Investigations of BOR-60 Structural Materials and Prospects for Further Work |
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| Authors: | V. N. Golovanov V. K. Shamardin V. I. Prokhorov V. S. Neustroev V. A. Kazakov G. P. Kobylyanskii A. M. Pecherin A. V. Povstyanko T. M. Bulanova V. A. Krasnoselov A. E. Fedoseev |
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| Affiliation: | (1) State Science Center of the Russian Federation – Scientific-Research Institute of Nuclear Reactors, Russia |
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| Abstract: | Since its startup in December in 1969, the BOR-60 reactor has been used effectively for irradiation of structural and fuel materials in a wide range of dose–temperature parameters. Analysis of the actual computational-experimental parameters (irradiation temperature, damage rates) shows that the irradiation conditions are highly reproducible and can be maintained accurately.The investigations made it possible to study phenomena which are important for building reactors using domestic structural materials and to choose the optimal composition and heat treatment of the materials.New directions are indicated for scientific-research work, for improving and increasing the service life of VVÉR type reactors, and for developing new-generation structural materials for fusion reactors being designed. |
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