Prediction of residual life of reactor steels to ensure safe operation of nuclear power plant reactor vessels

机译：反应堆钢材剩余寿命预测，以确保核电厂电抗血管安全运行

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Nuclear power plants are important generating units of the energy system worldwide. In the normal mode, nuclear power plants are absolutely safe, but emergency systems with radiation emissions have a devastating impact on the environment and public health. Despite the introduction of technologies and automatic monitoring systems, the threat of a potentially dangerous situation remains. The reactor vessel is the main object of activities to ensure the safety of nuclear power plants. One of the problems of ensuring the safety of nuclear power plant reactor vessels is the prediction of the level of crack resistance of reactor steels. The paper shows the possibility of estimating the neutron irradiation level on the nature of the temperature dependence of K_(IC). The prediction of the influence of radiation damage on the fracture toughness of the reactor steel can be obtained on the basis of the results of tests of small cylindrical samples with annular notches.

机译：核电站是全球能源系统的重要组织。在正常模式下，核电厂是绝对安全的，但辐射排放的紧急系统对环境和公共卫生产生了破坏性影响。尽管推出了技术和自动监测系统，但仍存在潜在危险情况的威胁。反应堆船是保证核电厂安全的活动的主要目标。确保核电厂反应堆容器安全的问题之一是预测反应器钢的抗裂性水平。本文显示了估计中子辐射水平对K_（IC）的温度依赖性的性质的可能性。可以基于具有环形凹口的小圆柱样品的测试结果获得辐射损伤对反应器钢断裂韧性的影响。

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《International Conference on Construction, Architecture and Technosphere Safety》|2019年|718-1429 p.|共5页
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Y Bakhracheva;
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中图分类工程材料学;
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1. Operation Safety Enhancement of VVER Power Plants Based on Steel Improvement for Reactor Vessels [J] . B. Z. Margolin, G. P. Karzov, I. V. Teplukhina, Inorganic materials: applied research . 2015,第6期

机译：基于反应堆容器钢改进的VVER电厂运行安全性提高
2. APPLICATION OF THE SYSTEM OF AUTOMATED MONITORING OF THE RESIDUAL SERVICE LIFE FOR THE SOLUTION OF THE PROBLEMS OF OPERATION OF NUCLEAR POWER PLANTS WITH WATER-COOLED WATER-MODERATED REACTORS [J] . V. Ya. Berkovich, A. V. Bogachev, B. N. Dranchenko Strength of Materials . 2010,第1期

机译：剩余寿命自动监控系统在解决水冷式水反应堆核电厂运行问题中的应用
3. Using NJOY99 and MCNP4B2 to Estimate the Radiation Damage Displacements per Atom per Second in Steel Within the Boiling Water Reactor Core Shroud and Vessel Wall from Reactor-Grade Mixed-Oxide/Uranium Oxide Fuel for the Nuclear Power Plant at Laguna Verd [J] . Lisa Vickers Nuclear science and engineering . 2003,第3期

机译：使用NJOY99和MCNP4B2估算拉古纳维尔德核电站用反应堆级混合氧化物/铀氧化物燃料在沸水反应堆堆芯导流罩和容器壁内的钢中每原子每秒的辐射损伤位移
4. Prediction of residual life of reactor steels to ensure safe operation of nuclear power plant reactor vessels [C] . Y Bakhracheva International Conference on Construction, Architecture and Technosphere Safety . 2019

机译：反应堆钢材剩余寿命预测，以确保核电厂电抗血管安全运行
5. Estimate of radiation-induced steel embrittlement in the BWR core shroud and vessel wall from reactor-grade MOX/UOX fuel for the nuclear power plant at Laguna Verde, Veracruz, Mexico. [D] . Vickers, Lisa Rene. 2001

机译：墨西哥韦拉克鲁斯州拉古纳维德核电站的反应堆级MOX / UOX燃料估算了BWR堆芯护罩和容器壁中辐射诱发的钢脆性。
6. Detection of alpha particle emitters originating from nuclear fuel inside reactor building of Fukushima Daiichi Nuclear Power Plant [O] . Yuki Morishita, Tatsuo Torii, Hiroshi Usami, -1

机译：在福岛第一核电站反应堆厂房内检测源自核燃料的α粒子发射器
7. RELATIONSHIP BETWEEN RADIATION INDUCTED YIELD STRENGTH INCREMENT AND CHARPY TRANSITION TEMPERATURE SHIFT IN REACTOR PRESSURE VESSEL STEELS OF KOREAN NUCLEAR POWER PLANTS [O] . Gyeong-Geun Lee, Yong-Bok Lee, Jun-Hyun Kwon 2012

机译：韩国核电站反应堆压力容器钢辐射电感屈服强度增量和夏比转变温度变化的关系
8. Reactor Safety Study:An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix VII. Release of Radioactivity in Reactor Accidents. Appendix VIII. Physical Processes in Reactor Meltdown Accidents. Appendix IX. Safety Design Rationale for Nuclear Power Plants. Appendix X. Design Adequacy. [R] . 1976

机译：反应堆安全研究：美国商业核电厂事故风险评估。附录七。反应堆事故中放射性的释放。附录八。反应堆熔毁事故中的物理过程。附录九。核电厂安全设计理念。附录X.设计充分性。

Prediction of residual life of reactor steels to ensure safe operation of nuclear power plant reactor vessels

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