| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of the Polonium Hazard in Nuclear Power Systems with LeadBismuth Coolant
|
D. V. Pankratov
|
|
2004
|
97 |
2 |
p. 559-563
5 p.
|
artikel
|
| 2 |
Analysis of the Polonium Hazard in Nuclear Power Systems with Lead–Bismuth Coolant
|
Pankratov, D. V.
|
|
2004
|
97 |
2 |
p. 559-563
|
artikel
|
| 3 |
Corrosion-Mechanical Strength of Structural Materials in Contact with Liquid Lead
|
A. D. Kashtanov
|
|
2004
|
97 |
2 |
p. 538-542
5 p.
|
artikel
|
| 4 |
Corrosion-Mechanical Strength of Structural Materials in Contact with Liquid Lead
|
Kashtanov, A. D.
|
|
2004
|
97 |
2 |
p. 538-542
|
artikel
|
| 5 |
Determination of the Fuel-Assembly Burnup in a Research Reactor by Repeated Short-Time Irradiation Followed by γ Spectrometric Measurements
|
A. V. Bushuev
|
|
2004
|
97 |
2 |
p. 571-576
6 p.
|
artikel
|
| 6 |
Determination of the Fuel-Assembly Burnup in a Research Reactor by Repeated Short-Time Irradiation Followed by γ Spectrometric Measurements
|
Bushuev, A. V.
|
|
2004
|
97 |
2 |
p. 571-576
|
artikel
|
| 7 |
Effect of Purging on the Tritium Concentration in Heavy-Water Nuclear-Reactor Coolant
|
É. B. Strakhov
|
|
2004
|
97 |
2 |
p. 590-592
3 p.
|
artikel
|
| 8 |
Effect of Purging on the Tritium Concentration in Heavy-Water Nuclear-Reactor Coolant
|
Strakhov, É. B.
|
|
2004
|
97 |
2 |
p. 590-592
|
artikel
|
| 9 |
Electronuclear Systems a New Generation of Nuclear Power Systems
|
O. V. Shvedov
|
|
2004
|
97 |
2 |
p. 577-582
6 p.
|
artikel
|
| 10 |
Electronuclear Systems – a New Generation of Nuclear Power Systems
|
Shvedov, O. V.
|
|
2004
|
97 |
2 |
p. 577-582
|
artikel
|
| 11 |
Heavy Liquid Metal Coolant LeadBismuth and Lead Technology
|
A. V. Zrodnikov
|
|
2004
|
97 |
2 |
p. 534-537
4 p.
|
artikel
|
| 12 |
Heavy Liquid Metal Coolant – Lead–Bismuth and Lead – Technology
|
Zrodnikov, A. V.
|
|
2004
|
97 |
2 |
p. 534-537
|
artikel
|
| 13 |
LeadBismuth and Lead Coolant in a New Technology for Reprocessing Liquids and Gases
|
P. N. Martynov
|
|
2004
|
97 |
2 |
p. 543-550
8 p.
|
artikel
|
| 14 |
Lead–Bismuth and Lead Coolant in a New Technology for Reprocessing Liquids and Gases
|
Martynov, P. N.
|
|
2004
|
97 |
2 |
p. 543-550
|
artikel
|
| 15 |
Measurement of the Characteristics of the Ventilation Pipe of the Filtration System for the Steam-Gas Medium of a Nuclear Power Plant
|
S. G. Kalyakin
|
|
2004
|
97 |
2 |
p. 583-586
4 p.
|
artikel
|
| 16 |
Measurement of the Characteristics of the Ventilation Pipe of the Filtration System for the Steam-Gas Medium of a Nuclear Power Plant
|
Kalyakin, S. G.
|
|
2004
|
97 |
2 |
p. 583-586
|
artikel
|
| 17 |
Method for Determining the α-Radiometry Coefficients of Thick-Layer Preparations
|
O. N. Prokof'ev
|
|
2004
|
97 |
2 |
p. 587-589
3 p.
|
artikel
|
| 18 |
Method for Determining the α-Radiometry Coefficients of Thick-Layer Preparations
|
Prokof'ev, O. N.
|
|
2004
|
97 |
2 |
p. 587-589
|
artikel
|
| 19 |
Optimization of Conceptual Solutions for the RBETs-M LeadBismuth Fast Reactor
|
P. N. Alekseev
|
|
2004
|
97 |
2 |
p. 551-558
8 p.
|
artikel
|
| 20 |
Optimization of Conceptual Solutions for the RBETs-M Lead–Bismuth Fast Reactor
|
Alekseev, P. N.
|
|
2004
|
97 |
2 |
p. 551-558
|
artikel
|
| 21 |
Role of Nuclear Power in Large-Scale Power Production in Russia in the 21st Century
|
E. O. Adamov
|
|
2004
|
97 |
2 |
p. 521-527
7 p.
|
artikel
|
| 22 |
Role of Nuclear Power in Large-Scale Power Production in Russia in the 21st Century
|
Adamov, E. O.
|
|
2004
|
97 |
2 |
p. 521-527
|
artikel
|
| 23 |
SVBR-75/100 Multipurpose Modular Low-Power Fast Reactor with LeadBismuth Coolant
|
A. V. Zrodnikov
|
|
2004
|
97 |
2 |
p. 528-533
6 p.
|
artikel
|
| 24 |
SVBR-75/100 Multipurpose Modular Low-Power Fast Reactor with Lead–Bismuth Coolant
|
Zrodnikov, A. V.
|
|
2004
|
97 |
2 |
p. 528-533
|
artikel
|
| 25 |
Tests of Models of BREST-OD-300 Reactor Fuel Elements in an Autonomous Lead-Cooled Channel of a BOR-60 Reactor
|
A. G. Kordyukov
|
|
2004
|
97 |
2 |
p. 564-570
7 p.
|
artikel
|
| 26 |
Tests of Models of BREST-OD-300 Reactor Fuel Elements in an Autonomous Lead-Cooled Channel of a BOR-60 Reactor
|
Kordyukov, A. G.
|
|
2004
|
97 |
2 |
p. 564-570
|
artikel
|
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