反應堆壓力容器鋼韌性評價及韌脆轉變機理的研究進展
Research Progress on Toughness Evaluation and of Ductile-Brittle Transition Mechanism of Reactor Pressure Vessel Steel
摘 要
反應堆壓力容器（RPV）鋼的力學性能評價是核電廠延壽評價的主要內容，其中輻照損傷引起的韌脆轉變溫度上升是影響運行安全和壽命的主要因素。RPV鋼的韌脆轉變評價通過抽取監督試樣進行，但監督試樣的短缺迫使材料工作者采用小試樣和試樣重組等技術研究韌性評價問題。對近年來國內外RPV鋼的韌性評價方法進行了論述，介紹了幾種無損檢測技術在RPV鋼力學性能檢測方面的應用；著重介紹了近3 a來國內外在RPV鋼輻照脆化機理，尤其是強輻照下組織結構演化機理的研究進展，最后對我國RPV鋼韌性評價和相關機理研究進行了展望。
韌脆轉變
析出相
輻照脆化
reactor pressure vessel steel
ductile-brittle transition
precipitate
irradiation embrittlement
Abstract
The evaluation of mechanical performance of reactor pressure vessel (RPV) steel is the main content of the life extension evaluation of nuclear power plants, and the increase of ductile-brittle transition temperature caused by irradiation damage is the main factor affecting operational safety and life. The toughness and brittleness transition evaluation of RPV steel is carried out by drawing surveillance samples, but the shortage of the surveillance samples forces material workers to study the toughness evaluation using small sample and sample reconstitution technique. The toughness evaluation methods of RPV steel at home and abroad in recent years are discussed, and the application of several nondestructive testing techniques on RPV steel mechanical property testing is described. The research progress on the irradiated embrittlement mechanism of RPV steels, especially the microstructure evolution mechanism of RPV steel under the high irradiation condition, in the past three years at home and abroad is described. Finally, the prospect of toughness evaluation and related mechanism research of RPV steel in China is presented.
中圖分類號 TL341 DOI 10.11973/jxgccl202107002
所屬欄目 綜述
基金項目 廣東省基礎與應用基礎研究重大項目（2019B030302011）；廣東省引進創新創業團隊項目（2016ZT06G025）；反應堆燃料及材料重點實驗室穩定支持課題（JCKYS2019201073）
收稿日期 2020/7/8
修改稿日期 2021/5/18
網絡出版日期
作者單位點擊查看
備注饒德林(1965-),男,江西南昌人,副研究員,博士
引用該論文: RAO Delin,MO Jiahao,GAO Jianbo,LI Jun,ZHANG Shuyan. Research Progress on Toughness Evaluation and of Ductile-Brittle Transition Mechanism of Reactor Pressure Vessel Steel[J]. Materials for mechancial engineering, 2021, 45(7): 7～11
饒德林,莫家豪,高建波,李軍,張書彥. 反應堆壓力容器鋼韌性評價及韌脆轉變機理的研究進展[J]. 機械工程材料, 2021, 45(7): 7～11
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參考文獻
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【18】王榮耀,王海濤,劉向兵,等.基于MBN的便攜式RPV鋼輻照脆化檢測系統設計[J].無損檢測,2019, 41(12):12-16. WANG R Y,WANG H T,LIU X B,et al.Design of portable RPV steel irradiation embrittlement detection system based on MBN[J].Nondestructive Testing,2019, 41(12):12-16.
【19】LI C L,SHU G G, LIU W, et al. Effects of neutron irradiation on elastic modulus of RPV steel[J]. Annals of Nuclear Energy, 2019, 134:20-26.
【20】LUO S, WU S J. Effect of dynamic strain aging on the microstructure and mechanical properties of a reactor pressure vessel steel[J]. Materials Science and Engineering:A, 2014, 596:25-31.
【21】李承亮,吳昊,劉飛華,等.反應堆壓力容器鋼質子輻照研究進展[J].中國材料進展,2019, 38(2):138-147. LI C L,WU H,LIU F H,et al.Progress in proton irradiation of reactor pressure vessel steels[J].Materials China,2019, 38(2):138-147.
【22】賀新福,王東杰,賈麗霞,等.反應堆壓力容器鋼中溶質元素空位型擴散機理研究[J].原子能科學技術,2017,51(2):200-208. HE X F,WANG D J,JIA L X, et al. Vacancy-mediated diffusion mechanism of solute element in reactor pressure vessel steel[J]. Atomic Energy Science and Technology, 2017, 51(2):200-208.
【23】BAI X M,KE H B,ZHANG Y F,et al. Modeling copper precipitation hardening and embrittlement in a dilute Fe-0.3at.%Cu alloy under neutron irradiation[J]. Journal of Nuclear Materials,2017, 495:442-454.
【24】CHEN L,NISHIDA K,MURAKAMI K,et al. Effects of solute elements on microstructural evolution in Fe-based alloys during neutron irradiation following thermal ageing[J]. Journal of Nuclear Materials,2018, 498:259-268.
