Effects of hold time and neutron irradiation on the low-cycle fatigue behaviour of type 316-CL and their consideration in a damage model

Nuclear Engineering and Design

Volumn 213, Issue 2-3, 2002, Pages 111-117

  Aktaa, J ^a   Horsten, M G ^b   Schmitt, R ^a  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b NUCLEAR RESEARCH AND CONSULTANCY GROUP NRG   (Netherlands)

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITE; CREEP; EMBRITTLEMENT; EXPERIMENTAL REACTORS; FAILURE ANALYSIS; FATIGUE OF MATERIALS; NEUTRON IRRADIATION; STRAIN;

HIGH FLUX REACTORS (HFR);

STAINLESS STEEL;

EID: 0036531831     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(01)00511-8     Document Type: Article

References (15)

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4. Creep rupture under multiaxial state of stress
5. Influence of low dose irradiation on the design criteria of fixed internals in fast reactors
6. Fatigue and creep-fatigue behavior of irradiated and unirradiated Type 308 stainless steel weld metal at elevated temperatures, properties of reactor structural alloys after neutron or particle irradiation
7. Hochtemperatur-ermüdungsverhalten des austenitischen EFR-werkstoffes 316 L(N)
8. Creep rupture
9. Fast reactor programme irradiation effects on the mechanical properties of 18Cr-11Ni stainless steel (DIN 1.4948, type AISI 304 ss)
10. Irradiation devices and testing facilities for small specimens of low-activation steels
11. Tensile, creep, and fatigue properties of low-fluence neutron-irradiated welded joints DIN 1.4948, Effect of radiation on materials: 10th conference
12. Effects of temperature and strain rate on the low cycle fatigue properties of neutron irradiated stainless steel DIN 1.4948, Effects of radiation on materials: 11th conference