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41
Pressure-Temperature Limit Curve For Reactor Vessel Evaluated By ASME Code
Pressure-Temperature Limit Curve For Reactor Vessel Evaluated By ASME Code
Myung Jo Jhung, Seok Hun Kim and Sung Gyu Jung (K, | 국제구조공학회 | 2002 ,
42
Multiphase Transport, 3. : Fundamentals, Reactor, Safety, Applications
Multiphase Transport, 3. : Fundamentals, Reactor, Safety, Applications
Veziroglu, T Nejat, 420.4-V597m | Hemisphere | 1980 420.4-V597m,
43
Engineerig Design and Structural Analysis of Nuclear Reactors
Engineerig Design and Structural Analysis of Nuclear Reactors
Mel'Nikov, N P, 429.24-M517e | Israel Program for Scientific Translations | 1967 429.24-M517e,
44
Multiphase Transport, 2. : Fundamentals, Reactor, Safety, Applications
Multiphase Transport, 2. : Fundamentals, Reactor, Safety, Applications
Veziroglu, T Nejat, 420.4-V597m | Hemisphere | 1980 420.4-V597m,
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