ODS cladding fuel pins irradiation tests using the BOR-60 reactor

References

• Shimakawa , Y , Kasai , S , Konomura , M and Toda , M . 2002 . An innovative concept of a sodium-cooled reactor to pursue high economic competitiveness . Nucl Technol , 140 : 1
   Web of Science ®Google Scholar
• Ukai , S , Mizuta , S , Fujiwara , M , Okuda , T and Kobayashi , T . 2002 . Development of 9Cr-ODS martensitic steel claddings for fuel pins by means of ferrite to austenite phase transformation . J Nucl Sci Technol. , 39 ( 7 ) : 778
   Web of Science ®Google Scholar
• Ukai , S , Okuda , T , Fujiwara , M , Kobayashi , T , Mizuta , S and Nakashima , H . 2002 . Characterization of high temperature creep properties in recrystallized 12Cr-ODS ferritic steel claddings . J Nucl Sci Technol. , 39 ( 8 ) : 872
   Web of Science ®Google Scholar
• Ukai , S and Fujiwara , M . 2002 . Perspective of ODS alloys application in nuclear environments . J Nucl Mater. , 307–311 : 749
   Web of Science ®Google Scholar
• Ukai , S , Kaito , T , Ohtsuka , S , Narita , T , Fujiwara , M and Kobayashi , T . 2003 . Production and properties of nano-scale oxide dispersion strengthened (ODS) 9Cr martensitic steel claddings . ISIJ Int. , 43 ( 12 ) : 2038
   Web of Science ®Google Scholar
• Ohtsuka , S , Ukai , S , Fujiwara , M , Kaito , T and Narita , T . 2005 . Nano-structure control in ODS martensitic steels by means of selecting titanium and oxygen contents . J Phys Chem Solids. , 66 : 571
   Google Scholar
• Yoshitake , T , Abe , Y , Akasaka , N , Ohtsuka , S , Ukai , S and Kimura , A . 2004 . Ring-tensile properties of irradiated oxide dispersion strengthened ferritic/martensitic steel claddings . J Nucl Mater. , 329–333 : 342
   Google Scholar
• Yamashita , S , Yoshitake , T , Akasaka , N , Ukai , S and Kimura , A . 2005 . Mechanical behavior of oxide dispersion strengthened steels irradiated in Joyo . Mater Trans. , 46 ( 3 ) : 493
   Google Scholar
• Kaito , T , Ohtsuka , S , Inoue , M , Asayama , T , Uwaba , T , Mizuno , T , Ukai , S , Furukawa , T , Ito , C , Kagota , E , Kitamura , R , Aoyama , A and Inoue , T . 2009 . In-pile creep rupture properties of ODS ferritic steel claddings . J Nucl Mater. , 386–388 : 294
   Web of Science ®Google Scholar
• Yano , Y , Ogawa , R , Yamashita , S , Ohtsuka , S , Kaito , T , Akasaka , N , Inoue , M , Yoshitake , T and Tanaka , K . 2011 . Effects of neutron irradiation on tensile properties of oxide dispersion strengthened (ODS) steel claddings . J Nucl Mater. , 419 : 305
   Google Scholar
• Ukai , S , Kaito , T , Seki , M , Mayorshin , A A and Shishalov , O V . 2005 . Oxide dispersion strengthened (ODS) fuel pins fabrication for BOR-60 irradiation test . J Nucl Sci Technol. , 42 ( 1 ) : 109
   Web of Science ®Google Scholar
• Kaito , T , Ukai , S , Povstyanko , A V and Effimov , V N . 2009 . Fuel pin irradiation test at up to 5 at% burnup in BOR-60 for oxide-dispersion-strengthened ferritic steel claddings . J Nucl Sci Technol. , 46 ( 6 ) : 529
   Web of Science ®Google Scholar
• Seki , M , Hirako , K , Kono , S , Kihara , Y , Kaito , T and Ukai , S . 2004 . Pressurized resistance welding technology development in 9Cr-ODS martensitic steels . J Nucl Mater. , 329–333 : 1534
   Web of Science ®Google Scholar
• Porollo , S I , Konobeev , Y V and Garner , F A . 2009 . Swelling and microstructure of austenitic stainless steel ChS-68 CW after high dose neutron irradiation . J Nucl Mater. , 393 : 61
   Google Scholar
• Kashihara , H , Shikakura , S , Yokouchi , Y , Shibahara , I , Matsushima , H and Yamamoto , K . 1990 . “ Dimensional stability of FBR fuel pins with modified type 316 stainless steel cladding at high burn-up ” . In Proceedings of the International Conference on Fast Reactor Core and Fuel Structural Behaviour 243 Inverness , , UK 1990 June 4—6 [ISBN-10: 0727715666, ISBN-13: 978-0-7277-1566-1]
   Google Scholar
• Herbig , R , Rudolph , K , Lindau , B , Skiba , O V and Maershin , A A . 1993 . Vibrocompacted fuel for the liquid metal reactor BOR-60 . J Nucl Mater. , 204 : 93
   Web of Science ®Google Scholar
• Mrowec , S. 1980 . Defects and diffusion in solids, an introduction. Material science monographs , Vol. 5 , PWN-Polish Scientific Publishers-Warszawa .
   Google Scholar
• Kasada , R , Lee , S G , Lee , J H , Omura , T , Zhang , C H , Dou , P , Isselin , J , Kimura , A , Inoue , M , Ukai , S , Ohnuki , S , Fujisawa , T , Okuda , T and Abe , F . 2009 . “ Super ODS steels R&D for fuel cladding of next generation nuclear systems 5) Mechanical properties and microstructure ” . In Proceeding of the International Conference on Advances in Nuclear Power Plants 2009 (ICAPP 2009) 2211 Tokyo , Japan 2009 May 10-14 [ISBN: 978-1-61738-608-4]
   Google Scholar
• Ohtsuka , S , Kaito , T , Yano , Y , Yamashita , S , Ogawa , R , Uwaba , T , Koyama , S and Tanaka , K . Investigation of the cause of peculiar irradiation behavior of 9Cr-ODS steel in BOR-60 irradiation test . J Nucl Sci Technol. , Forthcoming
   Google Scholar