scholarly journals Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

1985 ◽  
Author(s):  
P.J. Maziasz
Keyword(s):  
Stainless Steel ◽  
Neutron Irradiation ◽  
Microstructural Development ◽  
Helium Content ◽  
316 Stainless Steel

Microstructure and Post-Irradiation Annealing Behavior of 20% Cold-Worked 316 Stainless Steel

2000 ◽  
Vol 650 ◽  
Author(s):  
J. I. Cole ◽  
T. R. Allen ◽  
H. Kusanagi ◽  
K. Dohi ◽  
J. Ohta
Keyword(s):  
Stainless Steel ◽  
Cold Work ◽  
Microstructural Development ◽  
Dislocation Loops ◽  
Annealing Behavior ◽  
Post Irradiation ◽  
316 Stainless Steel ◽  
Dose Rates ◽  
Cold Worked

ABSTRACTMicrostructural examination and in situ post-irradiation annealing studies were carried out on 20% cold-worked 316 stainless steel (SS) hexagonal duct material following irradiation in the reflector region of the EBR-II reactor. Stainless steel hexagonal ducts were used to house reactor subassemblies and provide a valuable source of information on irradiation behavior of reactor structural materials at lower dose-rates (on the order of 10-8 dpa/sec) than previously examined. The microstructural development of samples irradiated to doses of 1, 20 and 30 dpa is examined, while the post-irradiation annealing behavior of a sample irradiated to 20 dpa is described. Annealing studies were performed at 370 and 500°C to examine the kinetics of radiation damage recovery as a function of annealing temperature. The initial (pre-annealed) microstructures consists of a substantial density of irradiation induced chromium-rich M23C6 and M6C carbides which form both on the grain boundaries and within the grain interiors. Recovery of the cold- work is evident in the 1 dpa sample while samples irradiated to 20 and 30 dpa possess dense populations of voids and dislocation structures consisting of networks of line dislocations and faulted dislocation loops. Results indicate that post-irradiation annealing of the samples at 370°C for 1 hour has little effect on the microstructure, while further annealing at 500°C for 1 hour results in void shrinkage, the formation of small cavities, and a reduction in the dislocation loop and network density.

scholarly journals DT fusion neutron irradiation of LLL 316 stainless steel

1976 ◽  
Author(s):  
S. C. MacLean
Keyword(s):  
Stainless Steel ◽  
Neutron Irradiation ◽  
316 Stainless Steel ◽  
Fusion Neutron

Neutron irradiation effects on tensile properties of welded type 316 stainless steel

1986 ◽  
Vol 5 (3) ◽  
pp. 257-259
Author(s):  
Toshimi Yamane ◽  
Keiichi Hirao ◽  
Yoritoshi Minamino
Keyword(s):  
Stainless Steel ◽  
Tensile Properties ◽  
Neutron Irradiation ◽  
Irradiation Effects ◽  
316 Stainless Steel
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