Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking

Lázaro Núñez, Álvaro and Ammirabile, Luca and Bandini, G. and Darmet, G. and Massara, S. and Dufour, Jean Francois and Tosello, A. and Gallego Díaz, Eduardo F. and Jiménez Varas, Gonzalo and Mikityuk, K. and Schikorr, M. and Bubelis, E. and Ponomarev, A. and Kruessmann, R. and Stempniewicz, M. (2014). Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking. "Nuclear Engineering and Design", v. 266 (n. null); pp. 1-16. ISSN 0029-5493. https://doi.org/10.1016/j.nucengdes.2013.10.019.

Description

Title: Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking
Author/s:
  • Lázaro Núñez, Álvaro
  • Ammirabile, Luca
  • Bandini, G.
  • Darmet, G.
  • Massara, S.
  • Dufour, Jean Francois
  • Tosello, A.
  • Gallego Díaz, Eduardo F.
  • Jiménez Varas, Gonzalo
  • Mikityuk, K.
  • Schikorr, M.
  • Bubelis, E.
  • Ponomarev, A.
  • Kruessmann, R.
  • Stempniewicz, M.
Item Type: Article
Título de Revista/Publicación: Nuclear Engineering and Design
Date: January 2014
ISSN: 0029-5493
Volume: 266
Subjects:
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

The new reactor concepts proposed in the Generation IV International Forum (GIF) are conceived to improve the use of natural resources, reduce the amount of high-level radioactive waste and excel in their reliability and safe operation. Among these novel designs sodium fast reactors (SFRs) stand out due to their technological feasibility as demonstrated in several countries during the last decades. As part of the contribution of EURATOM to GIF the CP-ESFR is a collaborative project with the objective, among others, to perform extensive analysis on safety issues involving renewed SFR demonstrator designs. The verification of computational tools able to simulate the plant behaviour under postulated accidental conditions by code-to-code comparison was identified as a key point to ensure reactor safety. In this line, several organizations employed coupled neutronic and thermal-hydraulic system codes able to simulate complex and specific phenomena involving multi-physics studies adapted to this particular fast reactor technology. In the “Introduction” of this paper the framework of this study is discussed, the second section describes the envisaged plant design and the commonly agreed upon modelling guidelines. The third section presents a comparative analysis of the calculations performed by each organisation applying their models and codes to a common agreed transient with the objective to harmonize the models as well as validating the implementation of all relevant physical phenomena in the different system codes.

Funding Projects

TypeCodeAcronymLeaderTitle
FP7232658CP-ESFRCOMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVESCollaborative Project on European Sodium Fast Reactor

More information

Item ID: 35676
DC Identifier: http://oa.upm.es/35676/
OAI Identifier: oai:oa.upm.es:35676
DOI: 10.1016/j.nucengdes.2013.10.019
Official URL: http://www.sciencedirect.com/science/article/pii/S0029549313005736
Deposited by: Memoria Investigacion
Deposited on: 28 Sep 2015 16:53
Last Modified: 23 May 2019 07:51
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