Flux and composition dependence of irradiation creep of austenitic alloys irradiated in PFR at ∼420°C

Author:

Toloczko M.B.,Garner F.A.,Standring J.,Munro B.,Adaway S.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference20 articles.

1. The effects of temperature and dose-rate variations on the creep of austenitic stainless steels in the dounreay fast reactor

2. G.W. Lewthwaite, D. Mosedale, in: Proceedings of the Conference on Dimensional Stability and Mechanical Behavior of Irradiated Metals and Alloys, vol. 1, BNES, 1983, pp. 129–132

3. An assessment of tensile, irradiation creep, creep rupture, and fatigue behavior in austenitic stainless steels with emphasis on spectral effects

4. Irradiation creep and void swelling of austenitic stainless steels at low displacement rates in light water energy systems

5. F.A. Garner, M.B. Toloczko, S.I. Porollo, A.N. Vorobjev, A.M. Dvoriashin, Yu.V. Konobeev, in: The Eighth International Symposium on Effects of Degradation of Materials in Nuclear Power Systems – Water Reactors, 10–14 August 1997, Amelia Island, FL, 1987, pp. 834–845

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