Validation of 3D neutronic-thermalhydraulic coupled codes RELAP5/PARCSv2.7 and TRACEv5.0P3/PARCSv3.0 against a PWR control rod drop transient. Issue 8 (3rd August 2017)

• Record Type: Journal Article
• Authors: Garcia-Fenoll, Marina; Mesado, Carles; Barrachina, Teresa; Miró, Rafael; Verdú, Gumersindo; Bermejo, Juan Antonio; López, Arturo; Ortego, Alberto
• Is Part Of: Journal of nuclear science and technology. Volume 54:Issue 8(2017)
• Page Start: 908
• Page End: 919
• Publication Date: 2017-08-03
• Subjects: PWR -- coupled codes -- rod drop -- TRACE/PARCS -- RELAP5/PARCS; Nuclear engineering -- Periodicals; Nuclear physics -- Periodicals; Nuclear energy -- Periodicals; 621.4805
• DOI: 10.1080/00223131.2017.1329035
• Languages: English
• ISSNs: 0022-3131

Abstract

ABSTRACT: In nuclear safety field, neutronic and thermalhydraulic codes performance is an important issue. New capabilities implementation, as well as models and tools improvements are a significant part of the community effort in looking for better nuclear power plants (NPP) designs. A procedure to analyze the PWR response to local deviations on neutronic or thermalhydraulic parameters is being developed. This procedure includes the simulation of Incore and Excore neutron flux detectors signals. A control rod drop real plant transient is used to validate the used codes and their new capabilities. Cross-section data are obtained by means of the SIMTAB methodology. Detailed thermalhydraulic models were developed: RELAP5 and TRACE models simulate three different azimuthal zones. Besides, TRACE model is performed with a fully three-dimensional core, thus, the cross-flow can be obtained. A Cartesian vessel represents the fuel assemblies and a cylindrical vessel the bypass and downcomer. Simulated detectors signals are obtained and compared with the real data collected during a control rod drop trial at a PWR NPP and also with data obtained with SIMULATE-3K code.