Community Research and Development Information Service - CORDIS

Abstract

Within the framework of the European network ageing materials evaluation and studies (AMES), a number of experimental works on reactor pressure vessel (RPV) materials embrittlement have been carried out. In order to conduct a very high quality irradiation programme, an AMES dedicated irradiation rig, LYRA facility, has been designed and developed at the high flux reactor (HRF) Petten. Another dedicated rig, named LIMA, has been developed at the HFR Petten in order to irradiate RPV steels, internals and in-core materials under typical boiling water reactor (BWR)/pressurized water reactor (PWR) conditions. The samples can be irradiated in pressurized water up to 160 bar, 320 C, and the water chemistry fully controlled. For irradiation of standard or miniaturized light water reactor (LWR) related materials samples, another group of well experienced irradiation devices with inert gas or liquid metals environment are employed. These devices are tailored to their various specific applications. This paper is intended to give information about the structure and the objectives of the existing European network AMES, and to present the various AMES main and spin-off projects, including a brief description on the modelling activities related to RPV materials embrittlement.

Additional information

Authors: DEBARBERIS L ET AL, JRC Petten (NL);STAMM H, JRC Ispra (IT);DE VRIES M I ET AL, ECN, Petten (NL)
Bibliographic Reference: Paper presented: Structural Mechanics in Reactor Technology, SMIRT Seminar no.2, Session 1: Irradiation Embrittlement, Lyon (FR), 25-26 August, 1997
Availability: Available from (1) as Paper EN 40968 ORA
Record Number: 199711554 / Last updated on: 1997-12-09
Category: PUBLICATION
Original language: en
Available languages: en