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CN112941413A - Anti-irradiation nuclear power reactor pressure vessel alloy - Google Patents

Anti-irradiation nuclear power reactor pressure vessel alloy Download PDF

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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
Authority
CN
China
Prior art keywords
pressure vessel
reactor pressure
nuclear power
alloy
power reactor
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.)
Pending
Application number
CN202110135216.9A
Other languages
Chinese (zh)
Inventor
沙刚
孔洋
薛飞
薛晶
胡蓉
梅金娜
靳慎豹
柏广海
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nanjing University of Science and Technology
Suzhou Nuclear Power Research Institute Co Ltd
Original Assignee
Nanjing University of Science and Technology
Suzhou Nuclear Power Research Institute Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Nanjing University of Science and Technology, Suzhou Nuclear Power Research Institute Co Ltd filed Critical Nanjing University of Science and Technology
Priority to CN202110135216.9A priority Critical patent/CN112941413A/en
Publication of CN112941413A publication Critical patent/CN112941413A/en
Pending legal-status Critical Current

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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
    • C22C38/02—Ferrous alloys, e.g. steel alloys containing silicon
    • 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
    • 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
    • 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
    • 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

Anti-irradiation nuclear power reactor pressure vessel alloy
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)

1.一种抗辐照核电反应堆压力容器合金，其特征在于，合金成分的质量配比(wt％)包括：0.08-0.10的碳、0.25-0.28的硅、0.80-0.90的锰、0.90-0.92的铬、0.40-0.42的镍、余量的铁，此外，由于冶金条件的限制，会含有些许的杂质元素，例如铜、磷等。1. A radiation-resistant nuclear power reactor pressure vessel alloy, characterized in that the mass ratio (wt%) of the alloy components comprises: 0.08-0.10 carbon, 0.25-0.28 silicon, 0.80-0.90 manganese, 0.90-0.92 In addition, due to the limitation of metallurgical conditions, it will contain some impurity elements, such as copper, phosphorus, etc. 2.根据权利要求1所述的合金，其特征在于，合金成分的组成以质量百分比计为：0.08的碳、0.25的硅、0.80的锰、0.90的铬、0.40的镍、余量的铁，此外，由于冶金条件的限制，会含有些许的杂质元素，例如铜、磷、等。2 . The alloy according to claim 1 , wherein the composition of the alloy components in mass percent is: 0.08 carbon, 0.25 silicon, 0.80 manganese, 0.90 chromium, 0.40 nickel, and the balance iron, 2 . In addition, due to the limitation of metallurgical conditions, it will contain some impurity elements, such as copper, phosphorus, etc. 3.根据权利要求1所述的合金，其特征在于，合金成分的组成以质量百分比计为：0.10的碳、0.28的硅、0.90的锰、0.92的铬、0.42的镍、余量的铁，此外，由于冶金条件的限制，会含有些许的杂质元素，例如铜、磷、等。3. The alloy according to claim 1, characterized in that, the composition of the alloy components in mass percent is: 0.10 carbon, 0.28 silicon, 0.90 manganese, 0.92 chromium, 0.42 nickel, and the balance iron, In addition, due to the limitation of metallurgical conditions, it will contain some impurity elements, such as copper, phosphorus, etc.
CN202110135216.9A 2021-02-01 2021-02-01 Anti-irradiation nuclear power reactor pressure vessel alloy Pending CN112941413A (en)

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)

* Cited by examiner, † Cited by third party
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 Steel for third-generation pressurized water reactor nuclear power station support hanger and manufacturing method thereof

Patent Citations (5)

* Cited by examiner, † Cited by third party
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 Steel for third-generation pressurized water reactor nuclear power station support hanger and manufacturing method thereof

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
刘胜新: "《实用金属材料手册》", 31 August 2011 *

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Application publication date: 20210611