scholarly journals Development of Heavy-Water Power Reactors in Canada

1960 ◽  
Vol 2 (3) ◽  
pp. 153-157
Author(s):  
F. W. Gilbert
Keyword(s):  
Heavy Water ◽  
Water Power

Density effect of reactivity in a heavy-water power reactor operating in the 233U self-fueling regime

Atomic Energy ◽  
2008 ◽  
Vol 105 (5) ◽  
pp. 316-323
Author(s):  
B. R. Bergelson ◽  
A. S. Gerasimov ◽  
G. V. Tikhomirov
Keyword(s):  
Heavy Water ◽  
Power Reactor ◽  
Density Effect ◽  
Water Power ◽  
Reactor Operating

Recycling plutonium in heavy-water power reactors

1967 ◽  
Vol 21 (1) ◽  
pp. 81-85
Author(s):  
P.I. Khristenko
Keyword(s):  
Heavy Water ◽  
Water Power

A gas-cooled heavy water power reactor

Atomic Energy ◽  
1956 ◽  
Vol 1 (1) ◽  
pp. 3-6 ◽  
Author(s):  
A. I. Alikhanov ◽  
V. V. Vladimirskii ◽  
P. A. Petrov ◽  
P. I. Khristenko
Keyword(s):  
Heavy Water ◽  
Power Reactor ◽  
Water Power

Plutonium recycle in heavy water-power reactors

1966 ◽  
Vol 20 (1) ◽  
pp. 32-35 ◽  
Author(s):  
P. I. Khristenko
Keyword(s):  
Heavy Water ◽  
Water Power

Self-fueling (233U) regime for a CANDU heavy-water power reactor

Atomic Energy ◽  
2004 ◽  
Vol 97 (4) ◽  
pp. 694-700 ◽  
Author(s):  
B. R. Bergel’son ◽  
A. S. Gerasimov ◽  
G. V. Tikhomirov ◽  
Li Tsinhun
Keyword(s):  
Heavy Water ◽  
Power Reactor ◽  
Water Power

A heavy-water power reactor with gas cooling

1956 ◽  
Vol 3 (1-2) ◽  
pp. 77-82
Author(s):  
A.I. Alikhanov ◽  
V.V. Vladimixsky ◽  
P.A. Petrov ◽  
P.I. Khristenko
Keyword(s):  
Heavy Water ◽  
Power Reactor ◽  
Water Power ◽  
Gas Cooling

scholarly journals Some questions on nuclear safety of heavy-water power reactor operating in self-sufficient thorium cycle

2008 ◽  
Vol 23 (2) ◽  
pp. 22-27
Author(s):  
Boris Bergelson ◽  
Alexander Gerasimov ◽  
Georgy Tikhomirov
Keyword(s):  
Heavy Water ◽  
Power Reactor ◽  
Water Channel ◽  
Nuclear Safety ◽  
Water Power ◽  
Fuel Assemblies ◽  
Different Types ◽  
Reactivity Increase ◽  
Reactor Operating ◽  
Thorium Cycle

In this paper the comparative calculations of the void coefficient have been made for different types of channel reactors for the coolant density interval 0.8-0.01 g/cm3. These results demonstrate the following. In heavy-water channel reactors, the replacement of D2O coolant by H2O, ensuring significant economic advantage, leads to the essential reducing of nuclear safety of an installation. The comparison of different reactors by the void coefficient demonstrates that at the dehydration of channels the reactivity increase is minimal for HWPR(Th), operating in the self-sufficient mode. The reduction of coolant density in channels in most cases is accompanied by the increase of power and temperatures of fuel assemblies. The calculations show that the reduction of reactivity due to Doppler effect can compensate the effect of dehydration of a channel. However, the result depends on the time dependency of heat-hydraulic processes, occurring in reactor channels in the specific accident. The result obtained in the paper confirms that nuclear safety of HWPR(Th) lies on the same level as nuclear safety of CANDU type reactors approved in practice.

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