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PWR失水事故工况下燃料包壳与水蒸汽反应研究 被引量:5

STUDY OF FUEL CLADDING-STEAM REACTION UNDER A LOSS OF COOLANT-ACCIDENT (LOCA)
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摘要 文章描述PWR失水事故工况下燃料包壳与水蒸汽的氧化反应行为。国产Zr-4包壳管在900-1500℃流动水蒸汽中的等温反应速率在1000℃以上遵循抛物线规律,ZrO_2层、α-Zr(O)层和ZrO_2+α-Zr(O)层的成长在此温度以上也遵循抛物线规律,其速率常数分别为:K,(O_2)=4.98 ×10~5exp(-20907/T),mg^2·cm^4·s^(-1);K,(ZrO_2)=0.0104exp(-17592/T),cm^2·s^(-1);K,(α-Zr(O))=0.6407exp(-23207/T),cm^2·s^(-1);K,(ξ)=0.3025exp(-20194/T),cm^2·s^(-1)。高温水中形成的氧化膜使1100℃以下的锆合金与水蒸汽的反应速率降低,不同表面处理和热处理对其影响极小。Zr-2和Zr-4在高温水中的氧化速率无明显差异,Zr-2.5Nb抗高温水蒸汽的氧化能力优于Zr-2和Zr-4。Zr-4合金在高温水蒸汽中的氧化增重超过35mg·cm^(-2)时,氧化膜易出现剥落和破裂。 The isothermal reaction rate of domestic Zircaloy--4 in flowing steam is measured in the temperaurerange of 900--1500℃. The reaction rate measured from the weight gain of the sample follows theparabolic law above 1000℃, the growth rates of ZrO_2 layer, oxygen--stablized alpha phase α--Zr (O)layer and ZrO_2 + α--Zr (O)layer are also parabolic above 1000℃. The parabolic rate constants are K_p(O_2) = 4.98×10~5exp(--20907/ T ), mg^2·cm^(-4)·s^(-1); K_p (ZrO_2) = 0. 0104 exp(--17592/ T ),cm^2·s^(-1); K_p(α--Zr (O) ) = 0.6407exp(--23207/ T ),cm^2·s^(-1); K_p(ξ) = 0. 3025exp(--20194/ T), cm^2·s^(-1). The oxide film produced in high temperature water decreases Zircaloy--steam reaction ratesat 1100℃ or less. Different surface treatments(pickling and polishing)and different heat treatments (αannealing and β quenching) have small or neglible effects. Oxidation rates of Zircaloy--2 and Zircaloy--4in high temperature steam haven't distinct difference, but the high tempetature steam oxidation resis-tance of Zr--2.5Nb is superior to that of Zircaloy--4 and Zircaloy--2. It is found that when the oxideweight gain of Zircaloy--4 in high tempetature steam in larger than 35mg·cm^(-2), the oxide film easilyseperates and spalls.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 1993年第4期376-382,共7页 Atomic Energy Science and Technology
基金 国家核安全局"七五"期间核安全技术研究计划中的一个专题
关键词 水蒸汽 燃料包壳 反应 冷却剂丧失 Zricaloy-4 Steam Reaction kintics Oxidation rate Layer thickness
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同被引文献39

  • 1张文宪.系统工程及其应用[J].航空系统工程,1995(3):2-8. 被引量:2
  • 2黄玉才,张述诚,尚成宇,高永光,陈立霞,阮於珍,张培生,吕路生.压水堆燃料棒锆-4包壳在大破口LOCA条件下的鼓胀爆破实验[J].核科学与工程,1997,17(1):45-51. 被引量:6
  • 3Hobson D O, et al. Embitterment of zircaloy clad fuel rods by steam during LOCA transients[R]. 1972,ORNL-4758.
  • 4Louis Baker Jr, Louis C Just. Studies of metal-water reaction at high temperatures experimental and theoretical studies of the zirconium-water reaction[M]. 1962, ANL-6548: 7.
  • 5Cathcart J V, Pawel R E, Mckke R A, et al. Zirconium metal-water oxidation kinetics IV reactor rate studies[M]. ORNL/NUREC, 1977: 1.
  • 6Leistikow S, Schanz G, Gerg H V. Kinetics and morphology of isothermal steam oxidation of Zircaloy-4 at 700 1300℃[R]. KFK report-2587,March 1978.
  • 7Fedotov P V, Salatov A V, Nechaeva O A, et al. The substantiation of embrittlement criterion of E110 alloy under LOCA conditions [C]// 8tb international conference on WWER performance modeling and experimental support. Helena Resort near Burgas, Bulgaria, 2009.
  • 8Vrtilkovd V, Novotny L, et al. Practical illustration of the traditional vers. alternative LOCA embitterment criteria [C]// Proceedings of the international conference nuclear energy for new europe. Bled, Slovenia, 2005.
  • 9Bibilashvili Yu K, Sokolov L N, et al. Thermomechanical property of zirconium-based alloys oxidation in LOCA simulating condition, cladding properties after high temperature oxidation[C]//Session 3(M). France,2002.
  • 10Hache G, Chung H M. The history of LOCA embrittlement criterion[C]// 28th water reactor safety information meeting. Bethesda,2000.

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