首页> 外文会议>The 3rd China-Canada joint workshop on supercritical water-cooled reactors >SYSTEMATIC APPROACH TO THE DEVELOPMENT OF THE CANADIAN SCWR REACTOR FOR DESIGN OPTIMIZATION
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SYSTEMATIC APPROACH TO THE DEVELOPMENT OF THE CANADIAN SCWR REACTOR FOR DESIGN OPTIMIZATION

机译:用于优化设计的加拿大SCWR反应堆开发的系统方法

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摘要

The Canadian Super-Critical Water-cooled Reactor (SCWR) is a Generation IV reactor that is beingdesigned as part of the international initiative to design next generation nuclear reactors known asthe Generation-IV International Forum (GIF). It is a heavy-water moderated pressure-tube typereactor that uses supercritical water as coolant (which allows ~40% higher thermodynamicefficiency than current light-water reactors), employs passive safety systems, uses an insulated fuelchannel design, and burns thorium as fuel for sustainability and proliferation resistance.The pressure tube design feature provides more flexibility to optimize the reactor efficiency inaddition to enhancing reactor safety in comparison with other reactor designs. The operatingpressure (25 MPa) and temperatures (typically 450?C to 625?C) of SCW reactors are significantlyhigher than those in existing light-water reactors, presenting design challenges that requireinnovative solutions. This paper provides a summary of current status of the mechanical design ofthe Canadian SCWR, discusses some of the design challenges and proposes path forward for futureR&D to deal with these challenges. Also the paper discusses a variety of technologies that may beemployed to achieve optimized reactor efficiency and increased plant reliability.
机译:加拿大超临界水冷堆(SCWR)是第四代反应堆,它是作为设计下一代核反应堆的国际倡议的一部分而设计的,被称为第四代国际论坛(GIF)。它是一种重水缓和压力管式反应器,使用超临界水作为冷却剂(与目前的轻水反应堆相比,具有约40%的热力学效率),采用被动安全系统,采用绝缘燃料通道设计,并燃烧th作为燃料与其他反应堆设计相比,压力管设计功能除了优化反应堆效率外,还提供了更大的灵活性来优化反应堆效率。 SCW反应器的工作压力(25 MPa)和温度(通常为450?C至625?C)明显高于现有的轻水反应堆,从而提出了需要创新解决方案的设计挑战。本文总结了加拿大SCWR机械设计的现状,讨论了一些设计挑战,并提出了未来研发应对这些挑战的途径。本文还讨论了可用于实现优化的反应堆效率和提高电厂可靠性的多种技术。

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