Development of a PFM code for evaluating reliability of pressure components subject to transient loading
- 11 August 2001
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 208 (1) , 1-13
- https://doi.org/10.1016/s0029-5493(01)00361-2
Abstract
No abstract availableThis publication has 3 references indexed in Scilit:
- Progress of LWR structural safety research at JAERINuclear Engineering and Design, 1997
- Further Experimental Verification of Warm Prestressing Effect Under Pressurized Thermal Shock (PTS)Journal of Pressure Vessel Technology, 1996
- Failure probability of PWR reactor coolant loop piping. [Double-ended guillotine break]Published by Office of Scientific and Technical Information (OSTI) ,1984