Title of article :
Sodium fast reactor evaluation: Core materials
Author/Authors :
Cheon، نويسنده , , Jin Sik and Lee، نويسنده , , Chan Bock and Lee، نويسنده , , Byoung Oon and Raison، نويسنده , , J.P. and Mizuno، نويسنده , , T. and Delage، نويسنده , , F. and Carmack، نويسنده , , J.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2009
Pages :
7
From page :
324
To page :
330
Abstract :
In the framework of the Generation IV Sodium Fast Reactor (SFR) Program the Advanced Fuel Project has conducted an evaluation of the available fuel systems supporting future sodium cooled fast reactors. In this paper the status of available and developmental materials for SFR core cladding and duct applications is reviewed. To satisfy the Generation IV SFR fuel requirements, an advanced cladding needs to be developed. The candidate cladding materials are austenitic steels, ferritic/martensitic (F/M) steels, and oxide dispersion strengthened (ODS) steels. A large amount of irradiation testing is required, and the compatibility of cladding with TRU-loaded fuel at high temperatures and high burnup must be investigated. The more promising F/M steels (compared to HT9) might be able to meet the dose requirements of over 200 dpa for ducts in the GEN-IV SFR systems.
Journal title :
Journal of Nuclear Materials
Serial Year :
2009
Journal title :
Journal of Nuclear Materials
Record number :
1365031
Link To Document :
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