US3261682A - Zirconium alloys containing cerium and yttrium - Google Patents
Zirconium alloys containing cerium and yttrium Download PDFInfo
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- US3261682A US3261682A US236421A US23642162A US3261682A US 3261682 A US3261682 A US 3261682A US 236421 A US236421 A US 236421A US 23642162 A US23642162 A US 23642162A US 3261682 A US3261682 A US 3261682A
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- zirconium
- yttrium
- cerium
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C16/00—Alloys based on zirconium
Definitions
- My invention relates to zirconium alloys and, in a more particular aspect, to alloys suitable as structural material for use in nuclear reactors, such as for the envelopes or cans of nuclear fuel elements.
- Structural materials in the interior of nuclear reactors are required to meet essentially the following four requirements:
- zirconium alloys have been found to be well suitable, particularly in reactors using water as coolant.
- Preferably employed has been the alloy known under the trade name Zircaloy-2 which, aside from zirconium, contains about 1.5% tin, 0.15% iron, 0.1% chromium and 0.05% nickel. (All percentages given in this specification are by weight.)
- These alloying additions counteract the impairment in corrosion resistance of pure zirconium due to contaminating traces of other elements, mainly nitrogen.
- Nuclear reactors equipped with fuel-element cans and structural parts of Zircaloy-2 or Zircaloy-4, the latter being nickel'free Zircaloy-2, can be operated with water temperatures only up to about 350 C. above which the materials are no longer sufficiently corrosion resistant. These temperatures do not afford employing in the reactor plant the improved, modern turbines of increased efficiency, because these turbines would make it desirable to convert to operation with superheated steam at temperatures between 400 and 500 C. and more.
- zirconium-columbium (niobium) alloys with promising improved corrosion resistance in the just-mentioned temperature range as compared with Zircaloy-Z and Zircaloy-4.
- zirconium-base alloy of 0.005 to 1% substance from the group consisting of cerium and yttrium, and one or more of the elements columbium, tin, copper, iron, chromium, nickel, molybdenum, tungsten, vanadium, tantalum and palladium, each in a quantity of up to about 5%, the remainder being substantially all of zirconium, which is understood to include impurities.
- the total amount of the abovementioned addition elements, aside from cerium or yttrium, is less than and preferably less than 5% so that zirconium constitutes more than 90% and preferably more than 95% of the alloy, all percentages stated in this specification being by weight.
- a cerium or yttrium content of 0.01 to 0.5%.
- a favorable alloy composition contains 0.1 to 5%, preferably 0.3 to 2.5% columbium, 0.01 to 0.5% cerium, the remainder being substantially zirconium inclusive of impurities. Also applicable is the same composition if the cerium is substituted by 0.01 to 0.5% yttrium. In both cases the alloy may also contain at least one of the following additions within the stated ranges:
- the increase in corrosion resistance under nuclear-reactor operating conditions achieved by the addition of cerium or yttrium is accompanied by the advantage that these additions do not appreciably increase the absorption cross section for thermal neutrons.
- the absorption cross section of cerium is 0.7 barns/atom. Cerium is the only element from the series of the rare earths having a relatively low absorption cross section.
- the absorption cross section for thermal neutrons in the case of yttrium is 1.38 barns/ atom, which is still rather low.
- the corresponding absorption cross sections for zirconium and columbium are 0.18 and 1.1 barns/ atom respectively.
- cerium or yttrium in the small quantities stated has only a negligible effect upon the absorption cross section of the entire Zr-Cb alloy. It will indeed be seen from the following test results that extremely slight quantities of cerium and yttrium additions suffice to secure the desired results.
- the improved corrosion properties of the alloys according to the invention are exemplified by test results reported in the following tables.
- the zircon alloys investigated were produced from zirconium sponge (reactor grade) and the alloying elements, by melting them together in an electric arc furnace under argon at a pressure of about 200 mm. Hg.
- each alloy was twice remelted.
- the alloy was subjected to cold rolling down to a sheet thickness of 0.8 mm.
- Specimens were produced of about 3 cm. size. These were etched in the usual manner.
- Employed as etching agent was the following composition: 45 volumetric percent HNO (65% concentration)+10 volumetric percent HF (40% concentration) +45 volumetric percent H O.
