Lead-Cooled Fast Reactor Systems and the Fuels and Materials Challenges

Anticipated developments in the consumer energy market have led developers of nuclear energy concepts to consider how innovations in energy technology can be adapted to meet consumer needs. Properties of molten lead or lead-bismuth alloy coolants in lead-cooled fast reactor (LFR) systems offer potential advantages for reactors with passive safety characteristics, modular deployment, and fuel cycle flexibility. In addition to realizing those engineering objectives, the feasibility of such systems will rest on development or selection of fuels and materials suitable for use with corrosive lead or lead-bismuth. Three proposed LFR systems, with varying levels of concept maturity, are described to illustrate their associated fuels and materials challenges. Nitride fuels are generally favored for LFR use over metal or oxide fuels due to their compatibility with molten lead and lead-bismuth, in addition to their high atomic density and thermal conductivity. Ferritic/martensitic stainless steels, perhaps with silicon and/or oxide-dispersion additions for enhanced coolant compatibility and improved high-temperature strength, might prove sufficient for low-to-moderate-temperature LFRs, but it appears that ceramics or refractory metal alloys will be necessary for higher-temperature LFR systems intended for production of hydrogen energy carriers.

[1]  I. Ricapito,et al.  Corrosion behaviour of steels and refractory metals and tensile features of steels exposed to flowing PbBi in the LECOR loop , 2003 .

[2]  Pavel Hejzlar,et al.  Performance of the Lead-Alloy-Cooled Reactor Concept Balanced for Actinide Burning and Electricity Production , 2004 .

[3]  Yuji Kurata,et al.  Excellent corrosion resistance of 18Cr–20Ni–5Si steel in liquid Pb–Bi , 2004 .

[4]  R. V. Strain,et al.  Fuel-sodium reaction product and its influence on breached mixed-oxide fuel pins , 1993 .

[5]  Ronald G. Ballinger,et al.  Corrosion Studies in Support of Medium-Power Lead-Alloy-Cooled Reactor , 2004 .

[6]  Walt Patterson Transforming Electricity: The Coming Generation of Change , 1999 .

[7]  James J. Sienicki,et al.  STAR-H2 : a long-refueling interval battery reactor for hydrogen and water supply to cities of developing countries. , 2004 .

[8]  P. Marmy,et al.  Charpy impact tests on martensitic/ferritic steels after irradiation in SINQ target-3 , 2005 .

[9]  K. Rudolph,et al.  Vibrocompacted fuel for the liquid metal reactor BOR-60 , 1993 .

[10]  Jinsuo Zhang,et al.  Review of the studies on fundamental issues in LBE corrosion , 2008 .

[11]  S. Zinkle,et al.  Operating temperature windows for fusion reactor structural materials , 2000 .

[12]  J. Kittel,et al.  History of Fast-reactor Fuel Development , 1993 .

[13]  A. Weisenburger,et al.  Corrosion Behavior of FBR Candidate Materials in Stagnant Pb-Bi at Elevated Temperature , 2004 .

[14]  Jinsuo Zhang,et al.  Corrosion/precipitation in non-isothermal and multi-modular LBE loop systems , 2004 .

[15]  M. G. Horsten,et al.  Irradiation Behavior of Ferritic-Martensitic 9–12%Cr Steels , 2000 .

[16]  Frank Zimmermann,et al.  Results of steel corrosion tests in flowing liquid Pb/Bi at 420-600 °C after 2000 h , 2002 .

[17]  Gaurav Gupta,et al.  Radiation Resistance of Advanced Ferritic-Martensitic Steel HCM12A , 2005 .

[18]  V. Randle,et al.  The Role of the Coincidence Site Lattice in Grain Boundary Engineering , 1996 .

[19]  Cliff Bybee Davis,et al.  Design of an Actinide-Burning, Lead or Lead-Bismuth Cooled Reactor that Produces Low-Cost Electricity , 2000 .

[20]  C. Fazio,et al.  Compatibility tests of steels in flowing liquid lead–bismuth , 2001 .

[21]  Douglas C. Crawford,et al.  Fuels for sodium-cooled fast reactors: US perspective , 2007 .

[22]  F. Balbaud-Célérier,et al.  Corrosion of metallic materials in flowing liquid lead-bismuth , 2002 .

[23]  Robert Hill,et al.  The design rationale of the IFR , 1997 .

[24]  Robert Hill,et al.  An advanced modular HLMC reactor concept featuring economy, safety, and proliferation resistance. , 2000 .

[25]  Neil E. Todreas,et al.  Design Strategy and Constraints for Medium-Power Lead-Alloy–Cooled Actinide Burners , 2004 .

[26]  L. S. Crespo,et al.  Behaviour of F82H mod. stainless steel in lead–bismuth under temperature gradient , 2001 .

[27]  R. Klueh,et al.  High-Chromium Ferritic and Martensitic Steels for Nuclear Applications , 2001 .

[28]  Neil E. Todreas,et al.  Fertile-Free Fast Lead-Cooled Incinerators for Efficient Actinide Burning , 2004 .

[29]  D. Struwe,et al.  The Potential of the LFR and the ELSY Project , 2007 .

[30]  N. Akasaka,et al.  Phase stability of oxide dispersion-strengthened ferritic steels in neutron irradiation , 2002 .

[31]  Hj. Matzke,et al.  Science of advanced LMFBR fuels , 1986 .