Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes

Spasov, I. and Mitkov, S. and Kolev, N. P. and Sánchez-Cervera Huerta, Santiago and García Herranz, Nuria and Sabater Alcaraz, Adrián and Cuervo Gómez, Diana and Jiménez, J. and Sánchez, V. H. and Vyskocil, L. (2017). Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes. "Nuclear Engineering and Design", v. 321 ; pp. 26-37. ISSN 0029-5493. https://doi.org/10.1016/j.nucengdes.2017.03.032.

Description

Title: Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
Author/s:
  • Spasov, I.
  • Mitkov, S.
  • Kolev, N. P.
  • Sánchez-Cervera Huerta, Santiago
  • García Herranz, Nuria
  • Sabater Alcaraz, Adrián
  • Cuervo Gómez, Diana
  • Jiménez, J.
  • Sánchez, V. H.
  • Vyskocil, L.
Item Type: Article
Título de Revista/Publicación: Nuclear Engineering and Design
Date: September 2017
Volume: 321
Subjects:
Freetext Keywords: VVER MSLB; Core boundary condition problem; Nodal methods; Best-estimate simulation
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

This paper summarizes the nodal level results from the VVER MSLB core simulation in the NURESAFE EU project. The main objective is to implement and verify new developments in the models and couplings of 3D core simulators for cores with hexagonal fuel assemblies. Recent versions of the COBAYA and DYN3D core physics codes, and the FLICA4 and CTF thermal-hydraulic codes were tested standalone and coupled through standardized coupling functions in the Salome platform. The MSLB core transient was analyzed in coupled code simulation of a core boundary condition problem derived from the OECD VVER MSLB benchmark. The impact of node sub-division and different core mixing models, as well as the effects of CFD computed core inlet thermal-hydraulic boundary conditions on the core dynamics were explored.

Funding Projects

TypeCodeAcronymLeaderTitle
FP7323263NURESAFEUnspecifiedNUCLEAR REACTOR SAFETY SIMULATION PLATFORM

More information

Item ID: 49805
DC Identifier: http://oa.upm.es/49805/
OAI Identifier: oai:oa.upm.es:49805
DOI: 10.1016/j.nucengdes.2017.03.032
Official URL: https://www.sciencedirect.com/science/article/pii/S0029549317301449?via%3Dihub
Deposited by: Memoria Investigacion
Deposited on: 23 Apr 2018 16:26
Last Modified: 19 Mar 2019 16:04
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