- specimens 15 and 16 exhibit a considerable increase in weight, indicative of lower resistance to corrosion, in comparison with the corresponding yttrium-containing alloys of Table III. As in the case of the cerium addition, very slight amounts of yttrium may be suflicient for reducing the weight increase down to one-half of its original value.
- a zirconium alloy consisting essentially of 0.1 to 5% columbium, 0.005 to 1.0% cerium, the balance consisting essentially of zirconium.
- a zirconium alloy consisting essentially of 0.3 to 2.5% columbium, 0.01 to 0.5% cerium, the balance consisting essentially of zirconium.
- a zirconium alloy consisting essentially of 0.3 to 2.5% columbium, 0.01 to 0.5% cerium, and at least one addition selected from the group consisting of Percent Sn 0.2 to 1 Cu 0.5 to 1.5 Fe 0.1 to 15 Cr 0.1 to 1.5 Ni 0.1 to 1.5 Mo 0.5 to 1 W 0.5 to 1 V 02 to 1 and the balance consisting essentially of zirconium.
- a zirconium alloy consisting essentially of about 0.5% columbium, about 0.02 to about 0.5% cerium, the balance consisting essentially of zirconium.
- a zirconium alloy consisting essentially of about 1% columbium, about 0.02% cerium, the balance consisting essentially of zirconium.
- a zirconium alloy consisting essentially of 0.1 to 5% columbium, 0.005 to 1.0% yttrium, the balance consisting essentially of zirconium.
- a zirconium alloy consisting essentially of 0.3 to 2.5 columbium, 0.01 to 0.5% yttrium, the balance consisting essentially of zirconium.
- a zirconium alloy consisting essentially of 0.3 to 2.5 columbium, 0.01 to 0.5% yttrium, and at least one addition selected from the group consisting of and the balance consisting essentially of zirconium.
- a zirconium alloy consisting essentially of about 0.5 to about 1% columbium, 0.02 to 0.5% yttrium, the balance consisting essentially of zirconium.
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- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Turbine Rotor Nozzle Sealing (AREA)
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Description
United States Patent 3,261,682 ZIRCONIUM ALLOYS CONTAINING CERIUM AND YTTRIUM Ulrich Rtisler, Erlangen, Germany, assignor to Siemens- Schuckertwerke Aktiengesellschaft, Berlin-Siemensstadt, Germany, a corporation of Germany No Drawing. Filed Nov. 8, 1962, Ser. No. 236,421 Claims priority, application Germany, Sept. 29, 1962,
S 81,837, S 81,838 9 Claims, (Cl. 75-177) My invention relates to zirconium alloys and, in a more particular aspect, to alloys suitable as structural material for use in nuclear reactors, such as for the envelopes or cans of nuclear fuel elements.
Structural materials in the interior of nuclear reactors, particularly canning materials for fuel elements, are required to meet essentially the following four requirements:
(1) Lowest feasible absorption cross section for thermal neutrons,
(2) High corrosion resistance relative to liquid or gaseous reactor coolants,
(3) Sufiicient mechanical strength and ductility, and
(4) Insensitivity to neutron irradiation.
As regards these requirements, zirconium alloys have been found to be well suitable, particularly in reactors using water as coolant. Preferably employed has been the alloy known under the trade name Zircaloy-2 which, aside from zirconium, contains about 1.5% tin, 0.15% iron, 0.1% chromium and 0.05% nickel. (All percentages given in this specification are by weight.) These alloying additions counteract the impairment in corrosion resistance of pure zirconium due to contaminating traces of other elements, mainly nitrogen.
Nuclear reactors equipped with fuel-element cans and structural parts of Zircaloy-2 or Zircaloy-4, the latter being nickel'free Zircaloy-2, can be operated with water temperatures only up to about 350 C. above which the materials are no longer sufficiently corrosion resistant. These temperatures do not afford employing in the reactor plant the improved, modern turbines of increased efficiency, because these turbines would make it desirable to convert to operation with superheated steam at temperatures between 400 and 500 C. and more. Recently there have become known zirconium-columbium (niobium) alloys with promising improved corrosion resistance in the just-mentioned temperature range as compared with Zircaloy-Z and Zircaloy-4.
It is an object of my invention to provide zirconium alloys, preferably for the above-mentioned use in nuclear reactor plants, which aiford achieving a considerably higher corrosion resistance than heretofore attained with the known zirconium-columbium alloys.
