Zobrazeno 1 - 10
of 11
pro vyhledávání: '"S. B. Ryzhov"'
Publikováno v:
Thermal Engineering. 58:179-183
Main results of the 40-year experience gained from operation of horizontal steam generators in VVER-type reactor installations used in Russia and many foreign countries are described. Existing unresolved problems are pointed out.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::16f55f21d67252c5d2a9eb11c4021274
https://doi.org/10.1134/s004060151103013x
https://doi.org/10.1134/s004060151103013x
Autor:
A. V. Shutikov, Yu. A. Ryzhkov, V. Ya. Berkovich, R. Z. Aminov, V. I. Ignatov, V. A. Khrustalev, Yu. M. Semchenkov, S. B. Ryzhov, Yu. V. Kop’ev
Publikováno v:
Thermal Engineering. 56:963-966
Safe operation of the Balakovo nuclear power station’s Unit 2 built around a VVER-1000 reactor at a thermal power output of 3120 MW with meeting of the safety criteria and compliance with the requirements of existing regulatory documents is substan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::68ccfbd59ca5e5604d02cdc866c4502c
https://doi.org/10.1134/s0040601509110111
https://doi.org/10.1134/s0040601509110111
Autor:
V. A. Khrustalev, Yu. M. Semchenkov, S. B. Ryzhov, V. Ya. Berkovich, Yu. A. Ryzhkov, Yu. V. Kop’ev, A. V. Shutikov, R. Z. Aminov, V. I. Ignatov
Publikováno v:
Atomic Energy. 107:9-17
The margin to critical level of heat exchange of thermal power and coolant temperature at the core exit as well as the nonuniformities of the energy release under the operating conditions of a nuclear power plant with VVER-1000 above nominal power is
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::38e5331f02aa8595b747ea866c704190
https://doi.org/10.1007/s10512-009-9189-z
https://doi.org/10.1007/s10512-009-9189-z
Publikováno v:
Thermal Engineering. 54:343-347
The problems of development of the Russian nuclear power industry on the basis of advancement of VVER-type pressurized light-water reactors for power engineering are discussed. Characteristics of the VVER-1200 reactor installation for the NPS-2006 pr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ddc29ce66a2adda2c724954d843fae63
https://doi.org/10.1134/s0040601507050023
https://doi.org/10.1134/s0040601507050023
Publikováno v:
Atomic Energy. 100:181-191
A conceptual approach is proposed to determining the minimum achievable number of control organs in the safety and control system and the minimum effectiveness of emergency shielding of VVER reactors. This approach includes a new probabilistic method
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8831591e69bc4659b22c90dbf08009f8
https://doi.org/10.1007/s10512-006-0071-y
https://doi.org/10.1007/s10512-006-0071-y
Publikováno v:
Thermal Engineering. 53:1-9
Experience gained in the development of reactor installations (RIs) with VVER reactors and their operation as part of a nuclear power station is analyzed. It is shown that the newly designed projects of RIs that comply with modern requirements for sa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9381888b371a84c5d8e5273f4b6ff93c
https://doi.org/10.1134/s0040601506010010
https://doi.org/10.1134/s0040601506010010
Publikováno v:
Atomic Energy. 99:911-916
The problems arising in the sealing of detachable connections in VVER-1000 reactors are described. The objectives, problems, and methods for upgrading these units using the new gasket material graphleks are presented. The results of the adoption and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::959d5c5f06e848a74707024e0ddbade6
https://doi.org/10.1007/s10512-006-0039-y
https://doi.org/10.1007/s10512-006-0039-y
Publikováno v:
Atomic Energy. 99:864-868
Many technical problems must be solved in order to adopt advanced fuel cycles at nuclear power plants with VVER-1000 reactors. The TVS-2 structure was initially developed in the process of solving these problems; it gave high technical performance an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::87f0c731cc887c05066ea6693212c0c9
https://doi.org/10.1007/s10512-006-0032-5
https://doi.org/10.1007/s10512-006-0032-5
Autor:
N. E. Kukharkin, V. S. Konstantinov, V. P. Deniskin, I. I. Fedik, Y.-U. G. Dragunov, V. I. Nalivaev, I. I. Konovalov, V. I. Subbotin, S. S. Gavrilin, N. N. Ponomarev-Stepnoi, S. B. Ryzhov, V. P. Spasskov
Publikováno v:
Atomic Energy. 96:250-259
The results of development work on a new generation of fuel elements based on microfuel for VVER reactors using the basic data from post-reactor investigations and bench tests in experiments simulating LOCA for existing fuel elements with ceramic fue
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2cccce83c1e1981834d9a85121929738
https://doi.org/10.1023/b:aten.0000035995.94259.dd
https://doi.org/10.1023/b:aten.0000035995.94259.dd
Publikováno v:
Kerntechnik. 67:190-195
The present paper deals with the consideration of cases of degradation of the basic equipment (reactor pressure vessels and steam generators') of WWER-440 and WWER-1000 reactor plants, the degradation mitigation measures on the equipment of operating
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2ed68d0a93347951188c0b23b2b6c032
https://doi.org/10.1515/kern-2002-0079
https://doi.org/10.1515/kern-2002-0079