Brittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident

The brittle failure assessment for the reactor pressure vessel (RPV) of a 1300MW pressurized water reactor was revised according to the state of the art. The RPV steel is 22 NiMoCr 37 (A 508 Cl. 2). The expected neutron fluence at the end of license (EOL) after 32years of full operation is Φ

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Bibliographische Detailangaben
Veröffentlicht in:	Journal of pressure vessel technology 2008-08, Vol.130 (3), p.031403 (8)-031403 (8)
Hauptverfasser:	Siegele, Dieter, Varfolomeyev, Igor, Nagel, Gerhard
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fracture mechanics (crack, fatigue, damage...) Fundamental areas of phenomenology (including applications) Installations for energy generation and conversion: thermal and electrical energy Materials and Fabrication Mechanical engineering. Machine design Physics Solid mechanics Static elasticity (thermoelasticity...) Steel design Steel tanks and pressure vessels boiler manufacturing Structural and continuum mechanics
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Beschreibung
Zusammenfassung:	The brittle failure assessment for the reactor pressure vessel (RPV) of a 1300MW pressurized water reactor was revised according to the state of the art. The RPV steel is 22 NiMoCr 37 (A 508 Cl. 2). The expected neutron fluence at the end of license (EOL) after 32years of full operation is Φ
ISSN:	0094-9930 1528-8978
DOI:	10.1115/1.2937759