scholarly journals Discussions on Availability of Weather Information Data and Painting Effect of Existing 8,600 TEU Container Ship Using Ship Performance Analysis Program

2020 ◽  
Vol 34 (6) ◽  
pp. 377-386
Author(s):  
Myung-Soo Shin ◽  
Min Suk Ki ◽  
Gyeong Joong Lee ◽  
Beom Jin Park ◽  
Yeong Yeon Lee ◽  
...  
Keyword(s):  
Performance Analysis ◽  
Container Ship ◽  
Analysis Program ◽  
Weather Information ◽  
Ship Performance

Development of a gas turbine performance analysis program and its application

Energy ◽  
2011 ◽  
Vol 36 (8) ◽  
pp. 5274-5285 ◽  
Author(s):  
Jong Jun Lee ◽  
Do Won Kang ◽  
Tong Seop Kim
Keyword(s):  
Performance Analysis ◽  
Gas Turbine ◽  
Analysis Program ◽  
Turbine Performance

Container Ship Round Trip Performance Analysis - A Case of Study Between East South America and Europe

2020 ◽  
Author(s):  
João Henrique Vieira ◽  
Fabio Rossi ◽  
Ramiro Fernandes Ramos ◽  
Sarah Menezes Alves ◽  
Jean-David Caprace
Keyword(s):  
Performance Analysis ◽  
South America ◽  
Container Ship ◽  
Round Trip

scholarly journals Lead-Cooled Fast Reactor Annular UN Fuel Design and Development of Performance Analysis Program

2021 ◽  
Vol 9 ◽  
Author(s):  
He Yuan ◽  
Guan Wang ◽  
Rui Yu ◽  
Yujie Tao ◽  
Zhaohao Wang ◽  
...  
Keyword(s):  
Performance Analysis ◽  
Fast Reactor ◽  
Strain Analysis ◽  
Analysis Program ◽  
Fuel Temperature ◽  
Stress Strain ◽  
Fuel Design ◽  
Simulation Results ◽  
Uranium Nitride ◽  
Fortran Programming Language

A kind of annular uranium nitride (UN) fuel suitable for lead-cooled fast reactor applications has been designed in this study. The design is directly targeting two main issues of UN fuel: severe swelling and thermal decomposition of UN fuel at high temperatures. A performance analysis program based on FORTRAN programming language has been developed for UN fuel in fast reactors. The program contains heat transfer, fuel stress-strain analysis, cladding stress-strain analysis, fission gas release and fuel-cladding mechanical interaction (FCMI) modules, etc. Extensive code verification has been performed by comparing simulation results obtained with the code and those obtained via the COMSOL Multiphysics platform. Preliminary code validation has been conducted as well by comparing code simulation results with experimental data. The results showed that this program could predict the fuel temperature, stress-strain, and displacement of UN fuel during reactor operation with a reasonable accuracy.

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