| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Announcement
|
|
|
2010
|
108 |
4 |
p. 229
|
artikel
|
| 2 |
BN-800 design validation and construction status
|
Saraev, O. M.
|
|
2010
|
108 |
4 |
p. 248-253
|
artikel
|
| 3 |
Computational tracking of BN-600 operation
|
Belov, A. A.
|
|
2010
|
108 |
4 |
p. 321-324
|
artikel
|
| 4 |
Concept of an advanced power-generating unit with a BN-1200 sodium-cooled fast reactor
|
Rachkov, V. I.
|
|
2010
|
108 |
4 |
p. 254-259
|
artikel
|
| 5 |
Core and fuel cycle for an advanced sodium-cooled fast reactor
|
Poplavskii, V. M.
|
|
2010
|
108 |
4 |
p. 260-266
|
artikel
|
| 6 |
Development of structural steel for fuel elements and fuel assemblies of sodium-cooled fast reactors
|
Tselishchev, A. V.
|
|
2010
|
108 |
4 |
p. 274-280
|
artikel
|
| 7 |
Fast reactors in the energy security for the stable development of Russia
|
Zrodnikov, A. V.
|
|
2010
|
108 |
4 |
p. 230-233
|
artikel
|
| 8 |
Fuel for advanced sodium-cooled fast reactors: current status and plans
|
Poplavskii, V. M.
|
|
2010
|
108 |
4 |
p. 267-273
|
artikel
|
| 9 |
Improvement of the equipment in fast-neutron reactor facilities
|
Vasiliev, B. A.
|
|
2010
|
108 |
4 |
p. 303-309
|
artikel
|
| 10 |
Investigation of the influence of the sodium void effect of reactivity on the technical-economic performance and safety of an advanced fast reactor
|
Poplavskii, V. M.
|
|
2010
|
108 |
4 |
p. 289-295
|
artikel
|
| 11 |
Layout and structural solutions for the reloading system of an advanced fast reactor
|
Vasiliev, B. A.
|
|
2010
|
108 |
4 |
p. 310-314
|
artikel
|
| 12 |
Main stages of physical startup of BN-600 and comparison of the measured and nominal characteristics
|
Matveev, V. I.
|
|
2010
|
108 |
4 |
p. 315-320
|
artikel
|
| 13 |
Operating experience and prospects for future development of sodium-cooled fast reactors
|
Saraev, O. M.
|
|
2010
|
108 |
4 |
p. 240-247
|
artikel
|
| 14 |
Sodium as a coolant for fast reactors
|
Poplavskii, V. M.
|
|
2010
|
108 |
4 |
p. 281-288
|
artikel
|
| 15 |
Thermohydraulic studies of sodium-cooled reactor facilities
|
Poplavksii, V. M.
|
|
2010
|
108 |
4 |
p. 296-302
|
artikel
|
| 16 |
30 Years of experience in operating the BN-600 sodium-cooled fast reactor
|
Oshkanov, N. N.
|
|
2010
|
108 |
4 |
p. 234-239
|
artikel
|
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