALKIN code is a new time domain analysis code for studying transients in a boiling water reactor. This code uses. Recirculation suction large break LOCA analysis of the Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1). Washington, DC: Springfield, VA: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission: Available from Supt. of Docs., U.S. G.P.O. ; National Technical Information Service [distributor. coupled-code benchmark was recently completed for a BWR turbine trip (TT) transient and is the object of the present report. Turbine trip transients in a BWR are pressurisation events in which the coupling between core space-dependent neutronic phenomena and system dynamics plays an important role. The data made. We use cookies to offer you a better experience, personalize content, tailor advertising, provide social media features, and better understand the use of our services.

Available in the National Library of Australia collection. Author: Gomez Nunez, Severo, ; Format: Book; p.: ill., maps (part fold.) ; c19 cm.   Development and Assessment of CFD Models Including a Supplemental Program Code for Analyzing Buoyancy-Driven Flows Through BWR Fuel Assemblies in SFP Complete LOCA Scenarios. NASA.   BWR Anticipated Transients Without Scram Leading to Instability. SciTech Connect. Cheng L. Y.; Baek J.; Cuadra, A. . restricted neacrp-l nea commitee on reactor physics reactor physics activities in nea member countries october september organisation for economic co .