Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2.7

• Published in: Annals of nuclear energy Vol. 87; pp. 308 - 317
• Main Authors: Ramos, Enrique, Roman, Jose E., Abarca, Agustín, Miró, Rafael, Bermejo, Juan A.
• Format: Journal Article
• Language: English
• Published: Elsevier Ltd 01.01.2016
• Subjects: COBRA-TF; Control rods; Joining; Mathematical models; Nuclear engineering; Nuclear power generation; Nuclear reactor components; Nuclear reactors; Parallel computing; PARCSv2.7; PETSc; Sub-channel simulation; PETSc; Parallel computing; Sub-channel simulation; PARCSv2.7; COBRA-TF
• ISSN: 0306-4549; 1873-2100
• DOI: 10.1016/j.anucene.2015.09.016

•An MPI parallel version of the thermal–hydraulic subchannel code COBRA-TF has been developed.•The parallel code has been coupled to the 3D neutron diffusion code PARCSv2.7.•The new codes are validated with a control rod drop transient. In order to reduce the response time when simulating large reactors in detail, a parallel version of the thermal–hydraulic subchannel code COBRA-TF (CTF) has been developed using the standard Message Passing Interface (MPI). The parallelization is oriented to reactor cells, so it is best suited for models consisting of many cells. The generation of the Jacobian matrix is parallelized, in such a way that each processor is in charge of generating the data associated with a subset of cells. Also, the solution of the linear system of equations is done in parallel, using the PETSc toolkit. With the goal of creating a powerful tool to simulate the reactor core behavior during asymmetrical transients, the 3D neutron diffusion code PARCSv2.7 (PARCS) has been coupled with the parallel version of CTF (pCTF) using the Parallel Virtual Machine (PVM) technology. In order to validate the correctness of the parallel coupled code, a control rod drop transient has been simulated comparing the results with the real experimental measures acquired during an NPP real test.