The effect of thermal aging on fracture properties of a narrow-gap Alloy 52 dissimilar metal weld

Author:

Lindqvist Sebastian,Que Zaiqing,Nevasmaa Pekka,Hytönen Noora

Funder

Teknologian Tutkimuskeskus VTT

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference32 articles.

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2. Aaltonen P, Hänninen H. Water chemistry and behavior of materials in PWRs and BWRs. IAEA-TECDOC-965, Vienna, Austria: IAEA; 1997, p. 205–22.

3. Ehrnstén U. Corrosion and stress corrosion cracking of austenitic stainless steels. In: Allen TR, Stoller RE, Yamanaka S, editors. Compr. Nucl. Mater., Amsterdam, The Netherlands: Elsevier Ltd; 2012, p. 93–104.

4. IAEA. Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of irradiation embrittlement effects in reactor pressure vessel steels. 2009.

5. International Review of Nuclear Reactor Pressure Vessel Surveillance Programs;Server;STP1603,2018

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