US3576622A - Nickel-base alloy - Google Patents

Nickel-base alloy Download PDF

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US3576622A
US3576622A US732962A US3576622DA US3576622A US 3576622 A US3576622 A US 3576622A US 732962 A US732962 A US 732962A US 3576622D A US3576622D A US 3576622DA US 3576622 A US3576622 A US 3576622A
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alloy
weight percent
nickel
base alloy
strength
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US732962A
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Herbert E Mccoy Jr
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US Atomic Energy Commission (AEC)
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    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C19/00Alloys based on nickel or cobalt
    • C22C19/03Alloys based on nickel or cobalt based on nickel
    • C22C19/05Alloys based on nickel or cobalt based on nickel with chromium
    • C22C19/051Alloys based on nickel or cobalt based on nickel with chromium and Mo or W
    • C22C19/057Alloys based on nickel or cobalt based on nickel with chromium and Mo or W with the maximum Cr content being less 10%

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  • the present invention relates to an improved nickelbase alloy. More particularly, it relates to an improvement in the nickel-base alloy known as I-NOR-8 or Hastelloy- N, the composition of which is described in U.S. Pat. No. 2,921,850 as comprising -22 weight percent molybdenum, 6-8 weight percent chromium, 0.02-0.5 Weight percent carbon, and the balance nickel.
  • This alloy was developed to meet a specific need for a material with suflicient high temperature strength that would also resist corrosive attack by molten fluoride salt mixtures. As such it was intended to serve as a fuel carrier and coolant in molten salt reactors of the kind under development by the U.S. Atomic Energy Commission at Oak Ridge, Tenn.
  • INOR-S has suitable properties for long-time use at high temperatures, a deterioration of these properties occurs in a high neutron field.
  • the alloy is susceptible to a form of high temperature irradiation damage that reduces its creep rupture life.
  • One form of irradiation damage has been attributed to nuclear transmutation involving helium formation, principally from the n,a reaction with boron-10. It has been postulated that the helium collects at the grain boundaries and promotes intergranular cracks. This type of irradiation damage has been found to be general for ironand nickelbase alloys.
  • the cause of the persisting embrittling effect is releated to the formation of a secondary, precipitated phase which has been identified by microprobe anaysis as a M C type precipitate where M, in weight percent, represents approximately 55 Mo, 31 Ni, 5 Cr, 5 Si, 4 Fe, and a residuum of other metals and non-metals.
  • the present invention provides a modification of the basic INOR-S alloy as disclosed in U.S. Pat. No. 2,921,- 850 and modified in U.S. patent application SJN. 603,085 by varying the molybdenum concentration in an amount sufiicient to effectively reduce or eliminate formation of the M C type precipitate as a secondary phase.
  • the present invention resides in a nickel-base alloy containing as essential alloying ingredients, in weight percent, 11-13 percent Mo, 6-8 percent Cr, 0.02-0.5 percent carbon, an amount of boride forming element selected from Ti, Zr, and Hf sufiicient to convert incidental amounts of boron to a boride of said selected element, from 0 up to 4 percent of a strengthening agent selected from W, Ta, V, and Nb, the balance being nickel.
  • FIG. 1 shows curves relating strength in creep in a plot of stress vs. rupture time of alloys within the scope of the invention in the unirradiated and irradiated states;
  • FIG. 2 shows ductility curves in terms of elongation at fracture as a function of rupture time in the irradiated and unirradiated states
  • FIG. 3 shows curves of stress vs. rupture time of welds made from alloys within the scope of the invention.
  • FIGS. 1-3 also include strength and ductility curves of alloys falling outside the scope of the invention which serve as a basis for comparison. Reference in detail to the data shown in these drawings will be made in the ensuing description.
  • the upper concentration of M0 in the alloy according to my invention should not exceed 13 weight percent in order to avoid the formation of the M C precipitated phase.
  • Concentrations of M0 in the range 11-13 weight percent provide the optimum Mo concentration in terms of producing an alloy which (1) will not form the persistent M C brittle intergranular secondary phase, (2) will be corrosion resistant to molten fluoride compositions, (3) will make for maximum fabrication ease, and (4) will be weldable. While lower concentrations will be effective to eliminate the M C phase, it will also tend to reduce the other desirable criteria mentioned.
  • Concentrations of iron may vary up to 6% by weight without affecting the advantages achieved by the essential alloying in- TABLE II.COMPARATIVE TENSILE PROPERTIES Standard INOR-S alloy Representative improved alloy Strength, K 5.1.
  • the improved alloy exhibits somewhat greater ductility, but at the cost of a loss in strength in comparison to the standard INOR-8 alloy (16 weight percent M0).
  • the loss in strength can be made up, however, by adding a solid solution strengthening concentration of at least one metal selected from W, Ta, V, or Nb.
  • the strength in creep at 650 C. for the two alloys is shown in FIG. 2 for the irradiated and non-irradiated case.
  • the strength of the repersentative alloy of the subject invention (curve C) is unaffected by radiation, whereas there is considerable reduction in strength between the reference INOR8 alloy in the irradiated (curve A) and non-irradiated (curve B) state.
  • An improved nickel-base alloy consisting essentially of 11-13 Weight percent molybdenum, 6-8 weight percent chromium, 0.02 to 0.5 weight percent carbon, an effective concentration of a boride forming element selected from the group consisting of titanium, zirconium, and hafnium sufiicient to react with incidental quantities of boron in the alloy to form a boride of said element, up to 4 weight percent of at least one strengthening agent from the group consisting of tungsten, tantalum, vanadium, and niobium, and the balance nickel.

