Community Research and Development Information Service - CORDIS

Abstract

In scaled experimental research the problem arises of adequate scaling of mechanical (pressure) and temperature loads; cracks in the vessel make the problem more complex. The described JRC approach attempts a solution of the scaling problems by simulating conditions in the nozzle corner and in the safe-end zones. The problem of examining the structural reliability of a cracked reactor pressure vessel which is exposed to repetitive pressurized thermal shock (PTS) loads, represents a follow-up of JRC research and experiments on the 1:5 scale PWR vessels loaded by pressure loads only. Results obtained there in the fields of elastic-plastic stress analysis, elastic-plastic fracture mechanics, NDE problems, cladding problems, etc. have been used also when tackling some of the PTS scaling problems. The way of tackling these problems in the planned PTS experiment is briefly described and some results given (use of "natural" fatigue cracks at the nozzle corner, pressure simulation, cladding effects, etc.). Also the overall JRC experimental facility for PTS experiments (scale 1:5) is briefly described, and the possibilities for the extrapolation and use of the results discussed.

Additional information

Authors: JOVANOVIC A, JRC ISPRA ESTAB. (ITALY);LUCIA A C, JRC ISPRA ESTAB. (ITALY);VOLTA G JRC ISPRA ESTAB. (ITALY), JRC ISPRA ESTAB. (ITALY)
Bibliographic Reference: REACTOR PRESSURE VESSEL BEHAVIOUR UNDER TRANSIENT CONDITIONS CAUSED BY THERMAL SHOCK, PLZEN (CZECHOSLOVAKIA), MAY 26-30, 1986 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32701 ORA
Availability: Can be ordered online
Record Number: 1989125056200 / Last updated on: 1987-11-01
Category: PUBLICATION
Available languages: en