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Advanced Reactor Physics Methods for Transient Analysis of Boiling Water Reactors

Gonzalez Vargas, Jose Angel


The safety assessment of nuclear power plants requires the consideration of the several physical phenomena taking place in the reactor core. Since the last decade, the simulations are performed using the so-called Best-Estimate (BE) thermal-hydraulic system codes coupled with 3D nodal diffusion reactor dynamics solvers. These numerical tools are well developed and validated for PWR but for BWR there are still improvements and developments to be done. In addition, homogenized cross sections libraries, depending on the individual thermal-hydraulic state parameters, e.g. fuel temperature, moderator density, etc., must be supplied to take into account the interdependencies of the involved physics.
In this PhD a new coupled code system named TRADYN was developed that consists of the novel and innovative integration of the core simulator DYN3D into the code system TRACE/PARCS using compiler preprocessor directives. This has the advantage to preserve the original TRACE/PARCS system “untouch” and to facilitate the maintenance, modification and debugging. In order to manage the transfer information between TRACE and DYN3D, a General Interface and Specific Data Map routines in FORTRAN were developed. ... mehr

Volltext §
DOI: 10.5445/IR/1000077121
Veröffentlicht am 11.12.2017
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Hochschulschrift
Publikationsjahr 2017
Sprache Englisch
Identifikator urn:nbn:de:swb:90-771212
KITopen-ID: 1000077121
HGF-Programm 32.02.01 (POF III, LK 01) Sicherheitsanalysen: Anlagendynamik
Verlag Karlsruher Institut für Technologie (KIT)
Umfang V, 116 S.
Art der Arbeit Dissertation
Fakultät Fakultät für Maschinenbau (MACH)
Institut Institut für Neutronenphysik und Reaktortechnik (INR)
Prüfungsdatum 27.10.2017
Referent/Betreuer Stieglitz, R.
KIT – Die Forschungsuniversität in der Helmholtz-Gemeinschaft
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