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Manufacture Of Alloys Or Alloy Compounds (AREA)

Abstract

AN IMPROVED NICKEL-BASE ALLOY WHICH CONTAINS A ESSENTIAL ALLOYING INGREDIENTS 11-13 WEIGHT PERCENT MOLYBDENUM, 6-8 WEIGHT PERCENTCHROMIUM, 0.02 TO 0.5 WEIGHT PERCENT CARBON, UP TO 1.0 WEIGHT PERCENT OF A BORIDE FORMING ELEMENT SELECTED FROM TITANIUM, ZIRCONIUM, AND HAFNIUM, UP TO 4 WEIGHT PERCENT OF AT LEAST ONE STRENGTHENING AGENT CONSISTING OF TUNGSTEN, TANTALUM, VANADIUM, AND NIOBIUM, AND THE BALANCE NICKEL.

Description

April 27, 1971 H. E. M COY. JR
' NICKEL-BASE ALLOY 3 Sheets-Sheet 1 Filed May 29, 1968 009 o2 OF P 523 S 5 203m o: 32:95 3225 2 m -62. 23 6 s 2 8 6 $223 53 moi m 5 INVENTOR. Herbert E. MECoy, Jr.
ATTORNEY.
H. E. M CQYI JR NICKEL-BASE ALLOY April 27, 1971 3 Sheets-Sheet 2 Filed May 29, 1968 mm: m2; umshmam QMFSEEEZD Q BUFLLOVHJ 1V NIVHlS NOLLVDNO'IB INVENTOR.
Herbert E. MQCoy, Jr.
ATTORNEY.
April 27,-1971 H. E. M COY, JR 3,576,622
v NICKEL-BASE ALLOY Filed May 29, 1968 5 Sheets-Sheet 5 o J J o o o u 1 f E n: I o 0-. E U) o C! 2 m (h m p o w L 0 all) m 0w D f E... oo O. 5 m 2 z 5 S s I :2 U i 3 o h 2 a. E
O E a. E O o o o o o o o o o O an ID r m w (lSd ooon $83818 INVENTOR.
Herbert E. M9 Coy Jr.
ATTORNEY.
United States Patent 3,576,622 NICKEL-BASE ALLOY Herbert E. McCoy, Jr., Oak Ridge, Tenn., assignor to the United States of America as represented by the United States Atomic Energy Commission Filed May 29, 1968, Ser. No. 732,962 Int. Cl. C22c 19/00 U.S. Cl. 75-171 1 Claim ABSTRACT OF THE DISCLOSURE BACKGROUND OF THE INVENTION The invention described herein was made in the course of, or under, a contract with the U.S. Atomic Energy Commission.
The present invention relates to an improved nickelbase alloy. More particularly, it relates to an improvement in the nickel-base alloy known as I-NOR-8 or Hastelloy- N, the composition of which is described in U.S. Pat. No. 2,921,850 as comprising -22 weight percent molybdenum, 6-8 weight percent chromium, 0.02-0.5 Weight percent carbon, and the balance nickel. This alloy was developed to meet a specific need for a material with suflicient high temperature strength that would also resist corrosive attack by molten fluoride salt mixtures. As such it was intended to serve as a fuel carrier and coolant in molten salt reactors of the kind under development by the U.S. Atomic Energy Commission at Oak Ridge, Tenn.
Although it has been shown that INOR-S has suitable properties for long-time use at high temperatures, a deterioration of these properties occurs in a high neutron field. Specifically, it has been found that the alloy is susceptible to a form of high temperature irradiation damage that reduces its creep rupture life. One form of irradiation damage has been attributed to nuclear transmutation involving helium formation, principally from the n,a reaction with boron-10. It has been postulated that the helium collects at the grain boundaries and promotes intergranular cracks. This type of irradiation damage has been found to be general for ironand nickelbase alloys. The addition of small amounts of titanium, zirconium, or hafnium up to about 1.0 weight percent has been found to reduce this form of irradiation damage significantly. Alloy modification of the basic INOR-8 composition designed to alleviate the helium embrittlement problem is the subject matter of U.S. patent application SN. 603,085 of common assignee. Although additions of titanium, zirconium, and hafnium have resulted in improvement, high temperature test data continue to evidence degradation of creep rupture and high temperature ductility. The reduction in those properties has been found to be partic ularly evident in welds made from the alloy where cracking along the line of the weld presents a serious problem. Weld integrity is, of course, essential to the development of the alloy as a nuclear reactor structural material.
In the original concept of the basic INOR-8 alloy, a molybdenum concentration range of 16-18 weight percent Was selected principally because it yielded a desirable solution strengthened phase. Subsequent high temperature strength and ductility studies have now shown that both the basic INOR-8 composition and the additives made to "ice it to accommodate intergranular cracking due to helium SUMMARY OF THE INVENTION The present inventive concept is based on the recognition of the cause and provides a means for reducing the effect of the embrittlement which has been noted even after modifications have been employed to deal with embrittlement due to helium formation. The cause of the persisting embrittling effect is releated to the formation of a secondary, precipitated phase which has been identified by microprobe anaysis as a M C type precipitate where M, in weight percent, represents approximately 55 Mo, 31 Ni, 5 Cr, 5 Si, 4 Fe, and a residuum of other metals and non-metals.
The present invention provides a modification of the basic INOR-S alloy as disclosed in U.S. Pat. No. 2,921,- 850 and modified in U.S. patent application SJN. 603,085 by varying the molybdenum concentration in an amount sufiicient to effectively reduce or eliminate formation of the M C type precipitate as a secondary phase. Specifically, the present invention resides in a nickel-base alloy containing as essential alloying ingredients, in weight percent, 11-13 percent Mo, 6-8 percent Cr, 0.02-0.5 percent carbon, an amount of boride forming element selected from Ti, Zr, and Hf sufiicient to convert incidental amounts of boron to a boride of said selected element, from 0 up to 4 percent of a strengthening agent selected from W, Ta, V, and Nb, the balance being nickel.
BRIEF DESCRIPTION OF THE DRAWINGS The effect of the alloy modification proposed by this invention will be more clearly understood by reference to the accompanying drawings in which:
