LYRA and other projects on RPV steel embrittlement: Study and mitigation of the AMES Network

Nuclear Engineering and Design

Volumn 195, Issue 2, 2000, Pages 217-226

  Debarberis, L ^a   Von Estorff, U ^a   Crutzen, S ^d   Beers, M ^a   Stamm, H ^b   De Vries, M I ^c   Tjoa, G L ^c  

^a JOINT RESEARCH CENTRE   (Italy)

^b Inst for Hlth and Consum Protect   (Netherlands)

^c NUCLEAR RESEARCH AND CONSULTANCY GROUP NRG   (Netherlands)

^d EUROPEAN COMMISSION   (Belgium)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; EMBRITTLEMENT; PRESSURIZED WATER REACTORS; STEEL STRUCTURES;

HIGH FLUX REACTORS (HFR);

PRESSURE VESSELS;

EID: 0033890299     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(99)00244-7     Document Type: Article

References (6)

1. Davies, L.M., 1993. Neutron irradiation effects in pressure vessel steels and weldments. IAEA Specialist Meeting on Irradiation Embrittlement and Optimisation of Annealing, Paris, France, 20-23 September 1993.
2. Debarberis, L., Sordon, G., Tjoa, G.L., 1995. Ageing of materials: experimental study on reference steels at the IAM Petten. International Conference on Material Ageing and Component Life Extension, CISE, Italy, 1995.
3. von Estorff, U., Crutzen, S., Törrönen, K, 1997. The role of the Joint Research Centre Institute of Advanced Materials in the European Networks AMES, ENIO and NESC (in print).
4. Markgraf J.F.W., Tartaglia G.P., Tsotridis G. Irradiation devices and irradiation programmes at the HFR Petten for the investigation of the irradiation behaviour of stainless steels. Nucl. Eng. Des. 159:1995;81-89.
5. Markgraf, J.F. et al., 199?. The High Flux Reactor Petten, a mufti-purpose research and testing facility for the future of nuclear energy. Proc. ENS Class 1 Topical Meeting on Research Facilities for the Future of Nuclear Energy, ISBN 981-02-2779-5.
6. Rice J.R., Thomson R. Ductile versus brittle behaviour of crystals. Phil. Mag. 30:1974;73-97.