Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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STATUS OF THE ASTRID CORE AT THE END OF THE PRE-CONCEPTUAL DESIGN PHASE 1

  • Chenaud, Ms. (CEA) ;
  • Devictor, N. (CEA) ;
  • Mignot, G. (CEA) ;
  • Varaine, F. (CEA) ;
  • Venard, C. (CEA) ;
  • Martin, L. (CEA) ;
  • Phelip, M. (CEA) ;
  • Lorenzo, D. (CEA) ;
  • Serre, F. (CEA) ;
  • Bertrand, F. (CEA) ;
  • Alpy, N. (CEA) ;
  • Le Flem, M. (CEA) ;
  • Gavoille, P. (CEA) ;
  • Lavastre, R. (CEA) ;
  • Richard, P. (CEA) ;
  • Verrier, D. (AREVA-NP) ;
  • Schmitt, D. (EDF)
  • Received : 2013.09.24
  • Accepted : 2013.10.02
  • Published : 2013.11.25
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Abstract

Within the framework of the ASTRID project, core design studies are being conducted by the CEA with support from AREVA and EDF. The pre-conceptual design studies are being conducted in accordance with the GEN IV reactor objectives, particularly in terms of improving safety. This involves limiting the consequences of 1) a hypothetical control rod withdrawal accident (by minimizing the core reactivity loss during the irradiation cycle), and 2) an hypothetical loss-of-flow accident (by reducing the sodium void worth). Two types of cores are being studied for the ASTRID project. The first is based on a 'large pin/small spacing wire' concept derived from the SFR V2b, while the other is based on an innovative CFV design. A distinctive feature of the CFV core is its negative sodium void worth. In 2011, the evaluation of a preliminary version (v1) of this CFV core for ASTRID underlined its potential capacity to improve the prevention of severe accidents. An improved version of the ASTRID CFV core (v2) was proposed in 2012 to comply with all the control rod withdrawal criteria, while increasing safety margins for all unprotected-loss-of-flow (ULOF) transients and improving the general design. This paper describes the CFV v2 design options and reports on the progress of the studies at the end of pre-conceptual design phase 1 concerning: - Core performance, - Intrinsic behavior during unprotected transients, - Simulation of severe accident scenarios, - Qualification requirements. The paper also specifies the open options for the materials, sub-assemblies, absorbers, and core monitoring that will continue to be studied during the conceptual design phase.

Keywords

References

  1. P. LE COZ, et al., "Sodium-Cooled Fast Reactors: the ASTRID Plant Project" - Proceedings of ICAPP 2011, Nice, France, May 2-5, 2011
  2. B. FONTAINE, et al., "Sodium-Cooled Fast Reactors: the ASTRID Plant Project" - Paper 432757, Proceedings of GLOBAL 2011, Makuhari, Japan, Dec. 11-16-5, 2011
  3. P. SCIORA et al., "A break even oxide fuel core for an innovative French sodium-cooled fast reactor : neutronic studies results", Global, Paris, Paper 9528 (2009)
  4. P. SCIORA, et al., "Low void effect core design applied on 2400 MWth SFR reactor" - Proceedings of ICAPP 2011, Nice, France, May 2-5, 2011
  5. F.VARAINE et al., "Pre-conceptual design study of ASTRID core" - Paper 432757, Proceedings of ICAPP 2012, Chicago, USA, June 24-28, 2012
  6. G. GEFFRAYE et al., "CATHARE 2 V2.5_2: A single version for various applications", Nuclear Engineering and Design, Volume 241, Issue 11, November 2011, Pages 4456-4463 https://doi.org/10.1016/j.nucengdes.2010.09.019
  7. L. ROCHE, M. Pelletier, "Modelling of the thermomechanical and physical processes in FR fuel pins using the GERMINAL code", Paper IAEA-SM-358/25, Proceedings of Symposium on MOX fuel technologies for medium and long term deployment, Vienna, 2000.
  8. M. LAINET "Recent modelling improvements in fuel performance code GERMINAL for SFR oxide fuel pins" IAEA-CN-199/241, FR13, Paris, March 4-7, 2013
  9. G. MIGNOT "Preliminary considerations on the startup phase for the ASTRID core", FR13, Paris, March 4-7, 2013
  10. DOUGLAS C. CRAWFORD et al. "An approach for fuel development and qualification", JNM 371, 2007
  11. I. MUNOZ " Recovery of materials from PHENIX to support the qualification of ASTRID design options", FR13, Paris, March 4-7, 2013
  12. E. BRUNON et al., "State-of-the-art of the conceptual design fuel sub-assembly for ASTRID", IAEA-CN-199/281, FR13, Paris, March 4-7, 2013
  13. I. GUENOT-DELAHAIE et al., "State-of-the-art of the conceptual designs of control and shutdown rods for ASTRID", poster IAEA-CN-199/285, FR13, Paris, March 4-7, 2013

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