الفهرس 
ContentsOnly 14 pages are availabe for public view
 |  | from | 205 |  |  |
| | | from | 205 | | |
Abstract
The integrity of the pressure vessel (PV) in pressurized water reactors (PWRS) is one of the major aspects in reactor safety study..
The change in mechanical properties of the PV material, due to the continuous irradiation during the reactor life time, and the recovery effects of the
annealing process are two important areas--that-have been
extensively studied but an experimental level. This
present study develops mathematical models for :
1. Void formation and percentage swelling due to
irradiation
ii. Percentage swelling due to Helium production.
iii.Nul-ductility transition temperature (NDT) change as releated to the total developed swelling.
iv. NDT recovery induced by the annealing process.
The study utilizes available experimental results in getting the best fit of the analytical model described above.
A main concern was directed towards developing a procedure that conservatively estimate one lite time (age) of the PV. by the end of this ace, the decision for