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Pressure-Temperature Limit Curve For Reactor Vessel Evaluated By ASME Code
Pressure-Temperature Limit Curve For Reactor Vessel Evaluated By ASME Code
Detailed Information
- Material Type
- 기사
- ISSN
- 12254568
- Title/Author
- Pressure-Temperature Limit Curve For Reactor Vessel Evaluated By ASME Code / Myung Jo Jhung, Seok Hun Kim and Sung Gyu Jung (Korea) 저
- Publish Info
- 대전 : 국제구조공학회, 2002.
- Material Info
- pp. 191-208
- Added Entry-Personal Name
- Myung Jo Jhung, Seok Hun Kim and Sung Gyu Jung (Korea)
- Host Item Entry
- Structural Engineering and Mechanics, An International Journal : Volume 14, Number 2, (2002 August) 2002, 08
- 모체레코드
- 모체정보확인
- Control Number
- kjul:60011018
MARC
008030704s2002 ULKa a KOR■022 ▼a12254568
■245 ▼aPressure-Temperature Limit Curve For Reactor Vessel Evaluated By ASME Code▼dMyung Jo Jhung, Seok Hun Kim and Sung Gyu Jung (Korea) 저
■260 ▼a대전▼b국제구조공학회▼c2002.
■300 ▼app. 191-208
■653 ▼aPRESSURETEMPERATURE▼aLIMIT▼aCURVE▼aREACTOR▼aVESSEL▼aEVALUATED▼aASME▼aCODE
■700 ▼aMyung Jo Jhung, Seok Hun Kim and Sung Gyu Jung (Korea)
■773 ▼tStructural Engineering and Mechanics, An International Journal▼gVolume 14, Number 2, (2002 August)▼d2002, 08
■SIS ▼aS008435▼b60010254▼h8▼s2
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