I have discovered, and it constitutes an essential feature of my invention, that such improvement in corrosion resistance is achieved by composing a zirconium-base alloy of 0.005 to 1% substance from the group consisting of cerium and yttrium, and one or more of the elements columbium, tin, copper, iron, chromium, nickel, molybdenum, tungsten, vanadium, tantalum and palladium, each in a quantity of up to about 5%, the remainder being substantially all of zirconium, which is understood to include impurities. However, the total amount of the abovementioned addition elements, aside from cerium or yttrium, is less than and preferably less than 5% so that zirconium constitutes more than 90% and preferably more than 95% of the alloy, all percentages stated in this specification being by weight.
I have found it preferable for best results, particularly with respect to structural materials for use in nuclear reactors, to employ a cerium or yttrium content of 0.01 to 0.5%. For example, a favorable alloy composition contains 0.1 to 5%, preferably 0.3 to 2.5% columbium, 0.01 to 0.5% cerium, the remainder being substantially zirconium inclusive of impurities. Also applicable is the same composition if the cerium is substituted by 0.01 to 0.5% yttrium. In both cases the alloy may also contain at least one of the following additions within the stated ranges:
Percent Sn 0.2 to 1 Cu 0.5 to 1.5 Fe 0.1 to 1.5 Cr 0.1 to 1.5 Ni 0.1 to 1.5 Mo 0.5 to 1 W 0.5 to 1 V 0.2 to 1 As mentioned, however, the total amount of such additions should remain below the limits given above. The just-mentioned additions belong to the group of metals known as constituents in zirconium-base alloys. In this respect, reference may be had to the following literature:
R. S. Ambartsumyan et al., Mechanical Properties and Corrosion Resistance of Zirconium and Its Alloys in Water, Steam and Gases at Elevated Temperatures, 2nd Geneva Conference (1958), 15/P/2044.
J. P. Pemsler, The Corrosion of Zirconium Alloys in 900 F. Steam, NMI-1208 (1958).
S, B. Dalgaard, The Corrosion Resistance of Zr-Nb and Zr-Nb-Sn Alloys in High-Temperature Water and Steam, AECL-993 (1960).
I. N. Wanklyn, J. T. Demant and D. Jones, The Cor rosion of Zirconium and Its Alloys by High Temperature Steam. Part I: The Effect of Alloy Composition, AERE- R3655 (1961).
In zirconium-base alloys according to the invention, the increase in corrosion resistance under nuclear-reactor operating conditions achieved by the addition of cerium or yttrium is accompanied by the advantage that these additions do not appreciably increase the absorption cross section for thermal neutrons. The absorption cross section of cerium is 0.7 barns/atom. Cerium is the only element from the series of the rare earths having a relatively low absorption cross section. The absorption cross section for thermal neutrons in the case of yttrium is 1.38 barns/ atom, which is still rather low. The corresponding absorption cross sections for zirconium and columbium are 0.18 and 1.1 barns/ atom respectively. The addition of cerium or yttrium in the small quantities stated has only a negligible effect upon the absorption cross section of the entire Zr-Cb alloy. It will indeed be seen from the following test results that extremely slight quantities of cerium and yttrium additions suffice to secure the desired results.
The improved corrosion properties of the alloys according to the invention are exemplified by test results reported in the following tables. The zircon alloys investigated were produced from zirconium sponge (reactor grade) and the alloying elements, by melting them together in an electric arc furnace under argon at a pressure of about 200 mm. Hg. For securing homogeneous concentration of the alloy, each alloy was twice remelted. The alloy was subjected to cold rolling down to a sheet thickness of 0.8 mm. Specimens were produced of about 3 cm. size. These were etched in the usual manner. Employed as etching agent was the following composition: 45 volumetric percent HNO (65% concentration)+10 volumetric percent HF (40% concentration) +45 volumetric percent H O. Approximately 25 microns thickness were eliminated by etching. The specimens were subjected for 32 days to a steam atmosphere of 500 C. at a pressure of 1 atmosphere absolute. The increase in weight stated in the last column of Table I was determined as a measure of susceptibility to corrosion.
TABLE I Increase in weight, mg/dm.
