scholarly journals Set-Based Models for Cryptocurrency Software

2021 ◽  
Vol 24 (3) ◽  
Author(s):  
Gustavo Betarte ◽  
Maximiliano Cristiá ◽  
Carlos Luna ◽  
Adrián Silveira ◽  
Dante Zanarini
Keyword(s):  
Software Development ◽  
Nuclear Power ◽  
Power Reactor ◽  
Software Industry ◽  
The Other ◽  
Nuclear Power Reactor ◽  
High Quality ◽  
Relevant Case ◽  
Development Methods ◽  
Certified Software

Formal methods (FM) are mathematics-based software development methods aimed at producing ``code for a nuclear power reactor''. That is, due application of FM can produce bug-free, zero-defect, correct-by-construction, guaranteed, certified software. However, the software industry seldom use FM. One of the main reasons for such a situation is that there exists the perception (which might well be a fact) that FM increase software costs. On the other hand, FM can be partially applied thus producing high-quality software, although not necessarily bug-free. In this paper we outline some FM related techniques whose application the cryptocurrency community should take into consideration because they could bridge the gap between ``loose web code'' and ``code for a nuclear power reactor''. We include relevant case studies in the area of cryptocurrency.

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.

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
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