185 research outputs found
An Advanced TRACE Modeling Approach: Automatic Connection of 3D Cartesian and Cylindrical VESSEL Components in Integral Plant Models
Best estimate system thermal-hydraulic codes in the nuclear engineering community, e.g., TRACE, RELAP3D, CATHARE-3, etc., were extended with 3D coarse-mesh components to better describe the 3D Thermal-Hydraulic (TH) phenomena taking place within the Reactor Pressure Vessel (RPV) and the core. The RPV is usually shaped like a cylinder while the core is mostly a cube. Hence, the TRACE code is equipped with a Cylindrical VESSEL and a Cartesian VESSEL. The former one is to represent the RPV (including core), pressurizer, and steam generator. The latter one is more appropriate to represent the core. The two components are connected by two Vessel-Junctions (VJ) at the core inlet and outlet. Due to the different nodalization between the two VESSELs, the analyst needs to do repetitive and error-prone work defining the cell-to-cell junctions and their TH parameters. To facilitate this process, the Karlsruhe Institute of Technology (KIT) has developed an automatic approach based on a mesh-constructing and field-mapping library, namely the MEDCoupling. These new capabilities of TRACE are demonstrated by the analysis of the coolant mixing for an academic case and the AP1000 reactor
Multiphysics modeling of a reactivity insertion transient at different fidelity levels in support to the safety assessment of a SMART-like small modular reactor
Coupling of PARCS with the Porous-media two-phase flow code Twoporflow for the imporved analysis of SMR-cores using the IcoCo-Approach
Investigations of a BWR SB-LOCA severe Accident scenario including SAM to prevent the reactor pressure vessel failure using the german Code ATHLET-CD
Assessment of the ASTEC Model of a Generic BWR-4 Mark-1 Peach Bottom Unit-2 NPP and Analysis of the ST-SBO Severe Accident Scenario
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