Identification of limiting case between DBA and SBDBA (CL break area sensitivity): A new model for the boron injection system
- San Piero A Grado Nuclear Research Group GRNSPG, Univ. of Pisa, Via Livornese 1291-56122, San Piero a Grado - Pisa (Italy)
- Nucleo-electrica Argentina Sociedad Anonima (NA-SA), Buenos Aires (Argentina)
Atucha-2 is a Siemens-designed PHWR reactor under construction in the Republic of Argentina. Its geometrical complexity and (e.g., oblique Control Rods, Positive Void coefficient) required a developed and validated complex three dimensional (3D) neutron kinetics (NK) coupled thermal hydraulic (TH) model. Reactor shut-down is obtained by oblique CRs and, during accidental conditions, by an emergency shut-down system (JDJ) injecting a highly concentrated boron solution (boron clouds) in the moderator tank, the boron clouds reconstruction is obtained using a CFD (CFX) code calculation. A complete LBLOCA calculation implies the application of the RELAP5-3D{sup C} system code. Within the framework of the third Agreement 'NA-SA - Univ. of Pisa' a new RELAP5-3D control system for the boron injection system was developed and implemented in the validated coupled RELAP5-3D/NESTLE model of the Atucha 2 NPP. The aim of this activity is to find out the limiting case (maximum break area size) for the Peak Cladding Temperature for LOCAs under fixed boundary conditions. (authors)
- Research Organization:
- American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
- OSTI ID:
- 22105813
- Resource Relation:
- Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 11 refs.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ARGENTINA
ATUCHA-2 REACTOR
BORON
BOUNDARY CONDITIONS
CLADDING
COMPUTER GRAPHICS
CONTROL ELEMENTS
CONTROL SYSTEMS
HEAVY WATER
KINETICS
LOSS OF COOLANT
MODERATORS
NEUTRONS
NUCLEAR INDUSTRY
NUCLEAR POWER PLANTS
SAFETY INJECTION
SENSITIVITY
THERMAL HYDRAULICS
THREE-DIMENSIONAL CALCULATIONS
VOID COEFFICIENT