| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accounting and monitoring of materials in the nuclear fuel cycle
|
Rumyantsev, A. N.
|
|
2006
|
101 |
3 |
p. 658-662
|
artikel
|
| 2 |
Analysis of the shutdown of a fast uranium-plutonium reactor
|
Gol’din, V. Ya.
|
|
2006
|
101 |
3 |
p. 684-686
|
artikel
|
| 3 |
Assessment of the quality and activity of the radionuclides in the fuel cycles of a three-component structure of nuclear power
|
Aseev, A. G.
|
|
2006
|
101 |
3 |
p. 663-668
|
artikel
|
| 4 |
Dependence of the characteristics of a nuclear reactor on the particle size of a nanodispersed moderator
|
Artem’ev, V. A.
|
|
2006
|
101 |
3 |
p. 675-679
|
artikel
|
| 5 |
Estimation of the effect of neutron spectrum regulation on VVÉR-1000 fuel burnup
|
Chibinyaev, A. V.
|
|
2006
|
101 |
3 |
p. 680-683
|
artikel
|
| 6 |
Hydrodynamic characteristics of an experimental model of the target in the MK-1 liquid-metal target system
|
Boronin, A. A.
|
|
2006
|
101 |
3 |
p. 636-643
|
artikel
|
| 7 |
Improving the performance of steel-zirconium adapters in RBMK process channels
|
Plyshevskii, M. I.
|
|
2006
|
101 |
3 |
p. 693-695
|
artikel
|
| 8 |
Optimization of the characteristics of the heat-insulating layer of quickly removable general-purpose insulation for nuclear power plants with VVÉR reactors
|
Skobelkina, T. N.
|
|
2006
|
101 |
3 |
p. 652-657
|
artikel
|
| 9 |
Possible future prospects for channel reactors
|
Ganev, I. Kh.
|
|
2006
|
101 |
3 |
p. 630-635
|
artikel
|
| 10 |
Quantile estimate of the uncertainties of probabilistic safety analysis for objects of the nuclear power industry
|
Rumyantsev, A. N.
|
|
2006
|
101 |
3 |
p. 617-624
|
artikel
|
| 11 |
Status and direction of development of ecological management in the nuclear power industry
|
Arkadov, G. V.
|
|
2006
|
101 |
3 |
p. 690-692
|
artikel
|
| 12 |
Steam-content and coolant-level emission sensors for a nuclear reactor
|
Postnikov, V. V.
|
|
2006
|
101 |
3 |
p. 644-651
|
artikel
|
| 13 |
The concept of risk and its use in safety investigations
|
Bakhmet’ev, A. M.
|
|
2006
|
101 |
3 |
p. 625-629
|
artikel
|
| 14 |
Thermohydraulic characteristics of an experimental fuel assembly for a water-graphite reactor
|
Dmitriev, A. M.
|
|
2006
|
101 |
3 |
p. 669-674
|
artikel
|
| 15 |
Water-free technology for nitride fuel regeneration using recrystallization processes
|
Ustinov, O. A.
|
|
2006
|
101 |
3 |
p. 687-689
|
artikel
|
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