| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of warm prestressing effect on fracture toughness of reactor pressure vessel steels
|
Beleznai, R.
|
|
2010
|
42 |
1 |
p. 120-123
|
artikel
|
| 2 |
A new approach to description of in-service embrittlement of WWER-1000 reactor pressure vessel materials
|
Margolin, B. Z.
|
|
2010
|
42 |
1 |
p. 2-16
|
artikel
|
| 3 |
Application of the system of automated monitoring of the residual service life for the solution of the problems of operation of nuclear power plants with water-cooled water-moderated reactors
|
Berkovich, V. Ya.
|
|
2010
|
42 |
1 |
p. 44-50
|
artikel
|
| 4 |
Approaches of fracture mechanics in the analysis of admissible defects in the form of notches
|
Matvienko, Yu. G.
|
|
2010
|
42 |
1 |
p. 58-63
|
artikel
|
| 5 |
Assessment of brittle strength of nuclear reactor pressure vessel steel upon warm prestressing
|
Yasnii, P. V.
|
|
2010
|
42 |
1 |
p. 32-37
|
artikel
|
| 6 |
A study of fracture kinetics in welded components of nuclear power plant equipment in the presence of surface semi-elliptical variously oriented cracks
|
Makhutov, N. A.
|
|
2010
|
42 |
1 |
p. 25-31
|
artikel
|
| 7 |
Ductility and cold resistance of structural steels
|
Kotrechko, S. A.
|
|
2010
|
42 |
1 |
p. 84-89
|
artikel
|
| 8 |
Electrochemical behavior of 15Kh2NMFA steel in borate-buffered reactor water at temperatures of 22–300°C under equilibrium pressures
|
Pokhmurs’kyi, V. I.
|
|
2010
|
42 |
1 |
p. 64-69
|
artikel
|
| 9 |
Evolution of the structure of the WWER-1000 reactor vessel from the prototype model to WWER-1200
|
Bakaldin, V. I.
|
|
2010
|
42 |
1 |
p. 38-43
|
artikel
|
| 10 |
Experimental study of variation of 08Kh18N12T steel properties in the npp main circulating pipeline during its operation
|
Sosnovskii, L. A.
|
|
2010
|
42 |
1 |
p. 95-100
|
artikel
|
| 11 |
Fatigue damage and failure of steam turbine rotors by torsional vibrations
|
Bovsunovskii, A. P.
|
|
2010
|
42 |
1 |
p. 108-113
|
artikel
|
| 12 |
Information technologies for vibration strength analysis of the Rovenskaya nuclear power plant main steam line
|
Shtefan, E. V.
|
|
2010
|
42 |
1 |
p. 124-128
|
artikel
|
| 13 |
Lifetime analysis of wwer reactor pressure vessel internals concerning material degradation
|
Dudra, Ju.
|
|
2010
|
42 |
1 |
p. 51-57
|
artikel
|
| 14 |
Structural integrity and life of npp equipment (Resource-2009)
|
|
|
2010
|
42 |
1 |
p. 1
|
artikel
|
| 15 |
Study of irradiation effects at the research reactor
|
Gillemot, F.
|
|
2010
|
42 |
1 |
p. 78-83
|
artikel
|
| 16 |
Study of the beltline weld and base metal of WWER-440 first generation reactor pressure vessel
|
Schuhknecht, J.
|
|
2010
|
42 |
1 |
p. 70-77
|
artikel
|
| 17 |
The influence of thermomechanical loading history on the stress level in WWER NPP reactor pressure vessels under thermal shock
|
Kharchenko, V. V.
|
|
2010
|
42 |
1 |
p. 17-24
|
artikel
|
| 18 |
The kinetics of damage accumulation in heat-resistant steels under different loading conditions
|
Giginyak, F. F.
|
|
2010
|
42 |
1 |
p. 90-94
|
artikel
|
| 19 |
Thermostressed state and crack growth resistance of rotors of the NPP turbine K-1000-60/1500
|
Shul’zhenko, M. G.
|
|
2010
|
42 |
1 |
p. 114-119
|
artikel
|
| 20 |
Ultimate exhaustion of local plasticity as a criterion of fatigue crack initiation
|
Tsybanev, G. V.
|
|
2010
|
42 |
1 |
p. 101-107
|
artikel
|
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