GB950163A - Improvements in or relating to uranium/molybdenum alloys - Google Patents
Improvements in or relating to uranium/molybdenum alloysInfo
- Publication number
- GB950163A GB950163A GB27272/62A GB2727262A GB950163A GB 950163 A GB950163 A GB 950163A GB 27272/62 A GB27272/62 A GB 27272/62A GB 2727262 A GB2727262 A GB 2727262A GB 950163 A GB950163 A GB 950163A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- cooling
- heat treatment
- molybdenum
- alloy
- 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
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
- G21C21/16—Manufacture of fuel elements or breeder elements contained in non-active casings by casting or dipping techniques
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C1/00—Making non-ferrous alloys
- C22C1/02—Making non-ferrous alloys by melting
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Manufacturing & Machinery (AREA)
- Dispersion Chemistry (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Crucibles And Fluidized-Bed Furnaces (AREA)
Abstract
A process for preparing a uranium molybdenum alloy (e.g. Mo 0.3-0.6% by weight, balance U) comprises melting the two metals under vacuum in a graphite crucible covered with a reducing cement (e.g. alumina or calcium zirconate), casting the melt and subjecting the bars or tubes so formed to a heat treatment in a molten salt bath followed by a stepped tempering to produce a grain size of 60-80 microns. The heat treatment is carried out at 675-800 DEG C. followed by cooling to 550 DEG C., keeping at this temperature for 15 minutes and then cooling to ambient temperatures at the rate of 20-60 DEG C. per minute. The alloy is stated to be useful as a nuclear reactor fuel element. In the example impurities in the starting materials are as follows: 100 p.p.m. of Al, Fe, Ni, Cr, Mn, 100 p.p.m. Si and 90 p.p.m. C in the uranium and 100 p.p.m. C and 120 p.p.m. metallic impurities in the molybdenum.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR868609A FR1303032A (en) | 1961-07-21 | 1961-07-21 | Uranium-molybdenum alloy and its manufacturing process |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB950163A true GB950163A (en) | 1964-02-19 |
Family
ID=8759768
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB27272/62A Expired GB950163A (en) | 1961-07-21 | 1962-07-16 | Improvements in or relating to uranium/molybdenum alloys |
Country Status (5)
| Country | Link |
|---|---|
| BE (1) | BE620149A (en) |
| ES (1) | ES279336A1 (en) |
| FR (1) | FR1303032A (en) |
| GB (1) | GB950163A (en) |
| LU (1) | LU42071A1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115094351A (en) * | 2022-07-05 | 2022-09-23 | 西安交通大学 | Depleted uranium-based hydrogen absorption and storage alloy and method |
-
0
- BE BE620149D patent/BE620149A/xx unknown
-
1961
- 1961-07-21 FR FR868609A patent/FR1303032A/en not_active Expired
-
1962
- 1962-07-16 GB GB27272/62A patent/GB950163A/en not_active Expired
- 1962-07-16 LU LU42071D patent/LU42071A1/xx unknown
- 1962-07-19 ES ES279336A patent/ES279336A1/en not_active Expired
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115094351A (en) * | 2022-07-05 | 2022-09-23 | 西安交通大学 | Depleted uranium-based hydrogen absorption and storage alloy and method |
| CN115094351B (en) * | 2022-07-05 | 2023-01-24 | 西安交通大学 | Depleted uranium-based hydrogen absorption and storage alloy and method |
Also Published As
| Publication number | Publication date |
|---|---|
| LU42071A1 (en) | 1962-09-17 |
| ES279336A1 (en) | 1963-01-16 |
| BE620149A (en) | |
| FR1303032A (en) | 1962-09-07 |
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