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Technology Gap Analysis On Sodium-heated Steam Generators Supporting Advanced Burner Reactor Development

机译：支持先进燃烧器反应堆的钠热蒸汽发生器的技术差距分析

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The goals of the Global Nuclear Energy Partnership (GNEP) are to expand the use of nuclear energy to meet increasing global energy demand in an environmentally sustainable manner, to address nuclear waste management issues without making separated plutonium, and to address nonproliferation concerns. The Advanced Burner Reactor (ABR) is a fast reactor concept that supports the GNEP fuel cycle system. Since the Integral Fast Reactor (IFR) and Advanced Liquid Metal Reactor (ALMR) projects were terminated in 1994, there has been no major development on sodium-cooled fast reactors in the United States. Therefore, in support of the GNEP ABR program, the history of sodium-cooled reactor development was reviewed to support the initiation of this technology within the United States and to gain an understanding of the technology gaps that may still remain for sodium fast reactor technology. A sodium-heated steam generator is one of the key components in the fast reactor system since it provides interface between sodium and water. In this gap analysis, information of fabrication and operation experiences in reactor plant steam generators and prototype steam generators was carefully reviewed, for example the Enrico Fermi Atomic Power Plant, the Prototype Fast Reactor (PFR), and Phenix steam generators; the Babcock & Wilcox helical coil tube, 70 MW; the Westinghouse double-wall tube, 70 MW; the Clinch River Breeder Reactor (CRBR) full-scale evaporator; the Superphenix prototype helical coil tube, 45 MW; the SNR-300 prototype straight tube, 50 MW; the SNR-300 prototype helical coil tube, 50 MW; and the Monju prototype helical coil tube, 50 MW. The results of this evaluation indicate that straight and helical coil tube steam generators are the best immediate candidate designs for producing reliable steam generators for future sodium fast reactor applications. Though the design comparison suggested that the straight tube type has the advantages of compactness and ease of inspection, prototype tests revealed more technical problems than the helical modules. From the viewpoint of tube material, 21/4Cr steel has been well established, and Incoloy~R 800, 9Cr, and 12Cr steels are available as higher-performance materials.
机译：全球核能伙伴关系（GNEP）的目标是扩大核能的使用，以一种环境可持续的方式满足日益增长的全球能源需求，解决核废物管理问题而不分离making，并解决不扩散问题。先进燃烧器反应堆（ABR）是支持GNEP燃料循环系统的快速反应堆概念。自从1994年终止整体快速反应堆（IFR）和高级液态金属反应堆（ALMR）项目以来，美国的钠冷快堆没有重大发展。因此，为支持GNEP ABR计划，对钠冷反应堆的发展历史进行了回顾，以支持该技术在美国的启动，并加深对钠快堆技术仍可能存在的技术差距的了解。钠热蒸汽发生器是快速反应器系统中的关键组件之一，因为它提供了钠和水之间的界面。在这种差距分析中，仔细审查了反应堆工厂蒸汽发生器和原型蒸汽发生器的制造和运行经验信息，例如恩里科·费米原子能发电厂，原型快速反应堆（PFR）和Phenix蒸汽发生器； 70兆瓦的Babcock＆Wilcox螺旋线圈管；西屋双壁管，70兆瓦；克林奇河育种反应堆（CRBR）大型蒸发器； Superphenix原型螺旋线圈管，45 MW； SNR-300原型直管，50 MW； SNR-300原型螺旋线圈管，50 MW；以及50兆瓦的Monju原型螺旋线圈管。评估结果表明，直管螺旋管蒸汽发生器是为将来的钠快堆应用生产可靠的蒸汽发生器的最佳直接候选设计。尽管设计比较表明直管型具有紧凑和易于检查的优点，但是原型测试显示出比螺旋模块更多的技术问题。从管材的角度来看，已经很好地建立了21 / 4Cr钢，可以使用Incoloy〜R 800、9Cr和12Cr作为高性能材料。

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