Assessment of the Technical Condition of the Emergency Heat Exchanger for the Reactor Plant of the B-320 Type in Order to Extend Its Service Life

V. Konshin, Mikola Zaiats
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Abstract

Extending the life of nuclear power plants in Ukraine during in the super-project period, as in most countries operating nuclear power units, is an accepted strategy and is being implemented practically. In this regard, there is a need for verification calculation of the main elements The calculated analysis of the stress-strain state of the heat exchanger is carried out using the finite element method of power equipment that determine the resource characteristics. The technical condition of the emergency cooling heat exchanger  for the power unit no. 3 of the SUNPP has been evaluated. The analysis of design, technical and operational documentation in the amount of preliminary evaluation of technical condition was performed. Potential mechanisms of wear of heat exchanger elements were determined. The technique of carrying out verification calculations for static, cyclic and seismic stability was described. The emergency cooling heat exchanger calculation model is made in the APM Structure 3D calculation code. The tense-deformed state of the heat exchanger is calculated using the finite-element method of resampling the design region.  The results of the verification calculation of the emergency cooling heat exchanger in the calculated states corresponding to normal operating conditions, hydrotests and under seismic impacts in conditions of the maximum design earthquake were presented.  The correspondence of the actual stresses in the calculation zones of the heat exchanger to the permissible values, specified in the current regulatory documentation was established. The amount of damageability to the heat exchanger elements was determined for the permissible number of load cycles. The cyclical strength of the elements of the emergency cooling heat exchanger, taking into account the period of application equal to 60 years inclusive, is ensured in accordance with the requirements.
B-320型反应堆装置应急热交换器技术状况评估以延长其使用寿命
在超级项目期间延长乌克兰核电厂的寿命,象大多数运行核动力装置的国家一样,是一项公认的战略,并正在实际执行。对此,需要对主要元件进行校核计算,采用确定资源特性的电力设备有限元法对换热器的应力-应变状态进行计算分析。介绍了1号机组应急冷却换热器的技术条件。对SUNPP中的3个进行了评估。对设计、技术和运行文件进行了分析,对技术条件进行了初步评价。确定了换热器元件磨损的潜在机理。介绍了进行静力、循环和地震稳定性验算的技术。应急冷却换热器的计算模型在APM结构三维计算程序中建立。采用有限元法对设计区域进行重采样,计算了换热器的张变形状态。给出了应急冷却换热器在正常工况、水压试验和最大设计地震条件下的计算状态下的校核计算结果。建立了热交换器计算区内的实际应力与现行法规文件中规定的允许值的对应关系。热交换器元件的易损性是根据允许的负载循环次数来确定的。考虑到使用期限为60年(含60年),应急冷却换热器元件的循环强度符合要求。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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