FIG. 1 shows curves relating strength in creep in a plot of stress vs. rupture time of alloys within the scope of the invention in the unirradiated and irradiated states;
FIG. 2 shows ductility curves in terms of elongation at fracture as a function of rupture time in the irradiated and unirradiated states;
FIG. 3 shows curves of stress vs. rupture time of welds made from alloys within the scope of the invention.
FIGS. 1-3 also include strength and ductility curves of alloys falling outside the scope of the invention which serve as a basis for comparison. Reference in detail to the data shown in these drawings will be made in the ensuing description.
BRIEF DESCRIPTION OF A REPRESENTATIVE EMBODIMENT For the sake of illustration, the invention will be described in comparative terms using as a standard alloy the standard INOR-8 alloy as disclosed in U.S. Pat. No. 2,921,850 and in U.S. patent application S.N. 603.085 as a basis for comparison against a representative improved alloy of this invention. The compositions of the standard and the representative alloys are given in Table I below.
3 Composition of standard INOR-8 alloy, wt. percent Several heats from each alloy composition were made up and tensile specimens were subjected to short-term tensile testing at temperatures ranging from room temperature C.) up to 800 C. The resultsare summarized in Table II below. The strength and tensile values as given in Table 11 represent an average of several tests using several heats. The higher and lower values bracket the range of values obtained under the stated conditions.
4 containing the 10-12 weight percent Mo, which are typical of those within the scope of my invention, show no secondary precipitated phase and do not lose strength in creep after exposure to nuclear irradiation as do the alloys containing 16% Mo, i.e., alloys represented by the standard INOR-8 case.
The upper concentration of M0 in the alloy according to my invention should not exceed 13 weight percent in order to avoid the formation of the M C precipitated phase. Concentrations of M0 in the range 11-13 weight percent provide the optimum Mo concentration in terms of producing an alloy which (1) will not form the persistent M C brittle intergranular secondary phase, (2) will be corrosion resistant to molten fluoride compositions, (3) will make for maximum fabrication ease, and (4) will be weldable. While lower concentrations will be effective to eliminate the M C phase, it will also tend to reduce the other desirable criteria mentioned. Concentrations of iron may vary up to 6% by weight without affecting the advantages achieved by the essential alloying in- TABLE II.COMPARATIVE TENSILE PROPERTIES Standard INOR-S alloy Representative improved alloy Strength, K 5.1. Elonga- Reduction Strength, K s.i.= Elonga- Reduction Temp., tion, in area, tion, in area, C. Yield Tensile percent percent Yield Tensile percent percent 1 The strength and tensile values represent an average of several tests using several heats.
2 K s.i.=thousand pounds/square inch.
From the results shown it will be seen that the improved alloy exhibits somewhat greater ductility, but at the cost of a loss in strength in comparison to the standard INOR-8 alloy (16 weight percent M0). The loss in strength can be made up, however, by adding a solid solution strengthening concentration of at least one metal selected from W, Ta, V, or Nb. The strength in creep at 650 C. for the two alloys is shown in FIG. 2 for the irradiated and non-irradiated case. It is to be noted that the strength of the repersentative alloy of the subject invention (curve C) is unaffected by radiation, whereas there is considerable reduction in strength between the reference INOR8 alloy in the irradiated (curve A) and non-irradiated (curve B) state.
A comparison of ductility in creep between the two alloys in the irradiated and unirradiated state at 650 C.
is shown by the curves of FIG. 2. In the unirradiated state, the ductility of the improved a alloy (curve E) is seen to increase with time at a given stress, while the duotility of the standard INOR-S alloy (curve D) degrades with time. In the irradiated state, the ductility of the irradiate representative improved alloy (curve F) of the present invention is clearly superior to the irradiated standard alloy (curve G).
An examination of the microstructure of several nickelbase alloys within and outside the scope of the present invention shows that the alloys containing 14-16 weight percent Mo show the typical secondary M C phase segregated at the grain boundaries, On the other hand, alloys gredients of my invention. Similarly, the use of minor amounts of such elements as manganese as a malleabilizing element or silicon as a deoxidizer is within the scope of this invention. The significance of the term weldability in the context of this invention is seen from the curves of FIG. 3 which compare the stress rupture properties at 650 C. of welds made with the Ti-modified INOR-S alloy composition as disclosed in US. patent application S.N. 603,085 (curve H) with the stress rupture properties at 650 C. of welds made with the representative improved alloy within the scope of the present invention (curve I).
What is claimed is:
1. An improved nickel-base alloy consisting essentially of 11-13 Weight percent molybdenum, 6-8 weight percent chromium, 0.02 to 0.5 weight percent carbon, an effective concentration of a boride forming element selected from the group consisting of titanium, zirconium, and hafnium sufiicient to react with incidental quantities of boron in the alloy to form a boride of said element, up to 4 weight percent of at least one strengthening agent from the group consisting of tungsten, tantalum, vanadium, and niobium, and the balance nickel.
References Cited UNITED STATES PATENTS 2,921,850 l/l960 Inouye et a1. l 71 RICHARD Q. DEAN, Primary Examiner
US732962A 1968-05-29 1968-05-29 Nickel-base alloy Expired - Lifetime US3576622A (en)

