Community Research and Development Information Service - CORDIS

Abstract

This is the latest in a series of reports on the evaluation of material tests using a full-scale boiling water reactor pressure vessel. It covers the period since 1988, during which Pressurised Water Reactor components have been added. A variety of faults was incorporated in these modules. In the first phase of tests a selection of the faults were ultrasonically inspected in accordance with ASME procedures and subsequently examined by teams from several countries. The results obtained by most of these are now available. In the second phase a central mast manipulator was placed at the MPA's disposal. Using slightly modified ASME techniques, under the supervision of an international team of experts in non-destructive testing, locations on the casing on two PWR modules and on the two Parametric Studies Blocks were inspected. Results from the latter accord well with measurements made in the course of the PISC II programme of inspections. The third phase, that of realistic inspection techniques, is continuing. Not all results are yet available, but the tests, in the course of which a wide variety of techniques suitable for regular inspection procedures were put to use, are judged to have been successful. The removal of a drill core for destructive metallographic verification of the results is planned for 1991.

Additional information

Authors: CRUTZEN S, JRC Ispra (IT);HERKENRATH H, JRC Ispra (IT);KUSSMAUL K, Universität Stuttgart, MPA (DE);MLETZKO U, Universität Stuttgart, MPA (DE)
Bibliographic Reference: Paper presented: 16. MPA-Seminar, Stuttgart (DE), Oct. 4-5, 1990
Availability: Available from (1) as Paper DE 35749 ORA
Record Number: 199011592 / Last updated on: 1994-12-02
Category: PUBLICATION
Original language: de
Available languages: de