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Refinado por: Nome da Publicação: Soviet Atomic Energy remover
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1
Determination of the cracking resistance characteristics of irradiated thin-walled parts
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Determination of the cracking resistance characteristics of irradiated thin-walled parts

Vainer, L. A.

Soviet Atomic Energy, 1989-04, Vol.66 (4), p.309-312 [Periódico revisado por pares]

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2
Effect of simulated nuclear coolant environment on the resistance of the materials of the thin-walled elements and assemblies to fatigue crack growth
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Effect of simulated nuclear coolant environment on the resistance of the materials of the thin-walled elements and assemblies to fatigue crack growth

Vainer, L. A.

Soviet Atomic Energy, 1989-03, Vol.66 (3), p.214-217 [Periódico revisado por pares]

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3
Effect of neutron irradiation and corrosive medium on the crack resistance of the water-moderated power reactor vessels
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Effect of neutron irradiation and corrosive medium on the crack resistance of the water-moderated power reactor vessels

Vainer, L. A.

Soviet Atomic Energy, 1987-05, Vol.62 (5), p.404-407 [Periódico revisado por pares]

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4
Evaluation of the changes occurring in the crack resistance of casing materials of water-cooled power reactors using the results of impact tests
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Evaluation of the changes occurring in the crack resistance of casing materials of water-cooled power reactors using the results of impact tests

Vainer, L. A. ; Deich, A. Sh

Soviet Atomic Energy, 1990-11, Vol.69 (5), p.927-930 [Periódico revisado por pares]

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5
Stress corrosion resistance of a steel used for the vessels (frames) of water-moderated power reactors (WMPR)
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Stress corrosion resistance of a steel used for the vessels (frames) of water-moderated power reactors (WMPR)

Vainer, L. A. ; Lanets, V. P.

Soviet Atomic Energy, 1987-11, Vol.63 (5), p.859-861 [Periódico revisado por pares]

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6
Apparatus for the investigation of cracking of materials in thin-walled elements in the core of a water-moderated, water-cooled power reactor (VV R)
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Apparatus for the investigation of cracking of materials in thin-walled elements in the core of a water-moderated, water-cooled power reactor (VV R)

Vainer, L. A. ; Kozhevnikov, O. A. ; Shoka, I. V.

Soviet Atomic Energy, 1989-04, Vol.66 (4), p.306-309 [Periódico revisado por pares]

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7
The possibility of modelling radiation embrittlement of the steels used for the vessels of water-moderated power reactors
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The possibility of modelling radiation embrittlement of the steels used for the vessels of water-moderated power reactors

Vainer, L. A. ; Zvezdin, Yu. I.

Soviet Atomic Energy, 1989-02, Vol.66 (2), p.96-100 [Periódico revisado por pares]

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8
Effect of neutron irradiation and hydrogenation on the fracture resistance of an alpha-titanium alloy
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Effect of neutron irradiation and hydrogenation on the fracture resistance of an alpha-titanium alloy

Vainer, L. A. ; Kozhevnikov, O. A. ; Pelyukhova, I. N. ; Takovleva, T. A.

Soviet Atomic Energy, 1990-08, Vol.69 (2), p.694-696 [Periódico revisado por pares]

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9
Effect of neutron irradiation on the mechanical properties of an alpha-titanium alloy
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Effect of neutron irradiation on the mechanical properties of an alpha-titanium alloy

Vainer, L. A. ; Deich, A. Sh ; Kozhevnikov, O. A. ; Pelyukhova, I. N. ; Yakovleva, T. A.

Soviet Atomic Energy, 1990-12, Vol.69 (6), p.1046-1051 [Periódico revisado por pares]

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10
Effects of preliminary few-cycle loading on the radiation embrittlement of 15Kh2MFA steel
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Effects of preliminary few-cycle loading on the radiation embrittlement of 15Kh2MFA steel

Vainer, L. A. ; Timofeev, B. T.

Soviet Atomic Energy, 1983-03, Vol.54 (3), p.215-216 [Periódico revisado por pares]

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