The Use of Abnormal Event Data in Nuclear Power Reactor System Analysis Using the Sequence Combining Method

1989 ◽  
Vol 84 (3) ◽  
pp. 296-304
Author(s):  
Henk W. Kalfsbeek
Keyword(s):  
Nuclear Power ◽  
System Analysis ◽  
Power Reactor ◽  
Reactor System ◽  
Event Data ◽  
Nuclear Power Reactor

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.

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.

Solution of the Lambda modes problem of a nuclear power reactor using an h–p finite element method

2014 ◽  
Vol 72 ◽  
pp. 338-349 ◽  
Author(s):  
A. Vidal-Ferrandiz ◽  
R. Fayez ◽  
D. Ginestar ◽  
G. Verdú
Keyword(s):  
Finite Element Method ◽  
Finite Element ◽  
Nuclear Power ◽  
Power Reactor ◽  
Nuclear Power Reactor ◽  
Element Method

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

scholarly journals Constraints on nonstandard neutrino interactions and unparticle physics withν¯e−e−scattering at the Kuo-Sheng nuclear power reactor

2010 ◽  
Vol 82 (3) ◽  
Author(s):  
M. Deniz ◽  
S. Bilmiş ◽  
İ. O. Yıldırım ◽  
H. B. Li ◽  
J. Li ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Reactor ◽  
Nuclear Power Reactor ◽  
Neutrino Interactions
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