Hydrodynamics of coolant flow in the circulational loop of atomic power plants with an RBMK-1000 reactor

1991 ◽  
Vol 71 (4) ◽  
pp. 795-800
Author(s):  
I. M. Arshavskii ◽  
A. E. Kroshilin
Keyword(s):  
Power Plants ◽  
Coolant Flow ◽  
Hydrodynamics Of Coolant ◽  
Atomic Power Plants

All-union Conference on the Preparation of Operating Personnel for Atomic Power Plants

1977 ◽  
Vol 42 (6) ◽  
pp. 587-588
Author(s):  
L. M. Voronin ◽  
G. N. Ushakov ◽  
V. M. Gordina
Keyword(s):  
Power Plants ◽  
Operating Personnel ◽  
Union Conference ◽  
Atomic Power Plants

scholarly journals Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors

2021 ◽  
Vol 7 (4) ◽  
pp. 311-318
Author(s):  
Artavazd M. Sujyan ◽  
Viktor I. Deev ◽  
Vladimir S. Kharitonov
Keyword(s):  
Supercritical Water ◽  
Nuclear Power ◽  
Power Plants ◽  
Negative Impact ◽  
Reactor Core ◽  
Resistance Coefficient ◽  
Coolant Flow ◽  
Water Reactor ◽  
Hydraulic Stability ◽  
Supercritical Water Reactor

The paper presents a review of modern studies on the potential types of coolant flow instabilities in the supercritical water reactor core. These instabilities have a negative impact on the operational safety of nuclear power plants. Despite the impressive number of computational works devoted to this topic, there still remain unresolved problems. The main disadvantages of the models are associated with the use of one simulated channel instead of a system of two or more parallel channels, the lack consideration for neutronic feedbacks, and the problem of choosing the design ratios for the heat transfer coefficient and hydraulic resistance coefficient under conditions of supercritical water flow. For this reason, it was decided to conduct an analysis that will make it possible to highlight the indicated problems and, on their basis, to formulate general requirements for a model of a nuclear reactor with a light-water supercritical pressure coolant. Consideration is also given to the features of the coolant flow stability in the supercritical water reactor core. In conclusion, the authors note the importance of further computational work using complex models of neutronic thermal-hydraulic stability built on the basis of modern achievements in the field of neutron physics and thermal physics.

Radiation safety of atomic power plants in the USSR

1983 ◽  
Vol 54 (4) ◽  
pp. 290-301
Author(s):  
E. I. Vorob'ev ◽  
L. A. Il'in ◽  
V. D. Turovskii ◽  
L. A. Buldakov ◽  
N. G. Gusev ◽  
...  
Keyword(s):  
Power Plants ◽  
Radiation Safety ◽  
Atomic Power Plants

Soviet-French Seminar on Safety of Atomic Power Plants with Water-Moderated-Water-Cooled Reactors

1979 ◽  
Vol 46 (5) ◽  
pp. 424-426
Author(s):  
A. N. Isaev
Keyword(s):  
Power Plants ◽  
Atomic Power Plants

Calculation of reactor water flow rate for purification of coolant in boiling-water single-loop atomic power plants

1980 ◽  
Vol 48 (1) ◽  
pp. 41-42
Author(s):  
V. V. Gerasimov ◽  
O. I. Martynova ◽  
O. T. Konovalova ◽  
T. I. Kosheleva
Keyword(s):  
Water Flow ◽  
Flow Rate ◽  
Power Plants ◽  
Water Flow Rate ◽  
Boiling Water ◽  
Single Loop ◽  
Reactor Water ◽  
Atomic Power Plants

Mathematical model for determining unit powers of atomic power plants and various reactor assemblies

1975 ◽  
Vol 38 (5) ◽  
pp. 369-373 ◽  
Author(s):  
V. M. Chakhovskii ◽  
V. V. Matskov
Keyword(s):  
Mathematical Model ◽  
Power Plants ◽  
Atomic Power Plants

Concerning automatic processing of information at atomic power plants

1972 ◽  
Vol 33 (4) ◽  
pp. 966-968
Author(s):  
V. S. Ermakov ◽  
V. S. Kakhanovich ◽  
R. A. Kal'ko ◽  
E. K. Zalivako
Keyword(s):  
Power Plants ◽  
Automatic Processing ◽  
Atomic Power Plants
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