Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis

Lázaro Núñez, Álvaro and Schikorr, M and Mikityuk, K. and Ammirabile, Luca and Bandini, G. and Darmet, G. and Schmitt, D. and Dufour, Jean Francois and Tosello, A. and Gallego Díaz, Eduardo F. and Jiménez Varas, Gonzalo and Bubelis, E. and Ponomarev, A. and Kruessmann, R. and Struwe, D. and Stempniewicz, M. (2014). Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis. "Nuclear Engineering and Design", v. 277 (n. null); pp. 265-276. ISSN 0029-5493. https://doi.org/10.1016/j.nucengdes.2014.02.029.

Description

Title: Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis
Author/s:
  • Lázaro Núñez, Álvaro
  • Schikorr, M
  • Mikityuk, K.
  • Ammirabile, Luca
  • Bandini, G.
  • Darmet, G.
  • Schmitt, D.
  • Dufour, Jean Francois
  • Tosello, A.
  • Gallego Díaz, Eduardo F.
  • Jiménez Varas, Gonzalo
  • Bubelis, E.
  • Ponomarev, A.
  • Kruessmann, R.
  • Struwe, D.
  • Stempniewicz, M.
Item Type: Article
Título de Revista/Publicación: Nuclear Engineering and Design
Date: October 2014
ISSN: 0029-5493
Volume: 277
Subjects:
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

Full text

[img]
Preview
PDF - Requires a PDF viewer, such as GSview, Xpdf or Adobe Acrobat Reader
Download (7MB) | Preview

Abstract

The new reactor concepts proposed in the Generation IV International Forum require the development and validation of computational tools able to assess their safety performance. In the first part of this paper the models of the ESFR design developed by several organisations in the framework of the CP-ESFR project were presented and their reliability validated via a benchmarking exercise. This second part of the paper includes the application of those tools for the analysis of design basis accident (DBC) scenarios of the reference design. Further, this paper also introduces the main features of the core optimisation process carried out within the project with the objective to enhance the core safety performance through the reduction of the positive coolant density reactivity effect. The influence of this optimised core design on the reactor safety performance during the previously analysed transients is also discussed. The conclusion provides an overview of the work performed by the partners involved in the project towards the development and enhancement of computational tools specifically tailored to the evaluation of the safety performance of the Generation IV innovative nuclear reactor designs.

Funding Projects

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

More information

Item ID: 35677
DC Identifier: http://oa.upm.es/35677/
OAI Identifier: oai:oa.upm.es:35677
DOI: 10.1016/j.nucengdes.2014.02.029
Official URL: http://www.sciencedirect.com/science/journal/00295493/277
Deposited by: Memoria Investigacion
Deposited on: 29 Sep 2015 16:35
Last Modified: 23 May 2019 07:52
  • Logo InvestigaM (UPM)
  • Logo GEOUP4
  • Logo Open Access
  • Open Access
  • Logo Sherpa/Romeo
    Check whether the anglo-saxon journal in which you have published an article allows you to also publish it under open access.
  • Logo Dulcinea
    Check whether the spanish journal in which you have published an article allows you to also publish it under open access.
  • Logo de Recolecta
  • Logo del Observatorio I+D+i UPM
  • Logo de OpenCourseWare UPM