US2990274A - Uranium-titanium-niobium alloys - Google Patents
Uranium-titanium-niobium alloys Download PDFInfo
- Publication number
- US2990274A US2990274A US742446A US74244658A US2990274A US 2990274 A US2990274 A US 2990274A US 742446 A US742446 A US 742446A US 74244658 A US74244658 A US 74244658A US 2990274 A US2990274 A US 2990274A
- Authority
- US
- United States
- Prior art keywords
- uranium
- titanium
- alloy
- niobium
- corrosion
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C43/00—Alloys containing radioactive materials
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/60—Metallic fuel; Intermetallic dispersions
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10S376/00—Induced nuclear reactions: processes, systems, and elements
- Y10S376/90—Particular material or material shapes for fission reactors
- Y10S376/901—Fuel
Definitions
- the present invention is concerned with uranium-base alloys and more particularly relates to uranium-base alloys containing titanium and niobium.
- Uranium is not resistant to corrosion; therefore one object of the present invention is to so improve the properties of uranium and uraniumrich alloys as to enhance the corrosion resistance thereof and render the same useful for various purposes for which uranium and uranium alloys now in use are not satisfactory or eiricient.
- Still another object of this invention is to produce uranium-titanium-niobium alloys, which are useful as fuel elements in nuclear reactors, such as disclosed in U.S. Patent No. 2,708,656 to Fermi et al.
- the present invention is directed to a ternary alloy of uranium, titanium and niobium, particularly one containing from about 2 /2 to 6 wt. percent titanium and about 1 to 2. wt. percent niobium. Our tests indicate that the optimum composition of the alloy for use in a nuclear reactor is about 3 wt. percent titanium and 1 /2 wt. percent niobium.
- Patent No. 2,743,174 it is shown that binary alloys of uranium and titanium are much more resistant to corrosive attack by water than is uranium alone. I have found that the addition of a relatively small amount of niobium to the binary alloy described in the patent improves greatly its resistance to corrosion and that the ternary alloy maintains its integrity many times longer than does an alloy containing no niobium.
- niobium is about 1 /2% niobium, although amounts ranging from 1 to 2% are operative to obtain the results desired.
- the chart also shows that the alloy according to the present invention is much more resistant to corrosion than is the ternary alloy containing 5% zirconium and 1 /2% niobium, which is used in fuel elements for the Experimental Boiling Water Reactor at Argonne National Laboratory. Corrosion of that alloy was about 10 times greater than that of the ternary alloy containing titanium.
- the chart also shows the heat treatment to which each alloy was subjected.
- a comparison between the results shown for the alloy according to my invention with several different heat treatments and the zirconium-containing alloy with about the same heat treatments indicates that my alloy is much less sensitive to heat treatment than is the zirconium-containing alloy.
- This statement also applies to the ternary alloy as compared to the binary alloy.
- These new alloys may be conveniently prepared by melting together the required amounts of uranium, titanium and niobium in a suitable refractory crucible, as for example a graphite crucible. Melting should be in the absence of oxygen or moisture, as for example in v-acuo, and heating may be by inductive heating which facilitates mixing of the metals.
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Dispersion Chemistry (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Description
United States Patent 2,990,274 URANIUM-TITANIUM-NIOBIUM ALLOYS Sherman Greenberg, Chicago, Ill., assignor to the United States of America as represented by the United Slates Atomic Energy Commission No Drawing. Filed June 16, 1958, Ser. No. 742,446 1 Claim. (Cl. 75-122.7)
The present invention is concerned with uranium-base alloys and more particularly relates to uranium-base alloys containing titanium and niobium.
Uranium is not resistant to corrosion; therefore one object of the present invention is to so improve the properties of uranium and uraniumrich alloys as to enhance the corrosion resistance thereof and render the same useful for various purposes for which uranium and uranium alloys now in use are not satisfactory or eiricient.
Still another object of this invention is to produce uranium-titanium-niobium alloys, which are useful as fuel elements in nuclear reactors, such as disclosed in U.S. Patent No. 2,708,656 to Fermi et al.
Other objects and advantages of the present invention will be apparent from the following description, taken in connection with the appended claim.
The present invention is directed to a ternary alloy of uranium, titanium and niobium, particularly one containing from about 2 /2 to 6 wt. percent titanium and about 1 to 2. wt. percent niobium. Our tests indicate that the optimum composition of the alloy for use in a nuclear reactor is about 3 wt. percent titanium and 1 /2 wt. percent niobium.
In Patent No. 2,743,174 it is shown that binary alloys of uranium and titanium are much more resistant to corrosive attack by water than is uranium alone. I have found that the addition of a relatively small amount of niobium to the binary alloy described in the patent improves greatly its resistance to corrosion and that the ternary alloy maintains its integrity many times longer than does an alloy containing no niobium.
The following chart illustrates the advantages obtained by the new alloys.
after an relapse of at least twice the time in which the binary alloy failed.
It is believed that the samples of ternary alloy remain intact because the niobium acted to prevent damage by corrosion product hydrogen, thereby preventing formation of cracks.
