Incorporation of full three-dimensional (3D) models of the reactor core into system transient codes allows better estimation of interactions between the core behavior and plant dynamics. Considerable efforts have been made in various countries and organizations to verify and validate the capability of the coupled codes technique. For these purposes appropriate Light Water Reactor (LWR) transient benchmarks based upon programmed transients performed in Nuclear Power Plants (NPP) were recently developed on a higher “best-estimate” level. The reference problem chosen for simulation in a VVER 1000 is a Main Coolant Pump (MCP) switching-on transient when the other three MCPs are in operation. This event is characterized by rapid increase in the flow through the core resulting in asymmetric coolant temperature decrease. The purpose of the work documented in this paper is three- fold: to validate the thermal-hydraulics (RELAP5) nodalization for VVER1000 analyses developed by University of Pisa, to assess the methodology developed by University of Pisa for coupling Thermal- Hydraulics (T-H) and 3-Dimensional (3-D) neutronics for VVER reactor type analyses; to contribute to the assessment of PARCS for coupled T-H/3D kinetics calculations in hexagonal geometry.
Analysis of the OECD/DOE/CEA VVER1000 CT-1 benchmark using Relap5/Parcs coupled codes
D'AURIA, FRANCESCO SAVERIO;
2005-01-01
Abstract
Incorporation of full three-dimensional (3D) models of the reactor core into system transient codes allows better estimation of interactions between the core behavior and plant dynamics. Considerable efforts have been made in various countries and organizations to verify and validate the capability of the coupled codes technique. For these purposes appropriate Light Water Reactor (LWR) transient benchmarks based upon programmed transients performed in Nuclear Power Plants (NPP) were recently developed on a higher “best-estimate” level. The reference problem chosen for simulation in a VVER 1000 is a Main Coolant Pump (MCP) switching-on transient when the other three MCPs are in operation. This event is characterized by rapid increase in the flow through the core resulting in asymmetric coolant temperature decrease. The purpose of the work documented in this paper is three- fold: to validate the thermal-hydraulics (RELAP5) nodalization for VVER1000 analyses developed by University of Pisa, to assess the methodology developed by University of Pisa for coupling Thermal- Hydraulics (T-H) and 3-Dimensional (3-D) neutronics for VVER reactor type analyses; to contribute to the assessment of PARCS for coupled T-H/3D kinetics calculations in hexagonal geometry.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
