Radiation-induced embrittlement of WWÉR-440 reactor pressure-vessel steel under loading

The results of evaluating the reference temperature T0 are presented and Master Curve is constructed from the experimental data for steel 15Cr2MoVA (base metal of WWER-440 reactor pressure vessel) in three states: unirradiated. irradiated, and irradiated under stress. It is shown that mechanical loa...

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Veröffentlicht in:	Strength of materials 2003, Vol.35 (1), p.24-30
Hauptverfasser:	GRINIK, E. U, CHIRKO, L. I, GUL'CHUK, Yu. S, STRIZHALO, V. A, NOVOGRUDSKII, L. S, BALLESTEROS, A, DEBARBERIS, L, SEVINI, F
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences Condensed matter: structure, mechanical and thermal properties Energy Energy. Thermal use of fuels Exact sciences and technology Fatigue, brittleness, fracture, and cracks Fission nuclear power plants Fractures Installations for energy generation and conversion: thermal and electrical energy Mechanical and acoustical properties of condensed matter Mechanical engineering. Machine design Mechanical properties and methods of testing. Rheology. Fracture mechanics. Tribology Mechanical properties of solids Metals. Metallurgy Physics Steel design Steel tanks and pressure vessels boiler manufacturing
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Zusammenfassung:	The results of evaluating the reference temperature T0 are presented and Master Curve is constructed from the experimental data for steel 15Cr2MoVA (base metal of WWER-440 reactor pressure vessel) in three states: unirradiated. irradiated, and irradiated under stress. It is shown that mechanical load, which simulates the coolant pressure, accelerates radiation embrittlement, whose contribution is comparable to that of neutron irradiation.
ISSN:	0039-2316 1573-9325
DOI:	10.1023/A:1022913119524