US3615369A - Austenitic stainless steels - Google Patents
Austenitic stainless steels Download PDFInfo
- Publication number
- US3615369A US3615369A US696381A US3615369DA US3615369A US 3615369 A US3615369 A US 3615369A US 696381 A US696381 A US 696381A US 3615369D A US3615369D A US 3615369DA US 3615369 A US3615369 A US 3615369A
- Authority
- US
- United States
- Prior art keywords
- percent
- weight
- austenitic stainless
- alloys
- stainless steel
- 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
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Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
- C22C38/48—Ferrous alloys, e.g. steel alloys containing chromium with nickel with niobium or tantalum
Definitions
- This invention relates to austenitic stainless steels.
- U.S. Pat. specification No. 3,148,973 discloses and claims austenitic stainless steel alloys consisting of essentially less than 0.07 percent carbon, 0.5-l percent manganese, 0.25-0.75 percent silicon, 24-26 percent nickel 19-21 percent chromium, up to 0.75 percent niobium, remainder iron and incidental impurities, the percentages being by weight.
- a third and connected aspect of the problem is to try to avoid or reduce the production of spalled oxides which, as a result of irradiation in a nuclear reactor, have induced radioactivity which is long-lived, for if such oxides should be carried around the coolant circuit and become lodged in some region to which access is required for maintenance purposes (for example heat exchangers in which steam for the power-producing turbines is generated), increasing concentration of oxide having long-lived radioactivity could produce a hazard for personnel required to perform such maintenance.
- Alloys of minimized manganese content in accordance with the invention have been found to have improved oxidation resistance in reactor coolants as compared with alloys as claimed in U.S. Pat. specification No. 3,148,978 having manganese contents in the range 0.5-1 percent by weight.
- FIGS. 11 and 2 of the accompanying drawings are weight gain/time curves obtained from corrosion tests in carbon dioxide at 7,500 C. and 850 C. ofa low-manganesesteel in accordance with the present invention and a standard steel having a manganese content as claimed in U.S. Pat. specification No. 3,148,978.
- the low manganese steel had the following analyzed composition.
- Chromium 20.68 percent by weight Nickel, 24.95 percent by weight Niobium, 0.28 percent by weight Carbon, 0.02 percent by weight Manganese, less than 0.05 percent by weight Silicon, 0.61 percent by weight Balance iron
- the standard steel had the following analyzed composition.
- Chromium percent by weight Nickel, 25.6 percent by weight Niobium, 0.70 percent by weight Carbon, 0.02 percent by weight Manganese, 0.73 percent by weight Silicon, 0.60 percent by weight Balance iron.
- Specimens 2 oxidation of the steels were cold-sheared from strip, degreased and finally electropolished in a sulfuric acidorthophosphoric acid-water (2: l :2) solution. Before oxidation the specimens were vacuum annealed at l,O00 C. for 2 hours. Prepared specimens were oxidized at 750 C. and 850 C. in purified carbon dioxide containing less than 2 v.p.m. of oxygen and 3 r.p.m. of water. Individual weight gain measurements (micrograms per square centimeter) were recorded for specimens of both the steels after oxidation of 0.1,1, l0, and hours at each of the reaction temperatures. Log-log plots of the data obtained are as shown in FIGS. 11 and 2.
- yttrium or gadolinium may be added within the range 0.025-l weight percent.
- Austenitic stainless steel alloys substantially free of ferrite and consisting essentially or less than 0.07 percent carbon, up to 0.1 percent manganese, 0.25-0.75 percent silicon, 24-26 percent nickel 19-21 percent chromium, up to 0.75 percent niobium, remainder iron and incidental impurities, the percentages being by weight.
- Austenitic stainless steel alloys as claimed in claim i having the following upper limits of cobalt and tantalum as incidental impurities, cobalt 0.005 percent by weight, tantalum 0.025 percent by weight.
- Austenitic stainless steel alloys as claimed in claim 2 having the following upper limits of cobalt and tantalum as incidental impurities, cobalt 0.005 percent by weight, tantalum 0.025 percent by weight.
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- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
- Transition And Organic Metals Composition Catalysts For Addition Polymerization (AREA)
- Hard Magnetic Materials (AREA)
- Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
- Treatment Of Steel In Its Molten State (AREA)
- Heat Treatment Of Steel (AREA)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB3750/60A GB905238A (en) | 1960-02-02 | 1960-02-02 | Improvements in or relating to austenitic stainless steels |
| GB2954/67A GB1210064A (en) | 1960-02-02 | 1967-01-19 | Improvements in or relating to austenitic stainless steels |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US3615369A true US3615369A (en) | 1971-10-26 |
Family
ID=9749178
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US696381A Expired - Lifetime US3615369A (en) | 1960-02-02 | 1968-01-08 | Austenitic stainless steels |
Country Status (6)
| Country | Link |
|---|---|
| US (1) | US3615369A (enExample) |
| BE (1) | BE709643A (enExample) |
| DE (1) | DE1608217A1 (enExample) |
| ES (1) | ES349513A2 (enExample) |
| FR (1) | FR94631E (enExample) |
| GB (1) | GB1210064A (enExample) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10643754B2 (en) * | 2016-03-14 | 2020-05-05 | Ultra Safe Nuclear Corporation | Passive reactivity control of nuclear thermal propulsion reactors |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| SE419102C (sv) | 1974-08-26 | 1985-12-23 | Avesta Ab | Anvendning av ett kromnickelstal med austenitisk struktur till konstruktioner som erfordrar hog extrem krypbestendighet vid konstant temperatur upp till 1200?59c |
| TW250567B (enExample) * | 1993-05-13 | 1995-07-01 | Gen Electric |
-
1967
- 1967-01-19 GB GB2954/67A patent/GB1210064A/en not_active Expired
-
1968
- 1968-01-08 US US696381A patent/US3615369A/en not_active Expired - Lifetime
- 1968-01-18 FR FR136569A patent/FR94631E/fr not_active Expired
- 1968-01-18 DE DE19681608217 patent/DE1608217A1/de active Pending
- 1968-01-19 BE BE709643D patent/BE709643A/xx unknown
- 1968-01-19 ES ES349513A patent/ES349513A2/es not_active Expired
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10643754B2 (en) * | 2016-03-14 | 2020-05-05 | Ultra Safe Nuclear Corporation | Passive reactivity control of nuclear thermal propulsion reactors |
| US11417437B2 (en) | 2016-03-14 | 2022-08-16 | Ultra Safe Nuclear Corporation | Variable propellant density for passive reactivity control of nuclear thermal propulsion reactors |
| US12456557B2 (en) | 2016-03-14 | 2025-10-28 | Standard Nuclear, Inc. | Adjusting wait time between burn cycles or merging burn cycles |
Also Published As
| Publication number | Publication date |
|---|---|
| ES349513A2 (es) | 1969-04-01 |
| FR94631E (fr) | 1969-09-19 |
| DE1608217A1 (de) | 1970-12-03 |
| BE709643A (enExample) | 1968-05-30 |
| GB1210064A (en) | 1970-10-28 |
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