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Within the framework of the European network on ageing materials evaluation and studies (AMES), a number of experimental works on reactor pressure vessel (RPV) materials embrittlement are carried out at the Institute for advanced materials (IAM) of the Joint Research Centre (JRC) of the European Commission (EC). The objectives of AMES are mainly the understanding of the properties degradation phenomena of RPV western reference steels like JRQ and HSST, eastern RPV steels like 15X2MFA and 15H2X15, and annealing possibilities. 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 (HFR) 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/pressurized water reactor conditions. For irradiation of standard or miniaturized light water reactor related materials samples, another group of well experienced irradiation devices with inert gas or liquid metals environments are employed. This paper is intended to give information about the structure and the objectives of AMES, and to present the various AMES main and spin-off projects, including the discussion on modelling activities related to RPV materials embrittlement.

Additional information

Authors: TÖRRÖNEN K ET AL, JRC Petten (NL)
Bibliographic Reference: Paper presented: Annual Meeting on Nuclear Technology, 1997
Availability: Available from (1) as Paper EN 41092 ORA
Record Number: 199810205 / Last updated on: 1998-02-12
Original language: en
Available languages: en
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