首页> 外文学位 >Neutron flux and energy characterization of a plutonium-beryllium isotopic neutron source by monte carlo simulation with verification by neutron activation analysis.

【24h】

Neutron flux and energy characterization of a plutonium-beryllium isotopic neutron source by monte carlo simulation with verification by neutron activation analysis.

机译：mon-铍同位素中子源的中子通量和能量表征，通过蒙特卡罗模拟并通过中子活化分析进行验证。

获取原文

获取原文并翻译 | 示例

页面导航

摘要
著录项
相似文献
相关主题

摘要

The purpose of this research was to characterize the neutron energy distribution and flux emitted from the UNLV plutonium-beryllium source, serial number MRC-N-W PuBe 453. This was accomplished through the use of the MCNPX/5 Monte-Carlo particle transport code to simulate radiation interactions within the physical environment of the source and its surroundings. The moderating drum currently containing the source as well as all of the sampling ports were accurately modeled in MCNPX/5. This geometry was then used to simulate the neutron interactions taking place in these geometries. The results of the simulations were then verified by the use of specifically chosen activation detectors and threshold foils designed to accurately convey information on the energy distribution and flux of the neutrons present at multiple sampling locations.

机译：这项研究的目的是表征从序列号MRC-NW PuBe 453的UNLV ber-铍源发出的中子能量分布和通量。这是通过使用MCNPX / 5蒙特卡洛粒子传输代码进行模拟来完成的源及其周围环境的辐射相互作用。当前包含源以及所有采样端口的调节鼓已在MCNPX / 5中精确建模。然后将这种几何形状用于模拟在这些几何形状中发生的中子相互作用。然后，通过使用专门选择的激活检测器和阈值箔片来验证仿真结果，这些激活检测器和阈值箔片旨在准确传达有关在多个采样位置处存在的中子的能量分布和通量的信息。

著录项

作者
Harvey, Zachary R.;
展开▼
作者单位

University of Nevada, Las Vegas.;

展开▼
授予单位 University of Nevada, Las Vegas.;
学科 Physics Nuclear.;Physics Radiation.
学位 M.S.
年度 2010
页码 85 p.
总页数 85
原文格式 PDF
正文语种 eng
中图分类
关键词

相似文献

外文文献
中文文献
专利

1. Monte Carlo simulation of thermal neutron flux of americium-beryllium source used in neutron activation analysis [J] . Didi Abdessamad, Dadouch Ahmed, Bencheikh Mohamed, Moscow University Physics Bulletin . 2017,第5期

机译：中子激活分析中的美洲铍源热中子源的蒙特卡罗模拟
2. Monte-Carlo simulations of elastically backscattered neutrons from hidden explosives using three different neutron sources. [J] . Elagib I, Elsheikh N, Alsewaidan H, Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine . 2009,第1期

机译：使用三种不同的中子源对隐藏爆炸物产生的弹性后向散射中子进行的蒙特卡洛模拟。
3. Simulation of the direct geometry spectrometer for neutron time of flight based on the Monte Carlo method to calculate the energy spectrum of the neutron source [J] . Hosseini Seyed Abolfazl, Mehrabi Mohammad Nuclear instruments and methods in physics research . 2020,第Jana1期

机译：基于蒙特卡罗方法的中子飞行时间直接几何光谱仪的仿真，以计算中子源的能谱
4. Monte Carlo simulation of neutron transport applied to criticality Focus on sources and flux convergence issues [C] . J. Miss, Y. Richet, O. Jacquet CNS/CNA student conference;Annual conference of the Canadian Nuclear Society . 2012

机译：应用于临界的中子输运的蒙特卡洛模拟关注源和通量收敛问题
5. The analog linear interpolation approach for Monte Carlo simulation of prompt gamma-ray neutron activation analysis. [D] . Zhang, Wenchao. 2003

机译：用于蒙特卡罗模拟的瞬态伽马射线中子活化分析的模拟线性插值方法。
6. Neutron activation analysis with a Monte Carlo simulation for kidney stones [O] . Huseyin Sahiner, Anjali Srivastava, Cynthia H McCollough, -1

机译：肾结石的蒙特卡罗模拟中子活化分析
7. NEUTRON SOURCES, ENERGY, FLUX DENSITY, AND MODERATION IN TOTAL-BODY NEUTRON ACTIVATION ANALYSIS. [O] . S.H. Cohn, R.G. Fairchild, K.K. Shukla 1972

机译：中子源，能量，助焊剂密度和全体中子激活分析中的适度。

Neutron flux and energy characterization of a plutonium-beryllium isotopic neutron source by monte carlo simulation with verification by neutron activation analysis.

摘要

著录项

相似文献

相关主题

期刊订阅