EP0037446B1

EP0037446B1 - Austenitic iron base alloy

Info

Publication number: EP0037446B1
Application number: EP19800303047
Authority: EP
Inventors: Michael Karl Korenko
Original assignee: Westinghouse Electric Corp
Current assignee: CBS Corp
Priority date: 1980-01-09
Filing date: 1980-09-02
Publication date: 1985-06-05
Also published as: DE3070736D1; JPS5698460A; EP0037446A1

Description

This invention relates to austenitic iron base alloys which find particular use in nuclear reactors and are characterized by improved swelling resistance and phase stability in both the annealed as well as the cold work condition in comparison with an AISI type 316 stainless steel.
With the advent of the nuclear age and the materials problems associated therewith, it was believed that the AISI type 316 stainless steel because of its austenitic character and which is strengthened through a solid solution strengthening addition would prove to be ideally suited for use in a nuclear reactor. This conclusion was supported by the fact that the AISI type 316 stainless steel appeared to possess the desired strength characteristics at elevated temperatures. It was soon found however that even after low fluid reactor irradiation copious amounts radiation induced precipitation were evident in the microstructure and the material was subjected to relatively high swelling. It therefore became apparent that it was necessary to alter the chemical composition AISI type 316 stainless steel in an attempt to eliminate the phase instabilities and to provide improved swelling resistance without seriously adversely affecting the strength characteristics of the fundamental alloy. To this end, the alloys of the present invention appear to fulfill these primary requisites.
Accordingly, the present invention resides in an austenitic iron base alloy having improved structural stability and swelling resistance compared to AISI type 316 stainless steel and which alloy is suitable for use in an atmosphere subject to neutron irradiation, characterized in that said alloy consists of from 14% to 16.5% nickel, from 12% to 14% chromium, from 1.2% to 1.7% molybdenum, from 0.5% to 1.1 % silicon, from 0.5% to 2.5% manganese, up to 0.1% zirconium, from 0.15% to 0.5% titanium, from 0.02% to 0.1% carbon, up to 0.01% boron and the balance iron with incidental impurities.
It has been found that the desired properties can be achieved by lowering the amounts of chromium, and molybdenum and by raising the amount of nickel while still maintaining the austenitic characteristic of the alloy when the same is subjected to elevated temperature irradiation of the type normally found, for example, in the case of fuel pins in a nuclear reactor. More specifically, the alloy will exhibit improved swelling resistance at elevated temperatures in both the annealed as well as the cold work condition.
In order that the invention can be more clearly understood, a preferred embodiment thereof will now be described, by way of example, with reference to the accompanying drawings in which:

Figure 1 is a plot of percent swelling verses the temperature of an alloy of the present invention in comparison with standard AISI type 316 stainless steel, the actual numbers of the data points being the actual fluence values; and
Figure 2 is a similar plot to Figure 1 but with the alloys in the cold work condition.

Table 1 set forth hereinafter lists the chemical composition of the AISI type 316 stainless steel as well as the broad range, the preferred range, and the specific composition of a heat falling within the broad ranges as set forth herein.
By inspection of Table 1 it becomes clear that the alloy of the present invention has less chromium, more nickel, and less molybdenum than that of a corresponding AISI type 316 stainless steel. Moreover, as can be seen from Table 1 the large reduction of the chromium together with a smaller reduction of the molybdenum and a small increase in the nickel is effective for maintaining the austenitic character of this alloy which austenitic character is strengthened by means of the molybdenum addition thereto. Note in particular that since the titanium and zirconium contents are quite limited, the microstructure of the alloy remains substantially precipitation free after extended exposures to the influence of neutron irradiation at elevated temperatures. In order to more clearly and graphically depict the improvement in swelling resistance exhibited by the alloy of the present invention, attention is directed to Figure 1 which directly compares a solution annealed AISI type 316 stainless steel and the alloy of this invention having the composition of heat number 5976 as identified in Table 1 and the effect of the temperature at various fluence values in relation to the percent swelling. Curve 10 of Figure 1 is a plot of the AISI type 316 stainless steel material whereas curve 12 is a plot of the identical values exhibited by the alloy of the present invention in the solution annealed condition which alloy has been arbitrarily designated D9B1. As can be seen from the data set forth in Figure 1, the alloy of the present invention has far superior swelling resistance to that exhibited by the AISI type 316 stainless steel. This is especially so when the percent swelling is considered at about the temperature of 600°C and a fluence value of 5.7_X10²² neutrons per square centimeter. These same results are more outstanding when the data is compared for the material in the cold work condition. Thus in Figure 2, the curve 20 illustrates the data for AISI type 316 stainless steel in the 20% cold work condition and curve 22 shows the swelling resistance of alloy D9B1 in the 25% cold work condition. It is also believed significant to point out that in the cold work condition, the alloy of the present invention is still densifying while the AISI type 316 stainless steel is into the void swelling regiment regardless of the temperatures employed. Thus, these data make it clear that the alloys of the present invention are particularly suitable for use for example in a fast breeder reactor. It has been found however that the long term stress rupture properties at temperatures greater than 650°C appear to be weaker than AISI type 316 stainless steel based on the lates unradiated specimen testing. However, it is believed that comparable results can be obtained where the material is in the cold worked condition and the degree of cold working is limited to about 20% for optimum stress rupture and swelling resistance characteristics. While it will be appreciated that the swelling resistance characteristics will still be outstanding where the alloy is worked to a degree greater than 20%. The optimum results appear to be obtained when the cold working is limited to 20%. For swelling resistance alone, it has been found that cold working the material within the range between 15% and 40% does not appear to adversely affect the swelling resistance demonstrated by the alloy of the present invention.

Claims

1. An austenitic iron base alloy having improved structural stability and swelling resistance compared to AISI type 316 stainless steel and which alloy is suitable for use in an atmosphere subject to neutron irradiation, characterised in that said alloy consists of from 14% to 16.5% nickel, from 12% to 14% chromium, from 1.2% to 1.7% molybdenum, from 0.5% to 1.1 % silicon, from 0.5% to 2.5% manganese, up to 0.1% zirconium, from 0.15% to 0.5% titanium, from 0.02% to 0.1% carbon up to 0.01% boron and the balance iron with incidental impurities.

2. An alloy according to claim 1, characterized in that said alloy consists of from 15.25% to 15.75% nickel, from 13.25% to 13.75% chromium, from 1.4% to 1.6% molybdenum, from 0.9% to 1.1% silicon, from 1.8% to 2.5% manganese, from 0.04% to 0.06% zirconium, from 0.2% to 0.3% titanium, from 0.03% to 0.04% carbon, up to 0.01% boron and the balance iron with incidental impurities.