Neutron embrittlement of wwer reactors: EC-supported projects

Results of the implementation of programs on the evaluation of the service life of reactor pressure vessels of NPPs are considered with the account of neutron embrittlement. Data on strength of WWER-440 reactor pressure vessels with a high and moderate content of detrimental impurities (copper and phosphorus) have been analyzed. For the welds of WWER-1000 reactor, drawbacks in the manufacture, dosimetry, and test procedures of surveillance specimens are shown. To ensure safe operation of reactor pressure vessels, new projects have been undertaken, focusing on the effect of neutron embrittlement of steel on the integrity of structures and on advanced experimental methods of studying material strength.