Zobrazeno 1 - 9
of 9
pro vyhledávání: '"V. N. Shulimov"'
Autor:
L. V. Kireeva, A. L. Izhutov, V. N. Shulimov, A. V. Alekseev, A. V. Goryachev, I. V. Kiseleva, O. I. Dreganov
Publikováno v:
Atomic Energy. 123:159-166
The main results of tests performed on VVER-1000 fuel elements with high burnup of fuel in a channel of the MIR channel reactor for LOC accident conditions are examined. The experimental setup contains one fuel element, which is arranged along the ce
Autor:
V. V. Kalygin, A. L. Izhutov, A. V. Burukin, V. N. Shulimov, A. V. Alekseev, I. V. Kiseleva, V. A. Ovchinnikov
Publikováno v:
Atomic Energy. 113:179-185
Information is presented on programs and methods for performing in the MIR research reactor loop tests in order to study the serviceability of the fuel elements of the water-cooled reactors in transient and emergency regimes (abrupt increase and cycl
Publikováno v:
Atomic Energy. 104:365-371
The creation of conditions in the core of a MIR reactor that allow safe experiments modeling the parameters of VVER fuel elements with power ramping and cyclic power change as well as with an anticipated reactivity accident is examined. The construct
Publikováno v:
Atomic Energy. 103:851-857
The testing procedure and the results of tests performed on a 19-element fragment of a VVER-1000 fuel assembly in the channel of a MIR reactor under conditions of the second and third stage of a maximum anticipated accident are presented. The state a
Publikováno v:
Atomic Energy. 101:882-886
A procedure for performing dynamical experiments to study the behavior of VVER fuel under the conditions of an anticipated accident with the introduction of positive reactivity has been developed and adopted on the MIR reactor. A power pulse is produ
Publikováno v:
Soviet Atomic Energy. 58:246-249
This paper addresses the problems originating with a change of the requirements for the operating conditions of nuclear power stations with water-cooled-water-moderated reactors (VVER) in the power generation system. In order to solve the problem of
Publikováno v:
Soviet Atomic Energy. 57:454-458
Gas phase in experimental fuel elements with compact uranium dioxide, irradiated in the SM-2 reactor
Autor:
Yu. I. Pimonov, V. N. Shulimov, V. Sh. Sulaberidze, A. P. Kirillovich, V. N. Kupriyanov, A. S. Biryukov, Yu. G. Lavrinovich
Publikováno v:
Soviet Atomic Energy. 57:517-522
A complex procedure has been developed for the study of gas release from nuclear fuel, including reactor measurements and post-reactor determination of the amount and composition of the gas medium in the fuel elements at room and elevated temperature
Publikováno v:
Soviet Atomic Energy. 29:876-881