首页> 外文期刊>Kerntechnik >Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies
【24h】

Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies

机译:两种不同构造类型的组件的VVER 1000有源铁芯的比较热工液压分析

获取原文
获取原文并翻译 | 示例
           

摘要

The OECD/NEA Benchmark on NPP Kalinin Unit 3 "Switch-ing-off of one of the four operating main circulation pumps at nominal power" based on measurements is at its end phase. A new benchmark is starting based on measurements from the NPP Rostov Unit 2 "Reactivity compensation with diluted boron by stepwise insertion of control rod cluster into the WER-1000 core". The Rostov-2 core is loaded with assemblies of a new modern type "TVS-2M" which differs in construction in comparison with the "TVSA"-type implemented in the Kali-nin-3 core. The goal of the performed study is to determine the thermohydraulic differences, during steady-state operation, between the two cores based on loads with different assembly types. Results of steady-state simulations are compared for Ka-linin-3 and Rostov-2 cores, taken from the respective Benchmarks specifications. To ensure that the observed differences are coming only from the fuel assembly construction, the same axial power density is used for all cases. Calculations are done with an under-development version of the GRS system code ATHLET, which has sub-channel modeling capabilities. Thus, in addition to the typical assembly-wise models, calculations with seven assemblies modeled at the sub-channel (pin-by-pin) level were also performed and analyzed. This work will help the Benchmarks' Rostov-2 participants to set up more accurate core thermohydraulic models.
机译:经合组织/核能机构关于核电厂加里宁3号机组的基准测试“以额定功率关闭四个运行中的主循环泵之一”处于测量的最后阶段。基于NPP罗斯托夫装置2“通过将控制棒簇逐步插入WER-1000堆芯,用稀释的硼进行反应性补偿”的测量结果开始了新的基准。罗斯托夫2型核装载了新型现代型“ TVS-2M”的组件,该组件与在卡利nin-3型核中实现的“ TVSA”型相比结构有所不同。进行研究的目的是根据组装类型不同的负载,确定稳态运行期间两个铁心之间的热工液压差。比较了各自基准规格中的Ka-linin-3和Rostov-2磁芯的稳态仿真结果。为了确保观察到的差异仅来自燃料组件的结构,在所有情况下均使用相同的轴向功率密度。使用具有子通道建模功能的GRS系统代码ATHLET的未开发版本进行计算。因此,除了典型的装配方式模型外,还执行并分析了在子通道(逐针)级别建模的七个装配体的计算。这项工作将帮助Benchmarks的Rostov-2参与者建立更准确的核心热工水力模型。

著录项

  • 来源
    《Kerntechnik》 |2019年第4期|316-321|共6页
  • 作者单位

    Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH Boltzmannstraße 14 Garching Germany;

    National Research Nuclear University MEPhI Moscow Russia;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号