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D. Erak, A. Kryukov, A. Ballesteros (2002)
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The Actual Properties of WWER-440 Reactor Pressure Vessel Materials Obtained by Impact Tests of Subsize Specimens Fabricated out of Samples Taken from the RPVASTM special technical publications
In work on minisamples of the fifth complex of the No. 3 unit of the Kola nuclear power plant it is shown that for neutron fluence 4⋅1023 m−2 (operation for approximately 10 yr), neutron flux density 3⋅1015 sec−1⋅m−2 and copper content 0.03% and 0.09% in the metal the shifts of the cold-brittleness temperature are 50 and 120°C, respectively. Under the same irradiation conditions but with neutron flux density 3⋅1016 sec−1⋅m−2, this shift for standard samples is 50°C. These results attest to the state of the vessel material at a given moment in time.
Atomic Energy – Springer Journals
Published: Feb 14, 2005
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