Zobrazeno 1 - 10
of 26
pro vyhledávání: '"O. D. Loskutov"'
Autor:
P. V. Alekseev, A. A. Tutnov, A. S. Kiselev, E. S. Krut’ko, Aleksandr S. Kiselev, O. D. Loskutov
Publikováno v:
Atomic Energy. 115:176-181
A method of calculating the probability of a leak occurring in the main joint of the reactor and the probability of the head detaching from the vessel body of VVER-TOI as a result of stud-bolt failure and the computational results are presented. The
Publikováno v:
Atomic Energy. 114:21-27
The regulatory documentation establishes the maximum admissible fracture probability for the collector vessels of steam generators at 10–7 yr–1 per unit, which cannot be compensated by regular accident localization systems. In this connection, it
Autor:
A. A. Tutnov, O. D. Loskutov
Publikováno v:
Atomic Energy. 110:26-32
An approach to calculating the effective critical stress intensity coefficient for mainline cracks in the perforation zone of the first-loop collector of a VVER steam generator is examined. The energy criterion is chosen as the condition for crack st
Autor:
O. D. Loskutov, A. A. Tutnov
Publikováno v:
Atomic Energy. 102:426-429
A two-stage approach to evaluating the probability of leak appearing in the flange joint as a result of a failure of the securing studs is described. First the probability of only one stud failing is calculated. This probability depends on, specifica
Publikováno v:
Atomic Energy. 102:264-270
The results of calculations of the probability of a leak appearing in the tube band of steam generator in a VVER-440 reactor system during operation are presented. The MAVR-1.1 computer code is used to calculate the probability of the formation of a
Publikováno v:
Atomic Energy. 98:256-261
The results of a computational investigation of the possibility of and the safety conditions for switching from a 4- to an 8-yr time interval between technical inspections of the main circulation pipeline and the pressure compensator vessel in VVER-1
Publikováno v:
Atomic Energy. 87:583-590
Basic features are presented on the calculation method for determining the strength and failure probability of a VVER containment vessel. A description is given of the computational method, which handles five related tasks: simulating the coolant con
Publikováno v:
Atomic Energy. 79:415-419
Publikováno v:
Atomic Energy; Apr2005, Vol. 98 Issue 4, p256-261, 6p
Autor:
O. D. Loskutov
Publikováno v:
Soviet Mining Science. 9:564-567