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Effect of Transverse Neutron Leakage on the Attenuation of the Displacements per Atom in the Reactor Pressure Vessel

机译:横向中子泄漏对反应堆压力容器中每个原子位移衰减的影响

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摘要

The changes in the energy dependence of the neutron removal cross section at the vessel inner wall water/steel interface produce a substantial shift in the neutron spectrum as the fluence propagates into the pressure vessel. To account for this spectral shift, Regulatory Guide 1.99, Revision 2 requires that the fluence used in determining the reference temperature for nil-ductility transition RT_(NDT) be extrapolated from the pressure vessel inner surface using the displacements per atom (dpa). The strong azimuthal and axial variation of the fluence at the vessel inner wall results in a substantial redistribution of the fluence as it propagates through the vessel due to transverse neutron leakage (i.e., perpendicular to the radial direction through the vessel). This transverse leakage tends to increase the dpa radial attenuation in regions of high fluence and reduce the attenuation in regions of low fluence. A series of pressure vessel fluence calculations has been carried out to determine the effect of (a) the transverse neutron leakage and (b) the plant-specific reactor design configuration on the radial attenuation of the dpa through the vessel. The calculations were performed for four operating pressurized water reactors and were carried out using the methods described in U.S. Nuclear Regulatory Commission Regulatory Guide 1.190. The calculations were performed with the DORT discrete ordinates transport code using ENDF/B-Ⅵ neutron transport and dpa cross sections. The transverse leakage is found to introduce a substantial variation of the dpa attenuation rate over the inner surface of the vessel. In the belt-line region opposite the core, the transverse leakage results in an ~6 to 14% azimuthal variation and an ~3 to 11% axial variation in the dpa at a 15-cm depth into the vessel, depending on the plant configuration. In order to simplify the determination of ΔRT_(NDT) in probabilistic fracture mechanics analyses, conservative belt-line and reflector region dpa attenuation rates have been determined. Plant-specific analytic expressions for the radial dependence of the dpa through the vessel have also been determined.
机译:当通量扩散到压力容器中时,容器内壁水/钢界面处中子去除截面的能量依赖性变化会导致中子谱发生明显变化。为了解决这一光谱偏移问题,《管理指南1.99,修订版2》要求使用每原子位移(dpa)从压力容器内表面外推确定零延展性转变RT_(NDT)的参考温度时所使用的注量。由于横向中子泄漏(即,垂直于通过容器的径向方向),当通量在容器内壁上传播时,通量在容器内壁处的强烈的方位角和轴向变化导致通量的实质性重新分布。这种横向泄漏往往会增加高通量区域的dpa径向衰减,并降低低通量区域的衰减。已经进行了一系列压力容器注量计算,以确定(a)横向中子泄漏和(b)特定于工厂的反应堆设计构型对通过容器的dpa径向衰减的影响。计算是针对四个运行中的压水反应堆进行的,并使用美国核监管委员会监管指南1.190中所述的方法进行。计算是使用ENDF /B-Ⅵ中子输运和dpa横截面的DORT离散纵坐标输运代码进行的。发现横向泄漏在容器的内表面上引起dpa衰减率的显着变化。在堆芯对面的带状线区域,横向泄漏导致进入容器15厘米深度时dpa的方位角变化约6%至14%,轴向变化约3至11%,这取决于工厂的配置。为了简化概率断裂力学分析中ΔRT_(NDT)的确定,已经确定了保守的皮带线和反射器区域dpa衰减率。还确定了通过血管的dpa径向依赖性的植物特异性分析表达式。

著录项

  • 来源
    《Nuclear science and engineering》 |2006年第3期|p.256-273|共18页
  • 作者

    John F. Carew; Kai Hu;

  • 作者单位

    Brookhaven National Laboratory, Department of Energy Science and Technology Nuclear Science and Technology Division, P.O. Box 5000, Upton, New York 11973-5000;

  • 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 原子能技术;
  • 关键词

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