Below about 2 /2% titanium the alloy has appreciably poorer corrosion resistance than with a higher amount. Above 6% titanium the corrosion resistance is probably satisfactory, but the alloy becomes brittle and therefore unsuitable for use in a reactor. Optimum percentage of niobium is about 1 /2% niobium, although amounts ranging from 1 to 2% are operative to obtain the results desired.
The chart also shows that the alloy according to the present invention is much more resistant to corrosion than is the ternary alloy containing 5% zirconium and 1 /2% niobium, which is used in fuel elements for the Experimental Boiling Water Reactor at Argonne National Laboratory. Corrosion of that alloy was about 10 times greater than that of the ternary alloy containing titanium.
The chart also shows the heat treatment to which each alloy was subjected. A comparison between the results shown for the alloy according to my invention with several different heat treatments and the zirconium-containing alloy with about the same heat treatments indicates that my alloy is much less sensitive to heat treatment than is the zirconium-containing alloy. This statement also applies to the ternary alloy as compared to the binary alloy.
These new alloys may be conveniently prepared by melting together the required amounts of uranium, titanium and niobium in a suitable refractory crucible, as for example a graphite crucible. Melting should be in the absence of oxygen or moisture, as for example in v-acuo, and heating may be by inductive heating which facilitates mixing of the metals.
It will be understood that this invention is not to be limited to the details given herein, but that it may be modified within the scope of the appended claim.
What is claimed is:
An alloy which is resistant to corrosion by water at Temp., 1 Corrosion Composition 0. Time rate. mg./ Remarks cmfl/day U- 3% Ti 1 260 Sample failed in 10 to 20 Sample failed by cracking.
l-2 wee s. U3% Ti 2 260 Sample broken into several pieces. U%% Ti-1%% Nb 1 150 In view of result, no test was made at 260 C. 150 15.7 days 0 I I LT-3% Til} Nb 1 260 Tests continuing 1 Sample in excellent condition at after 40 days. this time. U-3% Tl-1%% Nb 2 260 Tests continuing 1 Do.
after 5 days. U3% Ti- 136% Nb 5 260 Tests continuing 10 Sample in excellent condition.
after 22 days. 150 10.4 days 0 U6% Tl1%% Nb 1 260 1.7 days 80 Test sample was beginning to crack when test was discontinued. U5% Zr1%% Nb 1 200 One month 10 to 15 sampletihcrnmbling after about one mon U5% Zr-l%% Nb 2 260 Two months 6 Cracking atnld chipping after about one mon U5% Zr1} Nb 4 260 Up to 14 days"..- 17-30 Clifikillg develops in from 5 to 14 ays.
1 Quenched from 1000 C.
1 Quenched from 1000 0.; aged 400 C.2 hours. quenched from 750 C.
4 Quenched from 725-750 0.
260 C. containing 3 weight percent titanium and 1 /2 weight percent niobium, the remainder being uranium, which alloy has been quenched from a temperature from 750 C. to 1000" C.
(References on following page) A comparison between the results shown for the binary alloy and the 3% titanium ternary alloy at 260 C. indicates at once the great advantage of the ternary alloy. The corrosion rate is reduced to a tenth of that of the binary alloy and the sample is still in good condition 2,990,274 3 V 4 References Cited in the file of this patent OTHER REFERENCES UNI BMI-971 Corrosion Evaluation of Binary Uranium A1- TED STATES PATENTS loys in Water at 100 C., U.S. AEC, Oak Ridge, Tenn.,
2,743,174 Keeler et at 24, 1956 December 1954, pages 17-20. (Copy in Scientific Li- 2,888,343 McGeary et a1 May 26, 1959 5 bury) WAPD-PWR-PMM-601, Document pu-bl. by Atomic FOREIGN PATENTS Energy Comm., February 1, 1956, page 10. Copy in 537,159 Canada Feb. 12, 1957 I 75/122.7.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US742446A US2990274A (en) | 1958-06-16 | 1958-06-16 | Uranium-titanium-niobium alloys |
FR796856A FR1226385A (en) | 1958-06-16 | 1959-06-08 | Ternary uranium alloy |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US742446A US2990274A (en) | 1958-06-16 | 1958-06-16 | Uranium-titanium-niobium alloys |
Publications (1)
Publication Number | Publication Date |
---|---|
US2990274A true US2990274A (en) | 1961-06-27 |
Family
ID=24984875
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US742446A Expired - Lifetime US2990274A (en) | 1958-06-16 | 1958-06-16 | Uranium-titanium-niobium alloys |
Country Status (2)
Country | Link |
---|---|
US (1) | US2990274A (en) |
FR (1) | FR1226385A (en) |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3109730A (en) * | 1961-09-19 | 1963-11-05 | Sylvester T Zegler | Ductile uranium fuel for nuclear reactors and method of making |
US3266890A (en) * | 1964-03-23 | 1966-08-16 | Greenspan Jacob | Structural, high strength uranium alloys |