Ce, No. percent percent Zr Remainder TABLE II Cb, Increase No. percent Zr in weight, mg./dm'
7 0. 5 Remainder 474 8 1. do 731 TABLE III Cb, Y, Increase No. percent percent Zr in weight, mgJdmfl 0. 0. 02 Remainder. 272 0. 5 0.1 do 257 0.5 0.5 do 448 1.0 0.02 do 397 1.0 0.1 do 423 1.0 0.5 do 457 The yttrium-free alloys 15 and 16 according to the following Table IV were simultaneously subjected to the same tests as the alloys 9 to 14 according to Table III.
TABLE IV Cb, Increase N0. percent Zr in weight, rng'ldrn.
15 0.5 Remainder 474 16 1.0 do 731 It will be noted that specimens 15 and 16 exhibit a considerable increase in weight, indicative of lower resistance to corrosion, in comparison with the corresponding yttrium-containing alloys of Table III. As in the case of the cerium addition, very slight amounts of yttrium may be suflicient for reducing the weight increase down to one-half of its original value.
I claim:
1. A zirconium alloy consisting essentially of 0.1 to 5% columbium, 0.005 to 1.0% cerium, the balance consisting essentially of zirconium.
2. A zirconium alloy consisting essentially of 0.3 to 2.5% columbium, 0.01 to 0.5% cerium, the balance consisting essentially of zirconium.
3. A zirconium alloy consisting essentially of 0.3 to 2.5% columbium, 0.01 to 0.5% cerium, and at least one addition selected from the group consisting of Percent Sn 0.2 to 1 Cu 0.5 to 1.5 Fe 0.1 to 15 Cr 0.1 to 1.5 Ni 0.1 to 1.5 Mo 0.5 to 1 W 0.5 to 1 V 02 to 1 and the balance consisting essentially of zirconium.
4. A zirconium alloy consisting essentially of about 0.5% columbium, about 0.02 to about 0.5% cerium, the balance consisting essentially of zirconium.
5. A zirconium alloy consisting essentially of about 1% columbium, about 0.02% cerium, the balance consisting essentially of zirconium.
6. A zirconium alloy consisting essentially of 0.1 to 5% columbium, 0.005 to 1.0% yttrium, the balance consisting essentially of zirconium.
7. A zirconium alloy consisting essentially of 0.3 to 2.5 columbium, 0.01 to 0.5% yttrium, the balance consisting essentially of zirconium.
8. A zirconium alloy consisting essentially of 0.3 to 2.5 columbium, 0.01 to 0.5% yttrium, and at least one addition selected from the group consisting of and the balance consisting essentially of zirconium.
9. A zirconium alloy consisting essentially of about 0.5 to about 1% columbium, 0.02 to 0.5% yttrium, the balance consisting essentially of zirconium.
References Cited by the Examiner UNITED STATES PATENTS 3/1957 Marsh et al. -177 OTHER REFERENCES KAPL2162 Report by Bibb et al. (Nov. 1, 1960, 13
pages).
DAVID L. RECK, Primary Examiner.
WINSTON A. DOUGLAS, Examiner.
W. B. NOLL, W. C. TOWNSEND, P. WEINSTEIN,
Assistant Examiners.
Claims (1)
- 3. A ZIRCONIUM ALLOY CONSISTINGG ESSENTIALLY OF 0.3 TO 2.5% COLUMBIUM, 0.01 TO 0.5% CERIUM, AND AT LEAST ONE ADDITION SELECTED FROM THE GROUP CONSISTING OF
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DES81837A DE1202985B (en) | 1962-09-29 | 1962-09-29 | Zirconium alloy |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US3261682A true US3261682A (en) | 1966-07-19 |
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ID=7509941
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US236421A Expired - Lifetime US3261682A (en) | 1962-09-29 | 1962-11-08 | Zirconium alloys containing cerium and yttrium |
Country Status (3)
| Country | Link |
|---|---|
| US (1) | US3261682A (en) |
| DE (1) | DE1202985B (en) |
| GB (1) | GB1049380A (en) |
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2607141A1 (en) * | 1975-02-25 | 1976-09-02 | Gen Electric | PROCESS FOR HEAT TREATMENT OF OBJECTS MADE OF ZIRCONALIZATION AND DEVICE FOR CARRYING OUT THE PROCESS |
| DE2626941A1 (en) * | 1975-06-26 | 1977-01-20 | Gen Electric | CORROSION-RESISTANT ZIRCONIUM ALLOY COMPONENTS AND PROCESS FOR THEIR PRODUCTION |
