A. Povstyanko

发表

Mechanical properties and TEM examination of RAFM steels irradiated up to 70 dpa in BOR-60

J. Aktaa, E. Gaganidze, C. Petersen, 2011 .

Fuel Pin Irradiation Test at up to 5 at% Burnup in BOR-60 for Oxide-Dispersion-Strengthened Ferritic Steel Claddings

A. Povstyanko, S. Ukai, T. Kaito, 2009 .

Evolution of the mechanical properties and microstructure of ferritic–martensitic steels irradiated in the BOR-60 reactor

A. Povstyanko, A. E. Fedoseev, Z. Ostrovsky, 2002 .

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

A. Novoselov, Kenya Tanaka, A. Povstyanko, 2013 .

Heat resistant reduced activation 12% Cr steel of 16Cr12W2VTaB type-advanced structural material for fusion and fast breeder power reactors

M. I. Solonin, V. Chernov, A. Povstyanko, 2002 .

Influence of operation conditions on structure and properties of 12% Cr steels as candidate structural materials for fusion reactor

E. A. Medvedeva, S. Ostrovsky, A. Povstyanko, 1998 .

Impact property degradation of ferritic/martensitic steels after the fast reactor irradiation ‘ARBOR 1’

C. Petersen, A. Povstyanko, A. E. Fedoseev, 2007 .

Development of structural steel for fuel elements and fuel assemblies of sodium-cooled fast reactors

A. V. Kozlov, A. Povstyanko, V. S. Ageev, 2010 .

Low cycle fatigue properties of reduced activation ferritic/martensitic steels after high-dose neutron irradiation

J. Aktaa, E. Gaganidze, C. Petersen, 2011 .

Tensile and low cycle fatigue properties of different ferritic/martensitic steels after the fast reactor irradiation ‘ARBOR 1’

C. Petersen, A. Povstyanko, A. E. Fedoseev, 2009 .

Repeatability of irradiation damage and of recovery by post-irradiation annealing of EUROFER base steels

C. Petersen, A. Povstyanko, A. E. Fedoseev, 2017 .

Mechanical properties of Eurofer 97 in Pb–16Li and irradiation effect

G. Benamati, A. Povstyanko, A. Aiello, 2008 .