| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A combined thermal and strength analysis of the behavior of a VVER-440 reactor’s vessel during an accident involving core melting
|
Rassokhin, N. G.
|
|
2006
|
53 |
9 |
p. 675-681
|
artikel
|
| 2 |
A comparison of procedures for estimating the impact of nondensable gases on steam condensation taking into account the interaction of power engineering processes in the primary circuit of a nuclear power installation
|
Stepanov, O. E.
|
|
|
53 |
9 |
p. 699-705
|
artikel
|
| 3 |
A comparison of procedures for estimating the impact of nondensable gases on steam condensation taking into account the interaction of power engineering processes in the primary circuit of a nuclear power installation
|
Stepanov, O. E.
|
|
2006
|
53 |
9 |
p. 699-705
|
artikel
|
| 4 |
A List of Journal Papers on Nuclear Power Engineering Published in 2005
|
|
|
2006
|
53 |
9 |
p. 755-759
|
artikel
|
| 5 |
Assessing the influence of uncertain factors in analyzing emergency processes at nuclear power stations equipped with VVER-1000 reactors
|
Vorob’ev, Yu. B.
|
|
2006
|
53 |
9 |
p. 688-693
|
artikel
|
| 6 |
A system for monitoring the reliability of pump equipment during the operation of nuclear power stations
|
Bakhmet’ev, A. M.
|
|
2006
|
53 |
9 |
p. 737-742
|
artikel
|
| 7 |
Development in a nuclear power station project of matters concerning the dismantling of equipment at the stage of power unit decommissioning
|
Bylkin, B. K.
|
|
2006
|
53 |
9 |
p. 743-748
|
artikel
|
| 8 |
Optimizing the process for chemically decontaminating the multiple forced circulation circuit of power units built around RBMK reactors
|
Krasnoperov, V. M.
|
|
2006
|
53 |
9 |
p. 729-732
|
artikel
|
| 9 |
Raising the operational reliability of the steam generator of a BN-600 power unit in starting regimes
|
Govorov, P. P.
|
|
|
53 |
9 |
p. 733-736
|
artikel
|
| 10 |
Raising the operational reliability of the steam generator of a BN-600 power unit in starting regimes
|
Govorov, P. P.
|
|
2006
|
53 |
9 |
p. 733-736
|
artikel
|
| 11 |
Results from comprehensive thermal and chemical tests of steam generator No. 2 in unit 1 at the Volgodonsk Nuclear Power Station
|
Gorburov, V. I.
|
|
2006
|
53 |
9 |
p. 682-687
|
artikel
|
| 12 |
Simulating spatial effects during condensation of steam in a model containment using the KUPOL-3D computer code
|
Vitushkina, N. M.
|
|
|
53 |
9 |
p. 749-754
|
artikel
|
| 13 |
Simulating spatial effects during condensation of steam in a model containment using the KUPOL-3D computer code
|
Vitushkina, N. M.
|
|
2006
|
53 |
9 |
p. 749-754
|
artikel
|
| 14 |
The application of computational fluid dynamics for determining the hydraulic characteristics of pipelines at nuclear power stations
|
Novosel’skii, O. Yu.
|
|
2006
|
53 |
9 |
p. 723-728
|
artikel
|
| 15 |
The application of the BAGIRA code for a computational analysis of accident conditions involving a small leak from the reactor coolant circuit on the PSB-VVER test facility
|
Kroshilin, A. E.
|
|
2006
|
53 |
9 |
p. 714-722
|
artikel
|
| 16 |
The Moscow Power Institute’s Chair of Nuclear Power Stations turns fifty
|
|
|
2006
|
53 |
9 |
p. 673-674
|
artikel
|
| 17 |
Thermohydraulic factors causing the growth of dynamic stresses and cracks in the heads of pressurized-vessel reactors
|
Proskuryakov, K. N.
|
|
|
53 |
9 |
p. 694-698
|
artikel
|
| 18 |
Thermohydraulic factors causing the growth of dynamic stresses and cracks in the heads of pressurized-vessel reactors
|
Proskuryakov, K. N.
|
|
2006
|
53 |
9 |
p. 694-698
|
artikel
|
| 19 |
The use of supercritical parameters of a coolant—A promising path to development of nuclear power plant water-cooled reactors in the 21st century
|
Gabaraev, B. A.
|
|
2006
|
53 |
9 |
p. 706-713
|
artikel
|
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