| US4197145A (en) * | 1974-12-23 | 1980-04-08 | General Electric Company | Zirconium-base alloy structural component for nuclear reactor and method |
| US4879093A (en) * | 1988-06-10 | 1989-11-07 | Combustion Engineering, Inc. | Ductile irradiated zirconium alloy |
| US5019333A (en) * | 1988-10-26 | 1991-05-28 | Mitsubishi Metal Corporation | Zirconium alloy for use in spacer grids for nuclear reactor fuel claddings |
| US5211774A (en) * | 1991-09-18 | 1993-05-18 | Combustion Engineering, Inc. | Zirconium alloy with superior ductility |
| US5241571A (en) * | 1992-06-30 | 1993-08-31 | Combustion Engineering, Inc. | Corrosion resistant zirconium alloy absorber material |
| US5867552A (en) * | 1995-07-28 | 1999-02-02 | General Electric Company | Zirconium-based two-phase alloys for hydride resistant nuclear reactor components |
| US20080131306A1 (en) * | 2006-12-05 | 2008-06-05 | Korea Atomic Energy Research Institute | Zirconium alloy composition having excellent corrosion resistance for nuclear applications and method of preparing the same |
| US20120201341A1 (en) * | 2011-02-04 | 2012-08-09 | Battelle Energy Alliance, Llc | Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods |
| CN110964946A (en) * | 2019-12-18 | 2020-04-07 | 佛山科学技术学院 | Zirconium alloy |
| US20200157660A1 (en) * | 2017-08-18 | 2020-05-21 | Tokusen Kogyo Co., Ltd | Alloy for biomedical use and medical product |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2642215B1 (en) * | 1989-01-23 | 1992-10-02 | Framatome Sa | PENCIL FOR FUEL ASSEMBLY OF A CORROSION AND WEAR RESISTANT NUCLEAR REACTOR |
| FR2702776B1 (en) * | 1993-03-19 | 1995-04-28 | Commissariat Energie Atomique | Corrosion-resistant zirconium alloys, usable in particular in water reactors. |
| US5475723A (en) * | 1994-03-21 | 1995-12-12 | General Electric Company | Nuclear fuel cladding with hydrogen absorbing inner liner |
| CN113820191B (en) * | 2021-10-19 | 2024-01-19 | 西安西部新锆科技股份有限公司 | High-uniformity zirconium alloy standard substance and preparation method thereof |
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| GB715196A (en) * | 1951-04-17 | 1954-09-08 | Ozalid Co Ltd | Improvements in or relating to the production of photographic images by migratory transfer |
| US2698237A (en) * | 1954-08-16 | 1954-12-28 | Polaroid Corp | Photographic silver halide transfer product and process |
| GB724001A (en) * | 1951-04-30 | 1955-02-16 | Agfa Ag | Photographic light sensitive silver halide emulsions and process using the same |
| US2765240A (en) * | 1953-01-15 | 1956-10-02 | Polaroid Corp | Process for forming print-receiving elements |
| US2784084A (en) * | 1954-07-12 | 1957-03-05 | Jr Lyle L Marsh | Zirconium ternary alloys |
| US2857276A (en) * | 1954-11-23 | 1958-10-21 | Polaroid Corp | Photographic processes and compositions useful therein |
| US2897090A (en) * | 1957-04-11 | 1959-07-28 | Anken Chemical & Film Corp | Heat-sensitive copying paper |
| US3000736A (en) * | 1958-03-31 | 1961-09-19 | Eastman Kodak Co | Photographic silver halide diffusion transfer process |
| US3261683A (en) * | 1960-05-02 | 1966-07-19 | Gen Aniline & Film Corp | Method of preparing transfer copies and compositions for use therein |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1111405B (en) * | 1959-03-04 | 1961-07-20 | Metallgesellschaft Ag | Zirconium alloy |
| GB894156A (en) * | 1960-03-01 | 1962-04-18 | Ass Elect Ind | Improvements relating to zirconium alloys |
-
1962
- 1962-09-29 DE DES81837A patent/DE1202985B/en active Pending
- 1962-11-08 US US236421A patent/US3261682A/en not_active Expired - Lifetime
-
1963
- 1963-08-26 GB GB33771/63A patent/GB1049380A/en not_active Expired
Patent Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2584030A (en) * | 1947-02-07 | 1952-01-29 | Polaroid Corp | Light sensitive silver halide photographic product for image transfer and process utilizing the same |