【25】WATANABE H, MASAKI S,MASUBUCHI S,et al. Radiation induced hardening of ion irradiated RPV steels[J]. Journal of Nuclear Materials, 2011, 417:932-935.
【26】LINDGREN K, BOASEN M, STILLER K, et al. Evolution of precipitation in reactor pressure vessel steel welds under neutron irradiation[J]. Journal of Nuclear Materials,2017, 488:222-230.
【27】ALMIRALL N, WELLS P B, YAMAMOTO T, et al. Precipitation and hardening in irradiated low alloy steels with a wide range of Ni and Mn compositions[J]. Acta Materialia, 2019, 179:119-128.
【28】ALMIRALL N, WELLS P B, PAL S, et al. The mechanistic implications of the high temperature, long time thermal stability of nanoscale Mn-Ni-Si precipitates in irradiated reactor pressure vessel steels[J]. Scripta Materialia, 2020, 181:134-139.
【29】ODETTE G R, WIRTH B D. A computational microscopy study of nanostructural evolution inirradiated pressure vessel steels[J]. Journal of Nuclear Marerials, 1997, 251:157-171.
【30】MAMIVAND M, WELLS P, KE H, et al. CuMnNiSi precipitate evolution in irradiated reactor pressure vessel steels:Integrated cluster dynamics and experiments[J]. Acta Materialia, 2019, 180:199-217.
【31】SPROUSTER D J,SINSHEIMER J,DOORYHEE E,et al.Structural characterization of nanoscale intermetallic precipitates in highly neutron irradiated reactor pressure vessel steels[J].Scripta Materialia,2016,113:18-22.
【2】李云良, 張漢謙, 彭碧草, 等. 核電壓力容器用鋼的發展及研究現狀[J].壓力容器,2010, 27(5):36-43. LI Y L,ZHANG H Q,PENG B C,et al. Development and Recent Research of Nuclear Reactor Pressure Vessel Steels[J]. Pressure Vessel Technology,2010, 27(5):36-43.
【3】李今朝,陳亮,黃騰飛,等.關于反應堆壓力容器新型用鋼SA-508Gr.4N的研究進展[J].材料導報,2019, 33(1):382-385. LI J Z,CHEN L,HUANG T F,et al.Research progress on SA-508 Gr.4N pressure vessel steel[J].Materials Review,2019, 33(1):382-385.
【4】林赟,佟振峰,寧廣勝,等.國產A508-3鋼輻照前后小樣品斷裂韌性測試分析[J].核動力工程,2017(增刊1):74-76. LIN Y,TONG Z F,NING G S,et al.Fracture toughness of RPV steel using small specimens after neutron irradiation[J].Nuclear Power Engineering,2017, 38(S1):74-76.
【5】孫凱,馮明全,李國云,等. 反應堆壓力容器材料中子輻照脆化研究[J].核動力工程,2017,38(增刊1):125-128. SUN K, FENG M Q, LI G Y, et al. Assessment of irradiation embrittlement of domestic RPV material[J]. Nuclear Power Engineering, 2017,38(S1):125-128.
【6】XING R S, YU D J, XIE G F, et al. Effect of thermal aging on mechanical properties of a bainitic forging steel for reactor pressure vessel[J]. Materials Science and Engineering:A, 2018, 720:169-175.
【7】鐘巍華,佟振峰,寧廣勝,等.輻照用小尺寸樣品力學性能表征技術研究進展[J].原子能科學技術,2019,53(10):1894-1905. ZHONG W H, TONG Z F, NING G S, et al. Research progress in small specimen test technology for mechanical property of irradiated materials[J]. Atomic Energy Science and Technology, 2019,53(10):1894-1905.
【8】ANDRES D, LACALLE R, CICERO S, et al. Application of the small punch test in combination with the master curve approach for the characterization of the ductile to brittle transition region[J]. Journal of Nuclear Materials, 2019, 518:409-418.
【9】SHARMA T, DURGAPRASAD P V, KUMAR M N,et al. Detection of embrittlement in low alloy steels due to thermal aging by small punch test[J]. Materials Science and Engineering:A,2019,759:181-194.
【10】王成龍,白冰,張長義,等.10×1019 cm-2快中子輻照國產A508-3鋼材料的小沖桿試驗研究[J].原子能科學技術,2020,54(4):683-687. WANG C L,BAI B,ZHANAG C Y,et al. Study on small punch test of China A508-3 steel material irradiated by fast neutron at 10×1019 cm-2[J]. Atomic Energy Science and Technology, 2019, 54(4):683-687.
【11】GUAN K S, WANG D W, DOBROVSKA J, et al. Evaluation of the ductile-brittle transition temperature of anisotropic materials by small punch test with un-notched and U-notched specimens[J]. Theoretical and Applied Fracture Mechanics,2019, 102:98-102.
