| no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
| 1 |
Calculation of the Equivalent Dose Rate Distribution Using Data Obtained with a γ Locator
|
V. N. Potapov
|
|
2002
|
92 |
4 |
p. 357-366
10 p.
|
article
|
| 2 |
Calculation of the Equivalent Dose Rate Distribution Using Data Obtained with a γ Locator
|
Potapov, V. N.
|
|
2002
|
92 |
4 |
p. 357-366
|
article
|
| 3 |
Carbon-Fiber Adsorbent Materials for Removing Radioactive Iodine from Gases
|
N. I. Ampelogova
|
|
2002
|
92 |
4 |
p. 336-340
5 p.
|
article
|
| 4 |
Carbon-Fiber Adsorbent Materials for Removing Radioactive Iodine from Gases
|
Ampelogova, N. I.
|
|
2002
|
92 |
4 |
p. 336-340
|
article
|
| 5 |
Deformation and Operational Safety of Masonry in Commercial UraniumGraphite Reactors
|
A. I. Berezyuk
|
|
2002
|
92 |
4 |
p. 322-330
9 p.
|
article
|
| 6 |
Deformation and Operational Safety of Masonry in Commercial Uranium–Graphite Reactors
|
Berezyuk, A. I.
|
|
2002
|
92 |
4 |
p. 322-330
|
article
|
| 7 |
Determination of the Burnup of Spent Nuclear Fuel during Reloading
|
S. G. Oleinik
|
|
2002
|
92 |
4 |
p. 296-300
5 p.
|
article
|
| 8 |
Determination of the Burnup of Spent Nuclear Fuel during Reloading
|
Oleinik, S. G.
|
|
2002
|
92 |
4 |
p. 296-300
|
article
|
| 9 |
Determination of 234U Content in Uranium from Different Deposits
|
G. S. Solov'ev
|
|
2002
|
92 |
4 |
p. 317-321
5 p.
|
article
|
| 10 |
Determination of 234U Content in Uranium from Different Deposits
|
Solov'ev, G. S.
|
|
2002
|
92 |
4 |
p. 317-321
|
article
|
| 11 |
Discrepancies in Estimates of the Number of Secondary Fission Neutrons for 239Pu
|
L. P. Abagyan
|
|
2002
|
92 |
4 |
p. 287-295
9 p.
|
article
|
| 12 |
Discrepancies in Estimates of the Number of Secondary Fission Neutrons for 239Pu
|
Abagyan, L. P.
|
|
2002
|
92 |
4 |
p. 287-295
|
article
|
| 13 |
Efficient Distribution of Resources for Increasing the Shielding of Nuclear- and Radiation-Dangerous Objects
|
N. N. Radaev
|
|
2002
|
92 |
4 |
p. 310-316
7 p.
|
article
|
| 14 |
Efficient Distribution of Resources for Increasing the Shielding of Nuclear- and Radiation-Dangerous Objects
|
Radaev, N. N.
|
|
2002
|
92 |
4 |
p. 310-316
|
article
|
| 15 |
Impurity Composition and Content in Graphite from Commercial Reactors
|
A. V. Bushuev
|
|
2002
|
92 |
4 |
p. 331-335
5 p.
|
article
|
| 16 |
Impurity Composition and Content in Graphite from Commercial Reactors
|
Bushuev, A. V.
|
|
2002
|
92 |
4 |
p. 331-335
|
article
|
| 17 |
Management of the Service Life of a Nuclear Power Plant
|
S. E. Bugaenko
|
|
2002
|
92 |
4 |
p. 279-286
8 p.
|
article
|
| 18 |
Management of the Service Life of a Nuclear Power Plant
|
Bugaenko, S. E.
|
|
2002
|
92 |
4 |
p. 279-286
|
article
|
| 19 |
Radiation Equivalence and Natural Similitude in Handling Radioactive Wastes
|
A. V. Lopatkin
|
|
2002
|
92 |
4 |
p. 341-348
8 p.
|
article
|
| 20 |
Radiation Equivalence and Natural Similitude in Handling Radioactive Wastes
|
Lopatkin, A. V.
|
|
2002
|
92 |
4 |
p. 341-348
|
article
|
| 21 |
RTOP-Code Simulation of the Radial Distribution of Heat Release and Plutonium Isotope Accumulation in High Burnup Oxide Fuel
|
S. Yu. Kurchatov
|
|
2002
|
92 |
4 |
p. 349-356
8 p.
|
article
|
| 22 |
RTOP-Code Simulation of the Radial Distribution of Heat Release and Plutonium Isotope Accumulation in High Burnup Oxide Fuel
|
Kurchatov, S. Yu.
|
|
2002
|
92 |
4 |
p. 349-356
|
article
|
| 23 |
Temperature Standard for VVÉR-440
|
S. Shtants
|
|
2002
|
92 |
4 |
p. 301-305
5 p.
|
article
|
| 24 |
Temperature Standard for VVÉR-440
|
Shtants, S.
|
|
2002
|
92 |
4 |
p. 301-305
|
article
|
| 25 |
VVÉR-Based Power-Generating Units with Transcritical Coolant Parameters
|
V. V. Dolgov
|
|
2002
|
92 |
4 |
p. 306-309
4 p.
|
article
|
| 26 |
VVÉR-Based Power-Generating Units with Transcritical Coolant Parameters
|
Dolgov, V. V.
|
|
2002
|
92 |
4 |
p. 306-309
|
article
|
Journal description