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Simulated transient dynamics and heat transfer characteristics of the water boiler nuclear reactor - SUPO - with cooling coil heat extraction

机译:带有冷却盘管吸热的水锅炉核反应堆SUPO的模拟瞬态动力学和传热特性

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摘要

The term "water boiler" reactor refers to a type of aqueous homogeneous reactor (AHR) that was designed, built and operated by Los Alamos in the 1940s. This was the first type of liquid fuelled reactor and the first to be fuelled with enriched Uranium. For security reasons the term "water boiler" was adopted and three versions were built: LOPO (for low power), HYPO (for high power) and SUPO (for super power) which were spherical shaped reactor vessels. The name was appropriate as the reactors appeared to boil although this was actually due to the release of radiolytic gas bubbles; although SUPO was operated during some studies close to the boiling point of uranyl nitrate. The final water boiler "SUPO" was operated almost daily as a neutron source from 1951 until its deactivation in 1974-23 years of safe, reliable operation. Many of the key neutron measurements needed in the design of the early atomic weapons were made using LOPO, HYPO and SUPO. More recently SUPO has been considered as a benchmark for quasi-steady-state operation of AHRs with internal cooling structures. This paper presents modelling and analysis of the coupled neutronic and fluid time dependent characteristics of the SUPO reactor. In particular the quasi-steady-state dynamics of SUPO have been investigated together with its heat transfer characteristics. In the simulations presented the SUPO reactor is modelled using the spatially dependent neutron/multiphase CFD simulation tool, FETCH, at a quasi-steady-state power of 25 kW. SUPO also possessed a cooling coil system that fed cooling water through the reactor for the extraction of the fission and decay heat. This cooling system, and the heat extraction, is modelled in the simulations using a new sub-modelling approach that is detailed here. The results from this simulation, such as gas fraction, gas generation rate, coolant rate and average temperature, are compared against the available experimental information.
机译:术语“水锅炉”反应器是指一种水均相反应器(AHR),它是由Los Alamos在1940年代设计,建造和运行的。这是第一类液体燃料反应堆,也是第一种以浓缩铀为燃料的反应堆。出于安全原因,采用了“开水器”一词,并建造了三个版本:LOPO(低功率),HYPO(高功率)和SUPO(超级功率),它们是球形反应堆容器。这个名称很恰当,因为反应器似乎沸腾了,尽管这实际上是由于放出了放射性气泡所致。尽管在一些研究中SUPO在接近硝酸铀酰沸点的条件下进行。最终的水锅炉“ SUPO”从1951年开始几乎每天都作为中子运行,直到1974-23年安全可靠的运行被停用。早期原子武器设计所需的许多关键中子测量都是使用LOPO,HYPO和SUPO进行的。最近,SUPO被认为是带有内部冷却结构的AHR准稳态运行的基准。本文介绍了SUPO反应堆中子和流体时间相关耦合特性的建模和分析。特别地,已经研究了SUPO的准稳态动力学及其传热特性。在介绍的仿真中,使用空间相关的中子/多相CFD仿真工具FETCH对SUPO反应堆进行了建模,准稳态功率为25 kW。 SUPO还拥有一个冷却盘管系统,该系统将冷却水通过反应器供入,以提取裂变和衰变热。使用新的子建模方法在此模拟中对该冷却系统和热量提取进行了建模,在此进行详细介绍。将该模拟的结果(例如气体分数,气体产生速率,冷却剂速率和平均温度)与可用的实验信息进行比较。

著录项

  • 来源
    《Annals of nuclear energy》 |2012年第2012期|p.68-83|共16页
  • 作者单位

    Applied Modelling & Computational Group, Department of Earth Science and Engineering, Imperial College London, London, United Kingdom;

    Applied Modelling & Computational Group, Department of Earth Science and Engineering, Imperial College London, London, United Kingdom;

    Applied Modelling & Computational Group, Department of Earth Science and Engineering, Imperial College London, London, United Kingdom;

    Applied Modelling & Computational Group, Department of Earth Science and Engineering, Imperial College London, London, United Kingdom;

    Applied Modelling & Computational Group, Department of Earth Science and Engineering, Imperial College London, London, United Kingdom;

    Applied Modelling & Computational Group, Department of Earth Science and Engineering, Imperial College London, London, United Kingdom;

    Applied Modelling & Computational Group, Department of Earth Science and Engineering, Imperial College London, London, United Kingdom;

    Applied Modelling & Computational Group, Department of Earth Science and Engineering, Imperial College London, London, United Kingdom;

    Babcock and Wilcox Technical Services Group (B&W TSG), 800 Main Street, Lynchburg, VA 24504, USA;

    Babcock and Wilcox Technical Services Group (B&W TSG), 800 Main Street, Lynchburg, VA 24504, USA;

    NNSA Y-12 National Security Complex, Oak Ridge, TN 37831, USA;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    aqueous homogeneous reactor; fluid radiation simulation; reactor simulation; reactor coolant modelling;

    机译:水性均相反应器;流体辐射模拟反应堆模拟反应堆冷却剂建模;

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