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Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3804680A (en) * 1970-06-06 1974-04-16 Atomic Energy Commission Method for inducing resistance to embrittlement by neutron irradiation and products formed thereby
JP2014145106A (en) * 2013-01-29 2014-08-14 Mmc Superalloy Corp Ni-BASED ALLOY EXCELLENT IN CORROSION RESISTANCE TO FLUORIDE MOLTEN SALTS AS WELL AS DEVICE COMPONENT MADE OF THE SAME
WO2015020799A3 (en) * 2013-08-08 2015-05-21 Holcomb David E Creep-resistant, ni-mo-cr alloys
US9540714B2 (en) 2013-03-15 2017-01-10 Ut-Battelle, Llc High strength alloys for high temperature service in liquid-salt cooled energy systems
US9605565B2 (en) 2014-06-18 2017-03-28 Ut-Battelle, Llc Low-cost Fe—Ni—Cr alloys for high temperature valve applications
US9683280B2 (en) 2014-01-10 2017-06-20 Ut-Battelle, Llc Intermediate strength alloys for high temperature service in liquid-salt cooled energy systems
US9683279B2 (en) 2014-05-15 2017-06-20 Ut-Battelle, Llc Intermediate strength alloys for high temperature service in liquid-salt cooled energy systems
US10017842B2 (en) 2013-08-05 2018-07-10 Ut-Battelle, Llc Creep-resistant, cobalt-containing alloys for high temperature, liquid-salt heat exchanger systems

