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Theoretical and numerical studies of TWR based on ESFR core design

机译：基于ESFR核心设计的TWR的理论和数值研究

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摘要

This paper deals with the so-called traveling wave reactor (TWR) based on the core design of the European Sodium-cooled Fast Reactor (ESFR). The current concept of TWR is to use the conventional radial fuel shuffling technique to produce a continuous radial fuel movement so that a stationary self sustainable nuclear fission power can be established asymptotically by only loading fertile material consisting of natural or depleted uranium. The core design of ESFR loaded with metallic uranium fuel without considering the control mechanism is used as a practical application example. The theoretical studies focus mainly on qualitative feasibility analyses, i.e. to identify out in general essential parameter dependences of such a kind of reactor. The numerical studies are carried out more specifically on a certain core design. The multi-group deterministic neutronic code ERANOS with the JEFF3.1 data library is applied as a basic tool to perform the neutronics and burn-up calculations. The calculations are performed in a 2-D R-Z geometry, which is sufficient for the current core layout. Numerical results of radial fuel shuffling indicate that the asymptotic k_(eff) parabolically varies with the shuffling period, while the burn-up increases linearly. Typical shuffling periods investigated in this study are in the range of 300-1000 days. The important parameters, e.g. k_(eff), the burn-up, the power peaking factor, and safety coefficients are calculated.
机译：本文基于欧洲钠冷快堆（ESFR）的核心设计，研究了所谓的行波反应堆（TWR）。 TWR的当前概念是使用常规的径向燃料改组技术来产生连续的径向燃料运动，以便仅加载由天然或贫铀组成的肥沃材料就可以渐近地建立固定的，自我可持续的核裂变动力。在不考虑控制机制的情况下，采用金属铀燃料的ESFR核心设计被用作实际应用示例。理论研究主要集中在定性可行性分析上，即一般确定这种反应堆的基本参数依赖性。数值研究是针对特定的核心设计进行的。具有JEFF3.1数据库的多组确定性中子代码ERANOS被用作执行中子学和燃耗计算的基本工具。计算以2-R-Z几何形状进行，这对于当前的磁芯布局已足够。径向燃料改组的数值结果表明，渐进k_（eff）随改组周期呈抛物线变化，而燃耗线性增加。在这项研究中调查的典型改组期为300-1000天。重要参数，例如计算k_（eff），燃尽，功率峰值因数和安全系数。

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  • 来源
    《Energy Conversion & Management》 |2013年第8期|12-18|共7页
  • 作者

    Dalin Zhang; Xue-Nong Chen; Michael Flad; Andrei Rineiski; Werner Maschek;

  • 作者单位

    Institute for Nuclear and Energy Technologies (IKET), Karlsruhe Institute of Technology (KIT), Campus Nord, Hermann-von-Helmholtz-Platz 1,D-76344 Eggenstein-Leopoldshafen, Germany;

    Institute for Nuclear and Energy Technologies (IKET), Karlsruhe Institute of Technology (KIT), Campus Nord, Hermann-von-Helmholtz-Platz 1,D-76344 Eggenstein-Leopoldshafen, Germany;

    Institute for Nuclear and Energy Technologies (IKET), Karlsruhe Institute of Technology (KIT), Campus Nord, Hermann-von-Helmholtz-Platz 1,D-76344 Eggenstein-Leopoldshafen, Germany;

    Institute for Nuclear and Energy Technologies (IKET), Karlsruhe Institute of Technology (KIT), Campus Nord, Hermann-von-Helmholtz-Platz 1,D-76344 Eggenstein-Leopoldshafen, Germany;

    Institute for Nuclear and Energy Technologies (IKET), Karlsruhe Institute of Technology (KIT), Campus Nord, Hermann-von-Helmholtz-Platz 1,D-76344 Eggenstein-Leopoldshafen, Germany;

  • 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

    Traveling wave reactor (TWR); Sodium cooled fast reactor; Burn-up; Radial fuel shuffling;

    机译：行波反应堆（TWR）;钠冷快堆;耗尽了;径向燃料改组;

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