| US2686717A (en) * | 1949-04-16 | 1954-08-17 | Polaroid Corp | Photographic product comprising a sheet support and means for collecting liquid spread upon said support in excess of that required to cover a predetermined area of the support |
| GB715196A (en) * | 1951-04-17 | 1954-09-08 | Ozalid Co Ltd | Improvements in or relating to the production of photographic images by migratory transfer |
| GB724001A (en) * | 1951-04-30 | 1955-02-16 | Agfa Ag | Photographic light sensitive silver halide emulsions and process using the same |
| US2765240A (en) * | 1953-01-15 | 1956-10-02 | Polaroid Corp | Process for forming print-receiving elements |
| US2784084A (en) * | 1954-07-12 | 1957-03-05 | Jr Lyle L Marsh | Zirconium ternary alloys |
| US2698237A (en) * | 1954-08-16 | 1954-12-28 | Polaroid Corp | Photographic silver halide transfer product and process |
| US2857276A (en) * | 1954-11-23 | 1958-10-21 | Polaroid Corp | Photographic processes and compositions useful therein |
| US2897090A (en) * | 1957-04-11 | 1959-07-28 | Anken Chemical & Film Corp | Heat-sensitive copying paper |
| US3000736A (en) * | 1958-03-31 | 1961-09-19 | Eastman Kodak Co | Photographic silver halide diffusion transfer process |
| US3261683A (en) * | 1960-05-02 | 1966-07-19 | Gen Aniline & Film Corp | Method of preparing transfer copies and compositions for use therein |
Cited By (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4197145A (en) * | 1974-12-23 | 1980-04-08 | General Electric Company | Zirconium-base alloy structural component for nuclear reactor and method |
| DE2607141A1 (en) * | 1975-02-25 | 1976-09-02 | Gen Electric | PROCESS FOR HEAT TREATMENT OF OBJECTS MADE OF ZIRCONALIZATION AND DEVICE FOR CARRYING OUT THE PROCESS |
| DE2626941A1 (en) * | 1975-06-26 | 1977-01-20 | Gen Electric | CORROSION-RESISTANT ZIRCONIUM ALLOY COMPONENTS AND PROCESS FOR THEIR PRODUCTION |
| US4268586A (en) * | 1975-06-26 | 1981-05-19 | General Electric Company | Corrosion resistant zirconium alloy structural components and process |
| US4879093A (en) * | 1988-06-10 | 1989-11-07 | Combustion Engineering, Inc. | Ductile irradiated zirconium alloy |
| US5019333A (en) * | 1988-10-26 | 1991-05-28 | Mitsubishi Metal Corporation | Zirconium alloy for use in spacer grids for nuclear reactor fuel claddings |
| US5211774A (en) * | 1991-09-18 | 1993-05-18 | Combustion Engineering, Inc. | Zirconium alloy with superior ductility |
| US5241571A (en) * | 1992-06-30 | 1993-08-31 | Combustion Engineering, Inc. | Corrosion resistant zirconium alloy absorber material |
| US5867552A (en) * | 1995-07-28 | 1999-02-02 | General Electric Company | Zirconium-based two-phase alloys for hydride resistant nuclear reactor components |
| US20080131306A1 (en) * | 2006-12-05 | 2008-06-05 | Korea Atomic Energy Research Institute | Zirconium alloy composition having excellent corrosion resistance for nuclear applications and method of preparing the same |
| US20120201341A1 (en) * | 2011-02-04 | 2012-08-09 | Battelle Energy Alliance, Llc | Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods |
| US8831166B2 (en) * | 2011-02-04 | 2014-09-09 | Battelle Energy Alliance, Llc | Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods |
| US20200157660A1 (en) * | 2017-08-18 | 2020-05-21 | Tokusen Kogyo Co., Ltd | Alloy for biomedical use and medical product |
| US11692244B2 (en) * | 2017-08-18 | 2023-07-04 | Tokusen Kogyo Co., Ltd. | Alloy for biomedical use and medical product |
| CN110964946A (en) * | 2019-12-18 | 2020-04-07 | 佛山科学技术学院 | Zirconium alloy |
Also Published As
| Publication number | Publication date |
|---|---|
| GB1049380A (en) | 1966-11-23 |
| DE1202985B (en) | 1965-10-14 |
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