CN112941413A - Anti-irradiation nuclear power reactor pressure vessel alloy - Google Patents
Anti-irradiation nuclear power reactor pressure vessel alloy Download PDFInfo
- Publication number
- CN112941413A CN112941413A CN202110135216.9A CN202110135216A CN112941413A CN 112941413 A CN112941413 A CN 112941413A CN 202110135216 A CN202110135216 A CN 202110135216A CN 112941413 A CN112941413 A CN 112941413A
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- China
- Prior art keywords
- pressure vessel
- reactor pressure
- nuclear power
- alloy
- irradiation
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Classifications
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- 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
- C22C38/02—Ferrous alloys, e.g. steel alloys containing silicon
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- 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
- C22C38/04—Ferrous alloys, e.g. steel alloys containing manganese
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- 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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
- G21C13/087—Metallic vessels
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- 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
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- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Pressure Vessels And Lids Thereof (AREA)
Abstract
The invention belongs to the field of nuclear power materials, and particularly relates to an anti-irradiation nuclear power reactor pressure vessel alloy. The alloy comprises the following components in percentage by mass: 0.08 to 0.10 carbon, 0.25 to 0.28 silicon, 0.80 to 0.90 manganese, 0.90 to 0.92 chromium, 0.40 to 0.42 nickel, balance iron, and in addition, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions. Compared with the irradiation performance of the existing commercial nuclear power reactor pressure vessel alloy, the irradiation resistance performance of the nuclear power reactor pressure vessel alloy prepared according to the formula is improved by 12.2-15.3%. The nuclear power reactor pressure vessel alloy has wide application prospect in the nuclear reactor market.
Description
Technical Field
The invention belongs to the field of nuclear power materials, and particularly relates to an anti-irradiation nuclear power reactor pressure vessel alloy.
Background
The reactor pressure vessel is the most important non-replaceable component in the nuclear power station, and in the using process, the reactor pressure vessel needs to bear thermal radiation of about 290 ℃ for a long time and bear neutron radiation for a long time, so that the reactor pressure vessel can be gradually embrittled along with the operation of a reactor, the performance of the reactor pressure vessel is gradually deteriorated, and when the toughness-brittleness transition temperature of the alloy of the reactor pressure vessel rises above a safety value, the reactor pressure vessel has the risk of sudden fracture.
In general, the method of extending the life of a reactor pressure vessel may be summarized as follows: 1. changing alloy components, optimizing or removing certain alloy components (such as phosphorus and sulfur) and improving the radiation resistance; 2. the method is used for annealing the reactor pressure vessel which runs for a long time at a high temperature, so that the defect of performance deterioration caused in the running process of the reactor pressure vessel is reduced or even removed, and the performance of the reactor pressure vessel is partially recovered or even close to the initial performance state of the reactor pressure vessel.
Compared with the second method, the first method is obviously more consistent with the development of the nuclear power reactor pressure vessel alloy, and the finding of the anti-irradiation nuclear power reactor pressure vessel alloy is a difficult task which is currently very important for the health development of the nuclear power industry.
Disclosure of Invention
The invention aims to provide an anti-irradiation nuclear power reactor pressure vessel alloy.
The technical solution for realizing the purpose of the invention is as follows: an anti-irradiation nuclear power reactor pressure vessel alloy comprises the following components in percentage by mass: 0.08 to 0.10 carbon, 0.25 to 0.28 silicon, 0.80 to 0.90 manganese, 0.90 to 0.92 chromium, 0.40 to 0.42 nickel, balance iron, and in addition, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions.
Further, the alloy comprises the following components in percentage by mass: 0.08 carbon, 0.25 silicon, 0.80 manganese, 0.90 chromium, 0.40 nickel, balance iron, and in addition, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions.
Further, the alloy comprises the following components in percentage by mass: 0.10 carbon, 0.28 silicon, 0.90 manganese, 0.92 chromium, 0.42 nickel, balance iron, and, in addition, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions
Compared with the prior art, the invention has the remarkable advantages that:
compared with the irradiation performance of the existing commercial nuclear power reactor pressure vessel alloy, the irradiation resistance performance of the nuclear power reactor pressure vessel alloy prepared according to the formula is improved by 12.2-15.3%.
