Fatigue Crack Propagation in Fast Neutron Irradiated Stainless Steels and Welds

Fatigue Crack Propagation in Fast Neutron Irradiated Stainless Steels and Welds
Author: P. Shahinian
Publisher:
Total Pages: 14
Release: 1975
Genre: Crack propagation
ISBN:

Neutron irradiation to a fluence of 1.2 x 1022 neutrons (n)/cm2, > 0.1 MeV caused a small decrease in the resistance to fatigue crack propagation of Types 308 and 316 submerged-arc weld metals at 800 and 1100°F (427 and 593°C). Nevertheless, the postirradiation fatigue resistances of the weld metals were generally comparable to those of the corresponding base metal. Fatigue crack growth in Types 304 and 316 base metals were also affected by irradiation; the effect was dependent on the stress intensity factor and temperature. Although resistance to crack growth of cold-worked (25 percent) Type 304 stainless steel was only slightly reduced at 800°F by irradiation, the resistance at 1100°F was reduced markedly.

Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperatures

Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperatures
Author: P. Shahinian
Publisher:
Total Pages: 16
Release: 1973
Genre: Compressible flow
ISBN:

Resistance to fatigue crack propagation of pre- and postirradiation AISI Types 304 and 316 stainless steels was determined at 800 and 1100 F (427 and 593 C) using the fracture mechanics approach. The effect of irradiation on fatigue resistance was dependent upon test temperature and irradiation conditions. In general, irradiation degraded fatigue resistance at 1100 F (593 C) but at 800 F (427 C) enhancement as well was observed. In both steels irradiated in a thermal reactor to a fluence of 1.8 x 1021 n/cm2 >0.1 MeV, fatigue crack growth rates at 800 F (427 C) were lower than in the unirradiated steels for a given stress intensity factor range (?K). However, at 1100 F (593 C) the effect was reversed and crack growth rates were higher in the irradiated steels. Irradiation in a fast reactor to a fluence of ~1.2 x 1022 n/cm2 >0.1 MeV caused fatigue crack growth rates at 800 F (427 C) to increase at low values of ?K and decrease at high values of ?K. At 1100 F (593 C) the crack growth rates in the irradiated steel were either the same as or higher than in the unirradiated steel. The influence of irradiation on fatigue life generally reflected the effect observed on crack growth rate.

Fatigue Crack Growth and Fracture Toughness Properties of Low Fluence Neutron-Irradiated Type 316 and Type 304 Stainless Steels

Fatigue Crack Growth and Fracture Toughness Properties of Low Fluence Neutron-Irradiated Type 316 and Type 304 Stainless Steels
Author: MI. De Vries
Publisher:
Total Pages: 17
Release: 1987
Genre: Crack propagation
ISBN:

Small compact-tension specimens of Type 316 plate and Type 304 forging have been irradiated in the High Flux Reactor (HFR) at Petten, The Netherlands, up to a fluence level of 2 x 1024 neutrons (n) . m-2 (E > 0.1 MeV) at 573 K. Post-irradiation fatigue crack propagation tests and J-integral fracture toughness tests have been performed at the irradiation temperature. Additional tests were made at the higher temperatures of 723 and 823 K.

Nuclear Science Abstracts

Nuclear Science Abstracts
Author:
Publisher:
Total Pages: 632
Release: 1975
Genre: Nuclear energy
ISBN:

NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.