scholarly journals IMPROVING THE EFFICIENCY OF THE UNIT OF THE ZAPORIZHZHIA NPP WITH A WWER-1000 REACTOR

2020 ◽  
pp. 135-139
Author(s):  
A.A. Cheilytko ◽  
А.V. Karpenko ◽  
S.V. Ilin
Keyword(s):  
Water Temperature ◽  
Power Unit ◽  
Nuclear Power ◽  
Power Reactor ◽  
Cooling Water ◽  
Nuclear Power Reactor ◽  
Nuclear Power Unit ◽  
Turbine Installation ◽  
Physical Calculation

Improving the efficiency of the unit of the Zaporizhzhia NPP with a WWER-1000 reactor, by reducing the water temperature at the inlet to the condenser. The work describes the description of the NPP and the nuclear power reactor WWER-1000, by reducing the water temperature at the inlet to the condenser. Detailed neutron-physical calculation of the nuclear power unit with WWER-1000 reactor with a turbine installation K-1000-60/3000. The influence of the temperature of cooling water on the input to the capacitor and the load on the efficiency of the turbine installation and the flow of steam and heat to the turbine installation is established.

SANICRO 71

Alloy Digest ◽  
1965 ◽  
Vol 14 (12) ◽  
Keyword(s):  
Nuclear Power ◽  
Elevated Temperatures ◽  
Power Reactor ◽  
Base Alloy ◽  
Heat Treating ◽  
Good Resistance ◽  
Nuclear Power Reactor ◽  
Temperature Performance ◽  
Resistance To Stress ◽  
Nickel Base

Abstract Sanicro 71 is a nickel-base alloy having good resistance to stress-corrosion, oxidation and creep at elevated temperatures. It is recommended for nuclear power reactor heat exchanger tubes, aircraft turbojet engines and for equipment in the textile, plastic, and chemical industries. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties. It also includes information on high temperature performance and corrosion resistance as well as forming, heat treating, machining, joining, and surface treatment. Filing Code: Ni-108. Producer or source: Sandvik.

scholarly journals Operating characteristics and peak regulation capability of AP1000 nuclear power unit

2021 ◽  
Vol 714 (4) ◽  
pp. 042033
Author(s):  
Yongqiang Che ◽  
Yisen Chen ◽  
Fengcai Zheng ◽  
Junshan Guo ◽  
Panfeng Shang
Keyword(s):  
Power Unit ◽  
Nuclear Power ◽  
Operating Characteristics ◽  
Nuclear Power Unit

Visualization of Supercritical Carbondioxide Pseudo-Boiling Inside a Rectangular Channel

2001 ◽  
Author(s):  
K. Sakurai ◽  
H. S. Ko ◽  
K. Okamoto ◽  
H. Madarame
Keyword(s):  
Forced Convection ◽  
Supercritical Fluids ◽  
Nuclear Power ◽  
Power Reactor ◽  
Rectangular Channel ◽  
Visual Observation ◽  
Next Generation ◽  
Nuclear Power Reactor

Abstract The characteristics of the supercritical fluids should be precisely investigated for the next generation nuclear power reactor, i.e., Super-critical water Cooled Reactor (SCR). There are few experiments for visual observation especially in forced convection, because of the difficulty of the experiment.

On the Shape of Stress Corrosion Cracks in Water-Cooled Nuclear Power Reactor Piping

2013 ◽  
Vol 50 (30) ◽  
pp. 27-39 ◽  
Author(s):  
S.-K. Lee ◽  
D. Kramer ◽  
D. D. Macdonald
Keyword(s):  
Stress Corrosion ◽  
Nuclear Power ◽  
Power Reactor ◽  
Nuclear Power Reactor

Research on Negative Pressure Control Technology in NPP Reactor Building and its Application

2013 ◽  
Author(s):  
Jianghong Xie
Keyword(s):  
Power Unit ◽  
Negative Pressure ◽  
Nuclear Power ◽  
Pressure Control ◽  
Control Technology ◽  
Annular Space ◽  
Pressure System ◽  
Nuclear Power Unit ◽  
Reactor Building ◽  
Double Wall

The paper mainly elaborates the negative pressure control technology and commissioning approaches for double-wall containment of Russian WWER-1000 nuclear power units. It also carries out an analysis and research on the layered negative pressure technology in the containment. It mainly includes the following three parts: A Russian WWER-1000 nuclear power unit adopts the structure of double-wall containment for its Reactor building, with independent negative pressure systems for the containment and the annular space between the two walls. The paper mainly elaborates the control methods and limits requirements for the negative pressure in the containment and the annular space under the normal operation condition and in case of design basis accidents, with analysis and argumentation on the design function and operation requirements of the negative pressure system for the containment and the annular space. In the paper, the design philosophy of layered negative pressure and its feasibility study are analyzed from the aspects of radiated partition, air distribution of the negative pressure system and containment separator for layered negative pressure. The commissioning methods and technical requirements of negative pressure system in the Reactor building are described in the paper. Problems encountered during commissioning are also addressed and analyzed. Operations practices prove that the negative pressure control technology for double-wall containment of WWER-1000 nuclear power unit is advanced and reliable, which meets the requirements on nuclear air decontamination emission and radiation protection, and is worthy of study, research and reference.

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