Digitale Bibliotheek
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                             44 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Application of zonality conceptual model of chronic effects of ionizing radiation for studying the behavior of Sr-90 in terrestrial ecosystems Shoshina, R.R.
2015
4 p. 267-271
5 p.
artikel
2 Approach to radionuclide therapy dosimetry planning Lysak, Yu.V.
2016
4 p. 307-311
5 p.
artikel
3 Automated ultrasonic system residual stresses in the welded joints of the circulation pipe NPP Minin, S.I.
2016
4 p. 236-239
4 p.
artikel
4 Combined numerical and experimental study of temperature pulsations in the fragment of header unit of heat exchanger of nuclear power unit clean-up and cooldown system Dmitriev, S.M.
2015
4 p. 237-242
6 p.
artikel
5 Degenerate optimization problems and competitiveness of NPPs Klimenko, A.V.
2016
4 p. 299-306
8 p.
artikel
6 Design chemistry implementation experience during the power unit start-up and commissioning Vitkovsky, S.L.
2017
4 p. 313-318
artikel
7 Design features of water-cooled research reactors Chusov, I.A.
2016
4 p. 287-293
7 p.
artikel
8 Dynamic stability of the VVER-1200 power unit Gusev, I.N.
2017
4 p. 270-277
artikel
9 Estimation of the metrological performance instability for measuring channels of research reactors Berezhnoy, D.A.
2015
4 p. 253-258
6 p.
artikel
10 Experience of commissioning of the V-392M reactor plant passive heat removal system Galiev, K.F.
2017
4 p. 291-296
artikel
11 Experience of commissioning the AES-2006 (V-392M) steam generator blowdown system Yaurov, S.V.
2017
4 p. 323-330
artikel
12 Experimental studies into the thermal-hydraulic performance of the VK-300 reactor based on a draft tube model Serdun, N.P.
2015
4 p. 288-295
8 p.
artikel
13 Experimental study of local coolant hydrodynamics in TVS-Kvadrat PWR reactor fuel assembly using mixing spacer grids with different types of deflectors Dmitriev, S.M.
2015
4 p. 296-303
8 p.
artikel
14 Flexible distributed control and protection system for industrial objects – Consumers of electric power Alontseva, E.N.
2015
4 p. 233-236
4 p.
artikel
15 Improvement the value of sodium void reactivity effect of the fast neutron reactor by the instrumentality of the Monte Carlo code Maslov, P.A.
2015
4 p. 304-307
4 p.
artikel
16 In-service change in the flexural rigidity of the VVER-1000 fuel assemblies Pavlov, S.V.
2016
4 p. 251-255
5 p.
artikel
17 Internal corrosion of EK164 and CHS68 fuel pin cladding steels of uranium dioxide fast power reactor Kinev, E.A.
2015
4 p. 283-287
5 p.
artikel
18 Investigation of dependence of BN-600 reactor sector fuel cladding leak detection system responses on the operation parameters Albutova, O.I.
2015
4 p. 248-252
5 p.
artikel
19 Investigation of ecological constraints influence on competitiveness of nuclear power plants Marchenko, O.V.
2015
4 p. 277-282
6 p.
artikel
20 Investigations for the substantiation of high-temperature nuclear power generation technology using fast sodium-cooled reactor for hydrogen production and other innovative applications (Part 1) Kalyakin, S.G.
2016
4 p. 282-286
5 p.
artikel
21 Key results of commissioning activities for the emergency and scheduled cooldown system of the AES-2006 unit with the V-392M reactor plant Statsura, D.B.
2017
4 p. 278-284
artikel
22 Metascientific foundations of understanding of status of technology Kanke, V.A.
2017
4 p. 243-248
artikel
23 Methods for using computer training facilities in studies of special disciplines Tashlykov, O.L.
2016
4 p. 262-266
5 p.
artikel
24 Modeling of direct conversion of the uranium fission product kinetic energy to laser radiation energy in an argon–xenon dusty plasma with uranium nanoparticles Slyunyaev, M.N.
2015
4 p. 272-276
5 p.
artikel
25 Modeling of natural circulation for the inherent safety analysis of sodium cooled fast reactors Bochkarev, A.S.
2016
4 p. 294-298
5 p.
artikel
26 Multifunctional backup electricity supply for NPP auxiliary needs based on combined-cycle power plant with hydrogen overheating Yurin, V.E.
2016
4 p. 231-235
5 p.
artikel
27 New generation first-of-the kind unit – VVER-1200 design features Asmolov, V.G.
2017
4 p. 260-269
artikel
28 New generation refueling machine information and control system Korobkin, V.V.
2017
4 p. 302-306
artikel
29 On feasibility of optimizing the neutronic parameters of a laser system pumped by a pulsed reactor Gulevich, A.V.
2016
4 p. 277-281
5 p.
artikel
30 Physical characteristics of large fast-neutron sodium-cooled reactors with advanced nitride and metallic fuels Matveev, V.I.
2015
4 p. 308-312
5 p.
artikel
31 Plutonium in locations of local sources and its involvement in global circulation Bulgakov, V.G.
2017
4 p. 285-290
artikel
32 Prediction of electric power consumption by nuclear power plants for covering plant needs using data mining methods Kleshchyova, M.A.
2015
4 p. 243-247
5 p.
artikel
33 Protactinium-231 – New burnable neutron absorber Kulikov, G.G.
2017
4 p. 255-259
artikel
34 Reactimeter dispersion equation Yuferov, A.G.
2016
4 p. 245-250
6 p.
artikel
35 Results of preoperational inspection at unit 1 of Novovoronezh NPP II Urazov, O.V.
2017
4 p. 319-322
artikel
36 Sorption of cations of heavy metals and radionuclides from the aqueous media by new synthetic zeolite-like sorbent Shilina, A.S.
2017
4 p. 249-254
artikel
37 Specific features of initial fuel load of the innovative power unit under AES-2006 project Prytkov, A.N.
2017
4 p. 307-312
artikel
38 Standalone hydrogen generator based on chemical decomposition of water by aluminum Milinchuk, V.K.
2015
4 p. 259-266
8 p.
artikel
39 Statistical analysis of the nuclear power plant equipment failure data in non-homogeneous flow of events Antonov, A.V.
2016
4 p. 240-244
5 p.
artikel
40 Study of reactor plant disturbed cooling condition modes caused by the VVER reactor secondary circuit Belozerov, V.I.
2016
4 p. 256-261
6 p.
artikel
41 Study of VVER-1000 OECD LEU and MOX Computational Benchmark with VISWAM Code System Khan, Suhail Ahmad
2016
4 p. 312-334
23 p.
artikel
42 Testing of the ICMS input data diagnostic system at unit 1 of Novovoronezh NPP II Semenikhin, A.V.
2017
4 p. 297-301
artikel
43 The metascientific foundations of nuclear knowledge management Kanke, V.A.
2016
4 p. 267-271
5 p.
artikel
44 Use of Johnson–Cook plasticity model for numerical simulations of the SNF shipping cask drop tests Sobolev, A.V.
2016
4 p. 272-276
5 p.
artikel
                             44 gevonden resultaten
 
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