A.V Povstyanko : rechercher sur Z-Library

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1

Change in the properties of FeCrNi and FeCrMn austenitic steels under mixed and fast neutron irradiation

V.K. Shamardin, T.M. Bulanova, V.N. Golovanov, V.S. Neustroyev, A.V. Povstyanko, Z.E. Ostrovsky

Journal:

Journal of Nuclear Materials

Année:

1996

Langue:

english

Fichier:

PDF, 710 KB

english, 1996

2

Metallurgical aspects of possibility of 9–12% chromium steel application as a structural material for first wall and blanket of fusion reactors

A.G. Ioltukhovsky, V.P. Kondrat'ev, M.V. Leont'eva-Smirnova, S.N. Votinov, V.K. Shamardin, A.V. Povstyanko, T.M. Bulanova

Journal:

Journal of Nuclear Materials

Année:

1996

Langue:

english

Fichier:

PDF, 570 KB

english, 1996

3

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

C. Petersen, A. Povstyanko, V. Prokhorov, A. Fedoseev, O. Makarov, B. Dafferner

Journal:

Journal of Nuclear Materials

Année:

2007

Langue:

english

Fichier:

PDF, 575 KB

english, 2007

4

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

E. Gaganidze, C. Petersen, E. Materna-Morris, C. Dethloff, O.J. Weiß, J. Aktaa, A. Povstyanko, A. Fedoseev, O. Makarov, V. Prokhorov

Journal:

Journal of Nuclear Materials

Année:

2011

Langue:

english

Fichier:

PDF, 695 KB

english, 2011

5

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

A. Aiello, G. Benamati, R. Melder, A. Povstyanko

Journal:

Journal of Nuclear Materials

Année:

2008

Langue:

english

Fichier:

PDF, 549 KB

english, 2008

6

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

A.G Ioltukhovskiy, M.V Leonteva-Smirnova, M.I Solonin, V.M Chernov, V.N Golovanov, V.K Shamardin, T.M Bulanova, A.V Povstyanko, A.E Fedoseev

Journal:

Journal of Nuclear Materials

Année:

2002

Langue:

english

Fichier:

PDF, 86 KB

english, 2002

7

A materials-technology investigation of the control rod bushes of reactor type BOR-60

V. N. Golovanov, A. V. Povstyanko, V. S. Neustroev, V. M. Kosenkov, E. P. Klochkov, V. K. Shamardin

Journal:

Année:

1985

Langue:

english

Fichier:

PDF, 250 KB

english, 1985

8

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

A. V. Tselishchev, V. S. Ageev, Yu. P. Budanov, A. G. Ioltukhovskii, N. M. Mitrofanova, M. V. Leontieva-Smirnova, I. A. Shkabura, L. M. Zabud’ko, A. V. Kozlov, V. V. Mal’tsev, A. V. Povstyanko

Journal:

Année:

2010

Langue:

english

Fichier:

PDF, 212 KB

english, 2010

9

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

C. Petersen, A. Povstyanko, V. Prokhorov, A. Fedoseev, O. Makarov, M. Walter

Journal:

Journal of Nuclear Materials

Année:

2009

Langue:

english

Fichier:

PDF, 368 KB

english, 2009

10

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

V.K. Shamardin, V.N. Golovanov, T.M. Bulanova, A.V. Povstyanko, A.E. Fedoseev, Z.E. Ostrovsky, Yu.D. Goncharenko

Journal:

Journal of Nuclear Materials

Année:

2002

Langue:

english

Fichier:

PDF, 370 KB

english, 2002

11

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

A.G Ioltukhovsky, M.V Leontyeva-Smirnova, Y.I Kazennov, E.A Medvedeva, A.V Tselishchev, V.K Shamardin, A.V Povstyanko, S.E Ostrovsky, A.M Dvoryashin, S.I Porollo, A.N Vorobyev, V.S Khabarov

Journal:

Journal of Nuclear Materials

Année:

1998

Langue:

english

Fichier:

PDF, 1.86 MB

english, 1998

12

Investigations of BOR-60 Structural Materials and Prospects for Further Work

V.N. Golovanov, V.K. Shamardin, V.I. Prokhorov, V.S. Neustroev, V.A. Kazakov, G.P. Kobylyanskii, A.M. Pecherin, A.V. Povstyanko, T.M. Bulanova, V.A. Krasnoselov, A.E. Fedoseev

Journal:

Année:

2001

Langue:

english

Fichier:

PDF, 137 KB

english, 2001

13

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

Kaito, Takeji, Yano, Yasuhide, Ohtsuka, Satoshi, Inoue, Masaki, Tanaka, Kenya, Fedoseev, Alexander E., Povstyanko, Alexander V., Novoselov, Andrey

Journal:

Journal of Nuclear Science and Technology

Année:

2013

Langue:

english

Fichier:

PDF, 1.30 MB

english, 2013

14

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

KAITO, Takeji, UKAI, Shigeharu, POVSTYANKO, Alexander V., EFIMOV, Vladimir N.

Journal:

Journal of Nuclear Science and Technology

Année:

2009

Langue:

english

Fichier:

PDF, 1.07 MB

english, 2009

15

Microstructural Features of Embrittlement in Irradiated Steels and Alloys

Neustroev, V.S., Povstyanko, A.V., Shamardin, V.K.

Journal:

Materials Science Forum

Année:

1992

Fichier:

PDF, 455 KB

1992

16

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

Gaganidze, E., Petersen, C., Aktaa, J., Povstyanko, A., Prokhorov, V., Diegele, E., Lässer, R.

Journal:

Année:

2011

Langue:

english

Fichier:

PDF, 487 KB

english, 2011

17

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

Schneider, H.-C., Petersen, C., Povstyanko, A.V., Fedoseev, A.E., Makarov, O.

Journal:

Fusion Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 1.78 MB

english, 2017