Buy article PDF
The purchased file will be sent to you
via email after the payment is completed.
US$ 35
|
Structural Engineering and Mechanics Volume 14, Number 2, August 2002 , pages 191-208 DOI: https://doi.org/10.12989/sem.2002.14.2.191 |
|
|
|
Pressure-temperature limit curve for reactor vessel evaluated by ASME code |
||
Jhung MJ, Kim SH, Jung SG
|
||
| 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. | ||
| Key Words | ||
| pressure-temperature limit curve, fracture toughness, stress intensity factor, heat-up, cool-down, reactor vessel, ASME code | ||
| Address | ||
| Jhung MJ, Korea Inst Nucl Safety, Yusong Gu, 19 Kusong Dong, Taejon 305338, South Korea Korea Inst Nucl Safety, Yusong Gu, Taejon 305338, South Korea Korea Power Engn Co Inc, Yongin 449713, Kyunggi Do, South Korea | ||