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3804680A (en) * 1970-06-06 1974-04-16 Atomic Energy Commission Method for inducing resistance to embrittlement by neutron irradiation and products formed thereby
JP2014145106A (en) * 2013-01-29 2014-08-14 Mmc Superalloy Corp Ni-BASED ALLOY EXCELLENT IN CORROSION RESISTANCE TO FLUORIDE MOLTEN SALTS AS WELL AS DEVICE COMPONENT MADE OF THE SAME
US9540714B2 (en) 2013-03-15 2017-01-10 Ut-Battelle, Llc High strength alloys for high temperature service in liquid-salt cooled energy systems
US10017842B2 (en) 2013-08-05 2018-07-10 Ut-Battelle, Llc Creep-resistant, cobalt-containing alloys for high temperature, liquid-salt heat exchanger systems
WO2015020799A3 (en) * 2013-08-08 2015-05-21 Holcomb David E Creep-resistant, ni-mo-cr alloys
US9683280B2 (en) 2014-01-10 2017-06-20 Ut-Battelle, Llc Intermediate strength alloys for high temperature service in liquid-salt cooled energy systems
US9683279B2 (en) 2014-05-15 2017-06-20 Ut-Battelle, Llc Intermediate strength alloys for high temperature service in liquid-salt cooled energy systems
US9605565B2 (en) 2014-06-18 2017-03-28 Ut-Battelle, Llc Low-cost Fe—Ni—Cr alloys for high temperature valve applications
US9752468B2 (en) 2014-06-18 2017-09-05 Ut-Battelle, Llc Low-cost, high-strength Fe—Ni—Cr alloys for high temperature exhaust valve applications

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