Computational Studies of Thermal Hydraulics in a New Integral Reactor Plant VVER-I with Natural Circulation

IF 0.9 Q4 ENERGY & FUELS
M. M. Bedretdinov, O. E. Stepanov, D. N. Moisin, M. A. Bykov
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Abstract

In the present-day conditions under which the nuclear power industry is developed, a need arises to diversify the designs of new nuclear power plant units, which should differ from the previously constructed ones by featuring flexibility to the customer requirements and by using safety systems based on fully passive safety assurance principles. In 2022, specialists of Experimental and Design Organization (OKB) Gidropress commenced activities on elaborating the draft design of a new integral pressurized water-cooled reactor plant VVER-I with natural circulation of coolant for a basic thermal capacity of 250 MW. The design incorporates passive safety systems able to provide reliable heat removal from the core under the conditions of a long-term NPP blackout and without the operator’s participation. The article presents the results obtained from thermal and fluid dynamic computations of the new reactor plant carried out using the KORSAR/GP code that has been certified for safety analyses. A reactor plant thermal-hydraulic model, which can be used for computations of stationary normal operation conditions and, subsequently, also for simulating the accident scenarios evolvement dynamics, has been developed and tested. Computations carried out using the system code have confirmed a correct choice of the reactor’s main geometric parameters and the steam generator’s heat-transfer surface for operation at the nominal power. Based on the computation results for optimizing the design, it is proposed to use a jacketed steam generator, which will make it possible to exclude stray coolant leaks in bypass of the heat-transfer surface. It is shown that the newly developed reactor plant has a significant potential for increasing the thermal power capacity up to 400 MW without introducing fundamental changes in the design. The study results can be used in designing new VVER reactors with natural coolant circulation, and also in the development of passive safety systems.

Abstract Image

Abstract Image

新型自然循环整体式反应堆厂房 VVER-I 的热水力学计算研究
摘要--在当今核电工业发展的条件下,需要使新核电厂机组的设计多样化,这些机组应不同于以前建造的机组,其特点是灵活地满足客户的要求,并采用基于完全被动安全保证原则的安全系统。2022 年,吉德罗普雷斯实验和设计组织(OKB)的专家们开始了新的整体式压水冷却反应堆 VVER-I 的设计草案拟订工作,该反应堆采用自然循环冷却剂,基本热容量为 250 兆瓦。该设计包含被动安全系统,能够在核电厂长期停电的条件下,在运营商不参与的情况下,可靠地从堆芯中排除热量。文章介绍了使用已通过安全分析认证的 KORSAR/GP 代码对新反应堆厂房进行热力和流体动力学计算所获得的结果。已经开发并测试了一个反应堆厂房热工-流体动力学模型,该模型可用于静态正常运行条件下的计算,随后也可用于模拟事故情况下的动态演化。使用系统代码进行的计算证实,在额定功率下运行时,反应堆主要几何参数和蒸汽发生器传热面的选择是正确的。根据计算结果对设计进行了优化,建议使用夹套蒸汽发生器,这样可以避免冷却剂绕过传热面泄漏。研究结果表明,新开发的反应堆厂房在不对设计进行根本性修改的情况下,具有将热功率提高到 400 兆瓦的巨大潜力。研究结果可用于设计采用自然冷却剂循环的新型 VVER 反应堆,也可用于开发被动安全系统。
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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来源期刊
CiteScore
1.30
自引率
20.00%
发文量
94
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