Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator

Nuclear Engineering and Design

Volumn 241, Issue 8, 2011, Pages 3021-3031

  Bortot, S ^a   Moisseytsev, A ^b   Sienicki, J J ^b   Artioli, Carlo ^c  

^a POLITECNICO DI MILANO   (Italy)

^b ARGONNE NATIONAL LABORATORY   (United States)

^c ENEA   (Italy)

Author keywords

[No Author keywords available]

Indexed keywords

BEGINNING OF LIVES; CORE CONFIGURATION; CORE DESIGN; DESIGN STUDIES; END-OF-LIFE; ENERGY SECURITY; FLOW DUCT; FUEL ASSEMBLY; HEAT TRANSPORT; LEAD COOLED FAST REACTOR; NATURAL CIRCULATION; NEUTRONICS; PEAKING FACTOR; POWER LEVELS; PROLIFERATION RESISTANCE; RADIAL POWER PROFILE; REACTIVITY COEFFICIENTS; SECURE TRANSPORTABLE AUTONOMOUS REACTORS; TECHNOLOGICAL CONSTRAINTS; THERMAL-HYDRAULIC ANALYSIS;

FAST REACTORS; NATURAL CONVECTION;

STRUCTURAL DESIGN;

EID: 79961026586     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2011.04.012     Document Type: Article

References (24)

1. L. Barzotti Deterministic analysis of the encapsulated nuclear heat source by the European transport code ERANOS Proceedings of the International Conference on Fast Reactors and Related Fuel Cycles: Challenges and Opportunities (FR09) 2009
2. S. Bortot Conceptual core design of a generation IV LFR demonstration plant Proceedings of the International Conference on the PHYSics Of Reactors (PHYSOR 2010) 2010
3. S. Bortot Design study on a metallic fuel core option for a GEN-IV LFR DEMO Transactions of the American Nuclear Society Winter Meeting 2010
4. W.J. Carmack Metallic fuels for advanced reactors J. Nucl. Mater. 392 2009 139 150
5. L. Cinotti The potential of the LFR and the ELSY project Proceedings of the 2007 International Congress on Advances in Nuclear Power Plants (ICAPP 2007) 2007
6. L. Cinotti The ELSY project Proceedings of the International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" (PHYSOR'08) 2008
7. C. Fazio Lead, lead-bismuth eutectic technologies and materials studies for transmutation systems Proceedings of Global 2009 2009
8. L.R. Greenwood, and F.A. Garner Transmutation of Mo, Re, W Hf, and V in various irradiation test facilities and STARFIRE J. Nucl. Mater. 212-215 1994 635 639
9. Joint Evaluated File (JEF) Project The JEFF-3.1 Nuclear Data Library. Technical Report JEFF Report 21, OECD/NEA 2006
10. Moisseytsev, A;, 2003. Passive load follow analysis of the STAR-LM and STAR-H2 systems. Ph.D. Dissertation. Texas A&M University, College Station.
11. G. Rimpault Physics Documentation of ERANOS: The Ecco Cell Code. Technical Report DER-SPRC-LEPh-97-001, CEA 1997
12. G. Rimpault The ERANOS code and data system for fast reactor neutronic analyses Proceedings of the International Conference on the PHYSics of Reactors (PHYSOR 2002) 2002
13. J.M. Ruggieri TGV: A Coarse Mesh 3-Dimensional Diffusion-Transport Module for the CCRR/ERANOS Code System. Technical Report DRNR-SPCI-LEPh-93-209, CEA 1993
14. M. Sarotto ELSY Core Design, Static Dynamic and Safety Parameters with the Open Square FA. Technical Report Deliverable D8, EURATOM 2009
15. J.J. Sienicki STAR performer Nucl. Eng. Int. 2005 24
16. J.J. Sienicki Status of development of the small secure transportable autonomous reactor (SSTAR) for worldwide sustainable nuclear energy supply Proceedings of the 2007 International Congress on Advances in Nuclear Power Plants (ICAPP 2007) 2007
17. J.J. Sienicki SUPERSTAR: an improved natural circulation, lead-cooled, small modular fast reactor for international deployment Proceedings of the 2011 International Congress on Advances in Nuclear Power Plants (ICAPP 2011) 2011
18. N. Spring The mPower modular reactor Nucl. Power Int. 2010 16 18
19. R. Thetford, and V. Sobolev Recommended Properties of Fuel, Cladding and Coolant for EFIT Predesign. Deliverable 3.4 (Draft 0.4), IP EUROTRANS Contract n. FI6W-CT-2004-516520, DM3 AFTRA WP3.1 2005
20. A.E. Waltar, and A.B. Reynolds Fast Breeder Reactors 1981 Pergamon Press New York
21. L. Walters An innovative particulate metallic fuel for next generation nuclear energy Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants (ICAPP 2010) 2010
22. A. Weisenburger T91 cladding tubes with and without modified FeCrAlY coatings exposed in LBE at different flow, stress and temperature conditions J. Nucl. Mater. 376 2008 274 281
23. W.S. Yang Lead-cooled, long-life fast reactor concepts for remote deployment Proceedings of the 2005 International Congress on Advances in Nuclear Power Plants (ICAPP 2005) 2005
24. T. Yokoo A design study on the FBR metal fuel and core for commercial applications J. Nucl. Sci. Technol. 37 2000 636 645