A platform for research: civil engineering, architecture and urbanism
A platform for research: civil engineering, architecture and urbanism
Optimization of the water chemistry of the primary coolant at nuclear power plants with VVÉR
Abstract Results of the use of automatic hydrogen-content meter for controlling the parameter of “hydrogen” in the primary coolant circuit of the Kola nuclear power plant are presented. It is shown that the correlation between the “hydrogen” parameter in the coolant and the “hydrazine” parameter in the makeup water can be used for controlling the water chemistry of the primary coolant system, which should make it possible to optimize the water chemistry at different power levels
Optimization of the water chemistry of the primary coolant at nuclear power plants with VVÉR
Abstract Results of the use of automatic hydrogen-content meter for controlling the parameter of “hydrogen” in the primary coolant circuit of the Kola nuclear power plant are presented. It is shown that the correlation between the “hydrogen” parameter in the coolant and the “hydrazine” parameter in the makeup water can be used for controlling the water chemistry of the primary coolant system, which should make it possible to optimize the water chemistry at different power levels
Optimization of the water chemistry of the primary coolant at nuclear power plants with VVÉR
Barmin, L. F. (author) / Kruglova, T. K. (author) / Sinitsyn, V. P. (author)
Power Technology and Engineering ; 39 ; 44-46
2005-01-01
3 pages
Article (Journal)
Electronic Resource
English
water chemistry of the primary coolant circuit of NPP with VVÉR , parameter of coolant quality , automatic measurement of hydrogen , integral parameter Engineering , Energy Technology , Power Electronics, Electrical Machines and Networks , Renewable and Green Energy , Geoengineering, Foundations, Hydraulics
Optimization of the water chemistry of the primary coolant at nuclear power plants with VVÉR
| Online Contents | 2005
Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions
| DOAJ | 2017
Corrosion behaviour of reactor coolant system materials in nuclear power plants
| British Library Online Contents | 2002
Modeling of Coolant Flow Within the Spent Fuel Storage Pool of a VVER 440 Reactor
| DOAJ | 2017