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Steam generator test facility-A test bed for steam generators of Indian sodium cooled fast breeder reactors

机译:蒸汽发生器试验设施-印度钠冷却快中子增殖堆蒸汽发生器试验台

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摘要

Second stage of India's three stage nuclear power programme consisting of the development and operation of fast breeder reactors (FBRs) commenced with the construction, commissioning and operation of fast breeder test reactor (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam. FBTR operating experience and better understanding of the technologies involved has enabled India to design a 500 MWe prototype fast breeder reactor (PFBR). Construction of PFBR is in advanced stage at Kalpakkam. Steam generator (SG) is one of the critical components of a fast reactor power plant. It is a once-through SG housing both water at high pressure and sodium at low pressure separated by a tube wall. Any defect to this barrier resulting in an internal leak allowing sodium and water to react could severely affect the plant availability. A 5.7 MWt capacity steam generator test facility (SGTF) has been set up in Indira Gandhi Centre for Atomic Research (IGCAR) to test a 5.5 MWt sodium heated once through SG of 19 tubes similar to the indigenously designed 157 MWt, 547 tube SG of PFBR. The test programme includes the evaluation of thermal hydraulic performance of SG, instability mapping, measurement of tube bundle vibrations etc. Most of the planned experiments have been completed successfully. The heat transfer experiment has proved that the SG has a heat transfer area margin of 12.25%. This experiment has also helped in validating the design codes and reducing the area margin for SGs of future FBRs. Experiment on flow induced vibration of tube bundles has shown that the bending stress due to vibration is much less than the endurance limit of the material. The results of the experiments and the valuable lessons learnt from the operating experience have been successfully applied to PFBR and will be applied to future commercial fast breeder reactors. The facility is also planned as a test bed for SGs of Indian FBRs and to assess improved designs of auxiliary equipment used in FBRs. This paper brings out various experiments conducted and the experience gained during the operation of the facility.
机译:印度三阶段核电计划的第二阶段包括快速增殖反应堆(FBR)的开发和运营,首先是在卡尔帕卡姆的英迪拉·甘地原子研究中心(IGCAR)建造,调试和运行快速增殖试验堆(FBTR)。 。 FBTR的运营经验以及对所涉及技术的更好理解使印度得以设计出500 MWe原型快速增殖反应堆(PFBR)。卡尔帕卡姆的PFBR建设处于后期阶段。蒸汽发生器(SG)是快速反应堆电厂的关键组件之一。它是一次过的SG,它容纳高压水和低压钠,并通过管壁隔开。该屏障的任何缺陷都会导致内部泄漏,使钠和水发生反应,可能会严重影响工厂的可用性。已在英迪拉·甘地原子研究中心(IGCAR)建立了容量为5.7 MWt的蒸汽发生器测试设施(SGTF),以测试通过19条管的SG加热一次的5.5 MWt钠,该管与本地设计的157 MWt,547条SG的管类似PFBR。测试程序包括评估SG的热液压性能,不稳定性映射,管束振动的测量等。大多数计划的实验已成功完成。传热实验证明,SG的传热面积裕度为12.25%。该实验还有助于验证设计代码并减少未来FBR的SG的面积裕度。管束的流致振动实验表明,振动引起的弯曲应力远小于材料的承受极限。实验结果和从运行经验中学到的宝贵经验已成功应用于PFBR,并将应用于未来的商用快中子增殖堆。该设施还计划作为印度FBR SG的测试台,并评估FBR中使用的辅助设备的改进设计。本文介绍了该设备运行过程中进行的各种实验以及获得的经验。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2012年第7期|p.169-177|共9页
  • 作者单位

    Fast Reactor Technology Croup, Indira Gandhi Center for Atomic Research, Kalpakkam, India;

    Fast Reactor Technology Croup, Indira Gandhi Center for Atomic Research, Kalpakkam, India;

    Fast Reactor Technology Croup, Indira Gandhi Center for Atomic Research, Kalpakkam, India;

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

  • 入库时间 2022-08-18 00:43:59

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