US3969160A (en) * | 1975-06-03 | 1976-07-13 | The United States Of America As Represented By The United States Energy Research And Development Administration | High-strength ductile uranium alloy |
US4935200A (en) * | 1989-06-26 | 1990-06-19 | Allied-Signal Inc. | High density, high strength uranium-titanium-hafnium alloys |
FR2777688A1 (en) * | 1998-04-17 | 1999-10-22 | Korea Atomic Energy Res | Nuclear dispersion fuel production using uranium alloy powders |
US6726876B1 (en) * | 2002-12-27 | 2004-04-27 | The United States Of America As Represented By The Secretary Of The Army | Stakalloy: a uranium-vanadium-niobium alloy |
US11456083B2 (en) * | 2017-05-12 | 2022-09-27 | Westinghouse Electric Sweden Ab | Nuclear fuel pellet, a fuel rod, and a fuel assembly |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2743174A (en) * | 1946-04-25 | 1956-04-24 | John R Keeler | Uranium-titanium alloys |
CA537159A (en) * | 1957-02-12 | Imperial Chemical Industries Limited | Uranium alloys | |
US2888343A (en) * | 1955-10-11 | 1959-05-26 | Westinghouse Electric Corp | Alloys and members produced therefrom |
-
1958
- 1958-06-16 US US742446A patent/US2990274A/en not_active Expired - Lifetime
-
1959
- 1959-06-08 FR FR796856A patent/FR1226385A/en not_active Expired
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CA537159A (en) * | 1957-02-12 | Imperial Chemical Industries Limited | Uranium alloys | |
US2743174A (en) * | 1946-04-25 | 1956-04-24 | John R Keeler | Uranium-titanium alloys |
US2888343A (en) * | 1955-10-11 | 1959-05-26 | Westinghouse Electric Corp | Alloys and members produced therefrom |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3109730A (en) * | 1961-09-19 | 1963-11-05 | Sylvester T Zegler | Ductile uranium fuel for nuclear reactors and method of making |
US3266890A (en) * | 1964-03-23 | 1966-08-16 | Greenspan Jacob | Structural, high strength uranium alloys |
US3969160A (en) * | 1975-06-03 | 1976-07-13 | The United States Of America As Represented By The United States Energy Research And Development Administration | High-strength ductile uranium alloy |
US4935200A (en) * | 1989-06-26 | 1990-06-19 | Allied-Signal Inc. | High density, high strength uranium-titanium-hafnium alloys |
FR2777688A1 (en) * | 1998-04-17 | 1999-10-22 | Korea Atomic Energy Res | Nuclear dispersion fuel production using uranium alloy powders |
US6726876B1 (en) * | 2002-12-27 | 2004-04-27 | The United States Of America As Represented By The Secretary Of The Army | Stakalloy: a uranium-vanadium-niobium alloy |
US11456083B2 (en) * | 2017-05-12 | 2022-09-27 | Westinghouse Electric Sweden Ab | Nuclear fuel pellet, a fuel rod, and a fuel assembly |
Also Published As
Publication number | Publication date |
---|---|
FR1226385A (en) | 1960-07-11 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
KR100205917B1 (en) | Zirlo material for light water reactor applications | |
US3963534A (en) | Zirconium alloys | |
US4879093A (en) | Ductile irradiated zirconium alloy | |
US5080861A (en) | Corrosion resistant zirconium alloy | |
JP2008163465A (en) | Zirconium-based alloy resistant against creep and against corrosion by water and steam, manufacturing process, and use in nuclear reactor | |
US5278882A (en) | Zirconium alloy with superior corrosion resistance | |
US4963323A (en) | Highly corrosion-resistant zirconium alloy for use as nuclear reactor fuel cladding material | |
EP0196286B1 (en) | Method of manufacturing tubes of zirconium alloys with improved corrosion resistance for thermal nuclear reactors | |
US2990274A (en) | Uranium-titanium-niobium alloys | |
US5196163A (en) | Highly corrosion-resistant zirconium alloy for use as nuclear reactor fuel cladding material | |
US3347715A (en) | Heat treatment of steel | |
US3563728A (en) | Austenitic stainless steels for use in nuclear reactors | |
JPH07116575B2 (en) | Heat treatment of alloy 718 for improving stress corrosion cracking resistance | |
US2830896A (en) | Uranium alloys | |
US4863685A (en) | Corrosion resistant zirconium alloys | |
JPH0660364B2 (en) | Corrosion resistant zirconium alloy containing bismuth | |
Gilbert et al. | Dislocation structure in neutron irradiated zircaloy | |
US5122334A (en) | Zirconium-gallium alloy and structural components made thereof for use in nuclear reactors | |
US3431104A (en) | Zirconium base alloy | |
EP0514118A1 (en) | Austenitic stainless steel with extra low nitrogen and boron content to mitigate irradiation-assisted stress corrosion cracking | |
JPH01188643A (en) | Zr alloy for covering tube of atomic reactor fuel having excellent corrosion resistance | |
Gardner | MECHANICAL PROPERTIES. | |
JP2675297B2 (en) | Corrosion resistant zirconium alloy | |
JPH0483838A (en) | Zirconium alloy for constituting member of nuclear fuel aggregate | |
Bentley et al. | Stable phases in aged type 321 stainless steel |