The effect of material homogenization in calculating the gamma-ray dose from spent PWR fuel pins in an air medium

Trumbull TH; Harris DR

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The effect of material homogenization in calculating the gamma-ray dose from spent PWR fuel pins in an air medium

机译：在空气介质中，材料均质化对用过的PWR燃料销产生的伽马射线剂量的影响

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The effect of material homogenization on the calculated gamma-ray dose rate was studied for several arrangements of typical pressurized water reactor (PWR) spent fuel pins in an air medium using the Monte Carlo code MCNP. The models analyzed increased in geometric complexity, beginning with a single fuel pin; progressing to small lattices, i.e., 3 X 3, 5 X 5, and 7 X 7 fuel pins; and culminating with a full 17 X 17 pin PWR bundle analysis. The fuel pin dimensions and compositions were taken directly from a previous study, and efforts were made to parallel this study by specifying identical flux-to-dose functions and gamma-ray source spectra.

机译：使用蒙特卡罗代码MCNP，研究了空气介质中典型压水堆（PWR）用过的燃料销的几种布置方式，研究了材料均质化对计算的伽马射线剂量率的影响。从单个燃料销开始，分析的模型的几何复杂性增加；逐渐发展为较小的格子，即3 X 3、5 X 5和7 X 7燃料销；并以完整的17 X 17引脚PWR封装分析达到高潮。燃料销的尺寸和成分直接取自先前的研究，并通过指定相同的通量剂量功能和伽马射线源光谱，努力使该研究平行。

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来源
《Nuclear Technology》 |2006年第3期|p. 350-360|共11页
作者
Trumbull TH; Harris DR;
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作者单位

Lockheed Martin Corp, Schenectady, NY 12301 USA;

Rensselaer Polytech Inst, Dept Mech Aerosp & Nucl Engn, Troy, NY 12180 USA;

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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
gamma ray; homogenization; dose;

机译：γ射线;均匀化;剂量;

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1. Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System [J] . Arslan Alper Bugra, Yilmaz Ilayda, Bakir Gizem, Science and technology of nuclear installation . 2019,第PTa1期

机译：在加速器驱动系统中从Candu和PWR废燃料中提取的长寿命和中期裂变产品的差异
2. Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System [J] . Alper Bu?ra Arslan, ?layda Yilmaz, Gizem Bakir, Science and technology of nuclear installation . 2019,第5期

机译：在加速器驱动系统中从Candu和PWR废燃料中提取的长寿命和中期裂变产品的差异
3. New Principle for Efficiently Calculating Radiation Dose Rate Distributions in Ships Loading Multiple Shipping Casks Containing Spent Nuclear Fuel [J] . Hisao YAMAKOSHI Journal of nuclear science and technology . 1988,第7期

机译：有效地计算装载多个装有乏核燃料的集装箱的船舶中辐射剂量率分布的新原理
4. TRIPOLI-4 GAMMA-RAY DOSE CALCULATION FOR SPENT PWR FUELS [C] . Yi-Kang Lee, Kabir Sharma International conference on nuclear engineering . 2014

机译：压水堆燃料的TRIPOLI-4伽玛射线剂量计算
5. Monte Carlo characterization of PWR spent fuel assemblies to determine the detectability of pin diversion. [D] . Burdo, James S. 2010

机译：压水堆乏燃料组件的蒙特卡洛表征可确定销转向的可检测性。
6. Comparative Study on Vibration Fatigue Characteristics of Fuel Tank Material in Fuel and Air Media [O] . Long Yang, Bing Yang, Guangwu Yang, 2020

机译：燃料和空气介质中燃料箱材料振动疲劳特性的比较研究
7. Role of gamma-ray dose rate at the surface of spent fuel shipping cask in calculation of dose rate distribution throughout ship by using MANYCASK code. [O] . Hisao YAMAKOSHI 1990

机译：γ射线剂量率在花费燃料运输桶表面的作用，通过使用Manycask代码计算剂量率分布。

The effect of material homogenization in calculating the gamma-ray dose from spent PWR fuel pins in an air medium

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