Computational methods assuring nuclear power plant structural integrity and safety: an overview of the recent activities at VTT-Reference-Cited by-同舟云学术

Computational methods assuring nuclear power plant structural integrity and safety: an overview of the recent activities at VTT

Published:1998-07 Issue:1-2 Volume:183 Page:41-51
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Keinänen Heikki,Talja Heli,Rintamaa Rauno

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference19 articles.

1. Erve, M., 1995a. IAEA Coordinated Research Programme (CRP) Management of Ageing of Reactor Pressure Vessel (RPV) Primary Nozzle. Results of Stage I, Working material IWG-LMNPP-95/2. International Atomic Energy Agency, Vienna.

2. Erve, M., 1995b. Brittle fracture evaluation in the dissimilar weld. In IAEA Coordinated Research Programme (CRP) Management of Ageing of Reactor Pressure Vessel (RPV) Primary Nozzle. Results of Stage I, Appendix 1, Part B, Working material IWG-LMNPP-95/2. International Atomic Energy Agency, Vienna.

3. Kantola, K., 1986. Calculation of the stress intensity factor by the weight function method. Technical Report YRT-3/86. Technical Research Centre of Finland (VTT), Nuclear Engineering Laboratory (in Finnish).

4. Keilová, E., Kocik, J., 1994. Microstructure of the VVER-440 dissimilar weld joints. Nuclear Research Institute Rez plc. Nucleon 3, p. 31.

5. Keinänen, H., 1994. Fracture analyses of large scale international reference experiments (FALSIRE). Phase II analyses, PTSI/6, NKS 5, Report VALB-36. VTT Manufacturing Technology, Finland.