Detailed Description
An anti-irradiation nuclear power reactor pressure vessel alloy comprises the following components in percentage by mass: 0.08 to 0.10 carbon, 0.25 to 0.28 silicon, 0.80 to 0.90 manganese, 0.90 to 0.92 chromium, 0.40 to 0.42 nickel, balance iron, and in addition, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions.
After optimization, the mass ratio of the components comprises: 0.08 carbon, 0.26 silicon, 0.87 manganese, 0.91 chromium, 0.41 nickel, balance iron, and further, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions
The invention is characterized in that compared with the irradiation performance of the existing commercial nuclear power reactor pressure vessel alloy, the irradiation resistance of the nuclear power reactor pressure vessel alloy prepared according to the formula is improved by 12.2-15.3%. The alloy has wide market prospect in nuclear reactors.
Claims (3)
1. An anti-irradiation nuclear power reactor pressure vessel alloy is characterized in that the alloy comprises the following components in percentage by mass: 0.08 to 0.10 carbon, 0.25 to 0.28 silicon, 0.80 to 0.90 manganese, 0.90 to 0.92 chromium, 0.40 to 0.42 nickel, balance iron, and in addition, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions.
2. The alloy of claim 1, wherein the composition of the alloy composition in mass percent is: 0.08 carbon, 0.25 silicon, 0.80 manganese, 0.90 chromium, 0.40 nickel, balance iron, and, in addition, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions.
3. The alloy of claim 1, wherein the composition of the alloy composition in mass percent is: 0.10 carbon, 0.28 silicon, 0.90 manganese, 0.92 chromium, 0.42 nickel, balance iron, and, in addition, some impurity elements such as copper, phosphorus, etc. may be contained due to metallurgical conditions.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110135216.9A CN112941413A (en) | 2021-02-01 | 2021-02-01 | Anti-irradiation nuclear power reactor pressure vessel alloy |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110135216.9A CN112941413A (en) | 2021-02-01 | 2021-02-01 | Anti-irradiation nuclear power reactor pressure vessel alloy |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN112941413A true CN112941413A (en) | 2021-06-11 |
Family
ID=76240489
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110135216.9A Pending CN112941413A (en) | 2021-02-01 | 2021-02-01 | Anti-irradiation nuclear power reactor pressure vessel alloy |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN112941413A (en) |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ES336995A1 (en) * | 1966-02-21 | 1968-06-01 | United States Steel Corp | Steel resistant to embrittlement by neutron radiation |
| US4183774A (en) * | 1976-04-02 | 1980-01-15 | Commissariat A L'energie Atomique | High-endurance superalloy for use in particular in the nuclear industry |
| JPS5785956A (en) * | 1980-11-14 | 1982-05-28 | Sumitomo Metal Ind Ltd | Structural material of nuclear reactor core used in water-cooled environment |
| US5695716A (en) * | 1993-12-10 | 1997-12-09 | Bayer Aktiengesellschaft | Austenitic alloys and use thereof |
| CN109694988A (en) * | 2017-10-20 | 2019-04-30 | 鞍钢股份有限公司 | A kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel and its manufacturing method |
-
2021
- 2021-02-01 CN CN202110135216.9A patent/CN112941413A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ES336995A1 (en) * | 1966-02-21 | 1968-06-01 | United States Steel Corp | Steel resistant to embrittlement by neutron radiation |
| US4183774A (en) * | 1976-04-02 | 1980-01-15 | Commissariat A L'energie Atomique | High-endurance superalloy for use in particular in the nuclear industry |
| JPS5785956A (en) * | 1980-11-14 | 1982-05-28 | Sumitomo Metal Ind Ltd | Structural material of nuclear reactor core used in water-cooled environment |
| US5695716A (en) * | 1993-12-10 | 1997-12-09 | Bayer Aktiengesellschaft | Austenitic alloys and use thereof |
| CN109694988A (en) * | 2017-10-20 | 2019-04-30 | 鞍钢股份有限公司 | A kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel and its manufacturing method |
Non-Patent Citations (1)
| Title |
|---|
| 刘胜新: "《实用金属材料手册》", 31 August 2011 * |
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| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20210611 |
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| RJ01 | Rejection of invention patent application after publication |