首页> 外文会议>ICONE18;International conference on nuclear engineering >QUALIFICATION OF REACTOR PHYSICS TOOLSET FOR A THORIUM-FUELLED CANDU REACTOR
【24h】

QUALIFICATION OF REACTOR PHYSICS TOOLSET FOR A THORIUM-FUELLED CANDU REACTOR

机译:FU燃料坎杜反应器的反应器物理工具的定性

获取原文

摘要

AECL has developed enhanced versions of the reactor physics computer codes for analysis of CANDU® reactors and the ACR-1000 . The central codes that comprise the analysis toolset are WIMS-AECL (a lattice code), RFSP (a core code) and MCNP5 (a Monte Carlo code). The toolset, with ENDF/B- VI nuclear data, has been validated for application to the ACR-1000 design. In addition to comparisons of code predictions against relevant experiments conducted in AECL's ZED-2 critical facility, advanced methods based on cross-section sensitivity/uncertainty (S/U) analysis were used to extend the results of bias and uncertainty in reactivity coefficients, derived from analysis of ZED-2 tests, to the ACR-1000 reactor.The validation of this toolset with ENDF/B-VII nuclear data is proposed for application to analysis of a Thorium-fuelled CANDU Reactor (TCR). The TCR is based on the Enhanced CANDU 6™ (EC6~(TM)) reactor [1] and would operate with a fuel design that incorporates both low-enriched uranium (LEU) oxide and thorium oxide fuel elements in the same fuel bundle to achieve enhanced fuel and core performance with thorium fuel.For the initial TCR toolset qualification, important reactor physics phenomena would be validated using several relevant ZED-2 experiments performed in the past. Results from experiments with a variety of oxide fuels are available,includingplutonium/thorium (Pu/Th), (233)~U/Th, (235)~U/Th, LEU and CANDU-MOX (containing a mixture of plutonium, uranium and dysprosium to simulate the reactor physics affects of fuel burnup). Taken together along with other relevant experimental data, these experiments would be expected to address the important isotopes and many phenomena for the TCR and to enable the validation of the reactor physics toolset for this design. Additional confirmatory experiments would reduce uncertainties.This paper describes the qualification process, including validation, which is proposed to support the use of the reactor physics toolset for the TCR.
机译:AECL开发了反应堆物理计算机代码的增强版本,用于分析CANDU®反应堆和ACR-1000。组成分析工具集的中心代码是WIMS-AECL(晶格代码),RFSP(核心代码)和MCNP5(蒙特卡洛代码)。具有ENDF / BVI核数据的工具集已经过验证,可用于ACR-1000设计。除了将代码预测与在AECL的ZED-2关键设施中进行的相关实验进行比较之外,还使用了基于截面灵敏度/不确定度(S / U)分析的高级方法来扩展反应系数的偏差和不确定性的结果,从ZED-2测试分析到ACR-1000反应堆。 建议使用ENDF / B-VII核数据对该工具集进行验证,以将其用于分析CAN燃料的CANDU反应堆(TCR)。 TCR基于增强型CANDU 6™(EC6〜)反应堆[1],并且将在燃料设计中运行,该燃料设计将低浓铀(LEU)氧化物和氧化or燃料元素合并在同一燃料束中, or燃料可实现增强的燃料和核心性能。 对于最初的TCR工具集鉴定,将使用过去进行的若干相关ZED-2实验来验证重要的反应堆物理现象。提供了多种氧化物燃料的实验结果,包括p / or(Pu / Th),(233)〜U / Th,(235)〜U / Th,LEU和CANDU-MOX(包含p,铀的混合物)和来模拟燃料消耗的反应堆物理影响)。连同其他相关实验数据一起,这些实验将有望解决TCR的重要同位素和许多现象,并使该设计的反应堆物理工具集得以验证。额外的验证性实验将减少不确定性。 本文介绍了包括验证在内的鉴定过程,旨在支持TCR的反应堆物理工具集的使用。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号