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Home > Development of a Finite Element Computer Code for Thermal and Stress Analysis of Nuclear Reactor Components

Development of a Finite Element Computer Code for Thermal and Stress Analysis of Nuclear Reactor Components

Thesis Info

Author

Bashir Muhammad Zahid

Department

Pakistan Institute of Engineering & Applied Sciences, Nilore

Program

MSc

Institute

Quaid-i-Azam University

Institute Type

Public

City

Islamabad

Province

Islamabad

Country

Pakistan

Thesis Completing Year

2000

Thesis Completion Status

Completed

Page

ix, 100

Subject

Engineering & Applied Sciences

Language

English

Other

Call No: DISS/M.Sc PIEAS/164

Added

2021-02-17 19:49:13

Modified

2023-01-06 19:20:37

ARI ID

1676715711683

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