首页> 外文会议>JAERI-Conf 2005-003; Symposium on Nuclear Data; 20041111-12; Tokai(JP) >Comprehensive Study of Lattice Cell Calculations for Thorium Based Fuel Cycle in Light Water Reactors Using SRAC Code
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Comprehensive Study of Lattice Cell Calculations for Thorium Based Fuel Cycle in Light Water Reactors Using SRAC Code

机译:使用SRAC代码对轻水反应堆中基于Based的燃料循环进行晶格计算的综合研究

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The designers of the innovative reactors have proposed a number of approaches to increasing resource efficiency. Adding thorium, a fertile material, to the fuel is considered in this report. Under this approach, a large portion of the reactor output is produced by fissioning of the ~(233)U resulting from neutron capture by thorium, which results in reduced requirements for naturally-occurring fissile uranium (~(235)U). The proliferation potential of the light water reactor fuel cycle may be significantly reduced by utilization of thorium as a fertile component of the nuclear fuel.rnThe concept of using Th-~(233)U as fuel has been applied to an existing LWR design as compare with another fuel cycles (UO2 and MOX). SRAC code is extensive used to investigate the lattice cell problem.
机译:创新型反应堆的设计者提出了许多提高资源效率的方法。本报告中考虑了在燃料中添加th(一种可育材料)。在这种方法下,反应堆输出的大部分是由th中子俘获导致的〜(233)U裂变产生的,这导致对天然裂变铀(〜(235)U)的需求减少。通过使用as作为核燃料的可肥成分,可以大大降低轻水反应堆燃料循环的扩散潜能。相比之下,将Th-〜(233)U用作燃料的概念已经应用于现有的轻水堆设计中。与另一个燃料循环(UO2和MOX)。 SRAC代码广泛用于研究晶格问题。

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