scholarly journals TWO COMPUTER CODES (REFCO AND POW76) FOR CALCULATING THE FUEL CYCLE COST OF A NUCLEAR POWER REACTOR.

1971 ◽  
Author(s):  
R. Salmon
Keyword(s):  
Nuclear Power ◽  
Fuel Cycle ◽  
Power Reactor ◽  
Nuclear Power Reactor ◽  
Computer Codes

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 Design and analysis of a free-piston stirling engine for space nuclear power reactor

2020 ◽  
Author(s):  
Zhiwen Dai ◽  
Chenglong Wang ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Reactor ◽  
Stirling Engine ◽  
Nuclear Power Reactor ◽  
Free Piston ◽  
Space Nuclear Power ◽  
Free Piston Stirling Engine

1D BWR Nuclear Power Reactor Model to Study Thermal-hydraulic Oscillations

2003 ◽  
Vol 3 (3) ◽  
pp. 445-454
Author(s):  
D. Ginestar ◽  
G. Verdú
Keyword(s):  
Nuclear Power ◽  
Power Reactor ◽  
Reactor Model ◽  
Nuclear Power Reactor
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