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Koo, Gyeong Hoi; Lee, J. H.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2008
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2008
AbstractAbstract
[en] In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail
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Jan 2008; 171 p; Also available from KAERI; 24 refs, 30 figs, 2 tabs
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Report
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