Residual Cold Work and Its Influence on Tensile and Creep Properties of Types 304 and 316 Stainless Steel

1976 ◽  
Vol 31 (1) ◽  
pp. 96-114 ◽  
Author(s):  
V. K. Sikka ◽  
R. W. Swindeman ◽  
T. L. Hebble ◽  
C. R. Brinkman ◽  
M. K. Booker
Keyword(s):  
Stainless Steel ◽  
Cold Work ◽  
Creep Properties ◽  
316 Stainless Steel

EFFECTS OF CARBON, NITROGEN, AND MOLYBDENUM ON CREEP PROPERTIES OF TYPE 316 STAINLESS STEEL

1989 ◽  
pp. 1041-1048 ◽  
Author(s):  
T. Nakazawa ◽  
H. Abo ◽  
M. Tanino ◽  
H. Komatsu ◽  
T. Nishida ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Creep Properties ◽  
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.

Thermal creep properties of alloy D9 stainless steel and 316 stainless steel fuel clad tubes

2008 ◽  
Vol 85 (12) ◽  
pp. 866-870 ◽  
Author(s):  
S. Latha ◽  
M.D. Mathew ◽  
P. Parameswaran ◽  
K. Bhanu Sankara Rao ◽  
S.L. Mannan
Keyword(s):  
Stainless Steel ◽  
Thermal Creep ◽  
Creep Properties ◽  
316 Stainless Steel ◽  
Alloy D9

Creep Properties of Three Heats of Type 316 Stainless Steel for Elevated Temperature Nuclear Applications

1988 ◽  
Vol 81 (1) ◽  
pp. 114-121 ◽  
Author(s):  
M. D. Mathew ◽  
S. latha ◽  
G. Sasikala ◽  
S. L. Mannan ◽  
P. Rodriguez
Keyword(s):  
Stainless Steel ◽  
Elevated Temperature ◽  
Creep Properties ◽  
316 Stainless Steel ◽  
Nuclear Applications

scholarly journals Creep Properties of Low-Carbon Nitrogen-Alloyed Modified 316 Stainless Steel.

1991 ◽  
Vol 40 (457) ◽  
pp. 1283-1289
Author(s):  
Kazuo OGAWA ◽  
Tetsuro UNO ◽  
Nobuhiro FUJITA ◽  
Hidetaka KIMURA ◽  
Takanori NAKAZAWA
Keyword(s):  
Stainless Steel ◽  
Low Carbon ◽  
Creep Properties ◽  
316 Stainless Steel

Influence of carbon and nitrogen on the creep properties of type 316 stainless steel at 873 K

1991 ◽  
Vol 148 (2) ◽  
pp. 253-260 ◽  
Author(s):  
M.D. Mathew ◽  
G. Sasikala ◽  
K. Bhanu Sankara Rao ◽  
S.L. Mannan
Keyword(s):  
Stainless Steel ◽  
Creep Properties ◽  
Carbon And Nitrogen ◽  
316 Stainless Steel
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