Published December 2, 2022 | Version v1
Conference paper Restricted

Analysis of a Main Steam Line Break accident in the NuScale reactor by means of the coupled codes TRACE/PARCS

  • 1. Universidad Politécnica de Madrid

Description

In the present study, a Main Steam Line Break (MSLB) sequence has been simulated by means of the thermal-hydraulic (TH) and neutronic codes, TRACE and PARCS respectively. In that sense, UPM research group has developed a full-plant TH model of NuScale for TRACEv5 patch 6, along with a 3D kinetics model of the nodal diffusion code PARCSv332.

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Additional details

Funding

European Commission
McSAFER – High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors 945063