Fracture mechanics characterisation of the beltline welding seam of the decommissioned WWER-440 reactor pressure vessel of nuclear power plant Greifswald Unit 4

Author:

Viehrig Hans-Werner,Altstadt Eberhard,Houska Mario,Valo Matti

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference20 articles.

1. Konheiser J, Rindelhardt U, Viehrig H-W, Böhmer B, Gleisberg B. Pressure vessel investigations of the former Greifswald NPP: fluence calculations and Nb based fluence measurements. ICONE14/FEDSM2006 Proceedings, Contribution ICONE 14–89578, 2006M.

2. N.N.: safety assessment of the nuclear power plant Greifswald units 1 to 4. report GRS78,1991

3. Böhmer B, Böhmert J, Müller G, Rindelhardt U, Utke H. Embrittlement studies of the reactor pressure vessel of the Greifswald WWER-440 reactors. Technical Report Task 4: Data Collection; Project Reference: NUCRUS96601 Technical Report, published October 1999, TACIS service DG IA, European Commission, TACIS Information Office, European Commission, Aarlenstraat 88 1/06 Rue d’ Arlon, 1040 Brussels, Belgium.

4. Post mortem investigations of the NPP Greifswald WWER-440 reactor pressure vessels. Proceedings of the 19th International Conference on structural mechanics in reactor technology;Viehrig,2007

5. Investigation of the beltline welding seam of the Greifswald WWER-440 unit 1 reactor pressure vessel;Viehrig;Journal of ASTM International,2009

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