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http://dx.doi.org/10.12989/sem.2002.14.2.191

Pressure-temperature limit curve for reactor vessel evaluated by ASME code  

Jhung, Myung Jo (Korea Institute of Nuclear Safety)
Kim, Seok Hun (Korea Institute of Nuclear Safety)
Jung, Sung Gyu (Korea Power Engineering Company, Inc.)
Publication Information
Structural Engineering and Mechanics / v.14, no.2, 2002 , pp. 191-208 More about this Journal
Abstract
A comparative assessment study for a generation of the pressure-temperature (P-T) limit curve of a reactor vessel is performed in accordance with ASME code. Using cooling or heating rate and vessel material properties, stress distribution is obtained to calculate stress intensity factors, which are compared with the material fracture toughness to determine the relations between operating pressure and temperature during reactor cool-down and heat-up. P-T limit curves are analyzed with respect to defect orientation, clad thickness, toughness curve, cooling or heating rate and neutron fluence. The resulting P-T curves are compared each other.
Keywords
pressure-temperature limit curve; fracture toughness; stress intensity factor; heat-up; cool-down; reactor vessel; ASME code;
Citations & Related Records

Times Cited By Web Of Science : 1  (Related Records In Web of Science)
Times Cited By SCOPUS : 1
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