【12】KIRK M, LUCON E. PWR supplemental surveillance program. Effects of radiation on nuclear materials:26th volume:STP1572[S]. West Conshohocken:ASTM International, 2014.
【13】G AE'G RARD R, CHAOUADI R. Reactor pressure vessel surveillance programs in Belgium[M]//International Review of Nuclear RPV Surveillance Programs. West Conshohocken:ASTM International, 2018:250-275.
【14】SOKOLOV M A, LUCON E. Small specimen test techniques:6th volume:STP1576[S]. West Conshohocken:ASTM International, 2014.
【15】SERVER W L, BRUMOVSKY M. International review of nuclear reactor pressure vessel surveillance programs:STP1603[S]. West Conshohocken:ASTM International, 2018.
【16】KATHRYN H M, JIN-YEON K, JAMES J W, et al. Nonlinear ultrasonic characterization of radiation damage using Charpy impact specimen. Small specimen test techniques:6th Volume:STP1576[S]. West Conshohocken:ASTM International, 2014.
【17】范德良,王志武,袁廷碧.非線性超聲表征HR3C鋼時效過程中析出相的變化[J].金屬熱處理,2020,45(2):242-249. FAN D L,WANG Z W,YUAN T B. Precipitated phase change of HR3C steel during aging characterized by nonlinear ultrasonic technique[J]. Heat Treatment of Metals, 2020, 45(2):242-249.
【18】王榮耀,王海濤,劉向兵,等.基于MBN的便攜式RPV鋼輻照脆化檢測系統設計[J].無損檢測,2019, 41(12):12-16. WANG R Y,WANG H T,LIU X B,et al.Design of portable RPV steel irradiation embrittlement detection system based on MBN[J].Nondestructive Testing,2019, 41(12):12-16.
【19】LI C L,SHU G G, LIU W, et al. Effects of neutron irradiation on elastic modulus of RPV steel[J]. Annals of Nuclear Energy, 2019, 134:20-26.
【20】LUO S, WU S J. Effect of dynamic strain aging on the microstructure and mechanical properties of a reactor pressure vessel steel[J]. Materials Science and Engineering:A, 2014, 596:25-31.
【21】李承亮,吳昊,劉飛華,等.反應堆壓力容器鋼質子輻照研究進展[J].中國材料進展,2019, 38(2):138-147. LI C L,WU H,LIU F H,et al.Progress in proton irradiation of reactor pressure vessel steels[J].Materials China,2019, 38(2):138-147.
【22】賀新福,王東杰,賈麗霞,等.反應堆壓力容器鋼中溶質元素空位型擴散機理研究[J].原子能科學技術,2017,51(2):200-208. HE X F,WANG D J,JIA L X, et al. Vacancy-mediated diffusion mechanism of solute element in reactor pressure vessel steel[J]. Atomic Energy Science and Technology, 2017, 51(2):200-208.
【23】BAI X M,KE H B,ZHANG Y F,et al. Modeling copper precipitation hardening and embrittlement in a dilute Fe-0.3at.%Cu alloy under neutron irradiation[J]. Journal of Nuclear Materials,2017, 495:442-454.
【24】CHEN L,NISHIDA K,MURAKAMI K,et al. Effects of solute elements on microstructural evolution in Fe-based alloys during neutron irradiation following thermal ageing[J]. Journal of Nuclear Materials,2018, 498:259-268.
【25】WATANABE H, MASAKI S,MASUBUCHI S,et al. Radiation induced hardening of ion irradiated RPV steels[J]. Journal of Nuclear Materials, 2011, 417:932-935.
【26】LINDGREN K, BOASEN M, STILLER K, et al. Evolution of precipitation in reactor pressure vessel steel welds under neutron irradiation[J]. Journal of Nuclear Materials,2017, 488:222-230.
【27】ALMIRALL N, WELLS P B, YAMAMOTO T, et al. Precipitation and hardening in irradiated low alloy steels with a wide range of Ni and Mn compositions[J]. Acta Materialia, 2019, 179:119-128.
【28】ALMIRALL N, WELLS P B, PAL S, et al. The mechanistic implications of the high temperature, long time thermal stability of nanoscale Mn-Ni-Si precipitates in irradiated reactor pressure vessel steels[J]. Scripta Materialia, 2020, 181:134-139.
【29】ODETTE G R, WIRTH B D. A computational microscopy study of nanostructural evolution inirradiated pressure vessel steels[J]. Journal of Nuclear Marerials, 1997, 251:157-171.
【30】MAMIVAND M, WELLS P, KE H, et al. CuMnNiSi precipitate evolution in irradiated reactor pressure vessel steels:Integrated cluster dynamics and experiments[J]. Acta Materialia, 2019, 180:199-217.
【31】SPROUSTER D J,SINSHEIMER J,DOORYHEE E,et al.Structural characterization of nanoscale intermetallic precipitates in highly neutron irradiated reactor pressure vessel steels[J].Scripta Materialia,2016,113:18-22.
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