首页> 美国卫生研究院文献>Radiation Protection Dosimetry >PIECEWISE POLYNOMIAL APPROXIMATIONS TO THE ICRP 116 EFFECTIVE DOSE COEFFICIENTS: PHOTONS AND NEUTRONS
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PIECEWISE POLYNOMIAL APPROXIMATIONS TO THE ICRP 116 EFFECTIVE DOSE COEFFICIENTS: PHOTONS AND NEUTRONS

机译:ICRP 116有效剂量系数的分段多项式近似:光子和中子

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摘要

We present fitting equations for estimating effective dose per unit fluence at any photon energy between 10 keV and 10 GeV and any neutron energy between 0.001 eV and 10 GeV. These new equations are based on the latest radiation protection quantities for external radiation exposure found in International Commission on Radiological Protection (ICRP) Publication 116 and incorporate the latest definition of effective dose as described in ICRP Publication 103. The ICRP 116 dose coefficients were fit to piecewise polynomial functions. A total of 8 irradiation geometries were considered: the six in ICRP 116 and two additional geometries presented elsewhere in the literature. The fitting functions generally reproduce the ICRP 116 data to within 3% or better. The functions were used to modify the Monte Carlo N-Particle radiation transport code version 6 (MCNP6) and were applied to a sample problem. The results are intended to be used as a basis for revising the American National Standards Institute/American Nuclear Society 6.1.1-1991 standard.
机译:我们提出了拟合方程,用于估算在10 keV和10 GeV之间的任何光子能量以及0.001 eV和10 GeV之间的任何中子能量时每单位注量的有效剂量。这些新方程式基于国际放射防护委员会(ICRP)出版物116中关于外部辐射暴露的最新辐射防护量,并结合了ICRP出版物103中描述的有效剂量的最新定义。ICRP116剂量系数适合分段多项式函数。总共考虑了8种辐照几何形状:ICRP 116中的6种辐照几何形状以及文献中其他地方提出的另外两种几何形状。拟合功能通常会将ICRP 116数据再现到3%或更好的范围内。该函数用于修改蒙特卡罗N粒子辐射传输代码版本6(MCNP6),并应用于示例问题。该结果旨在用作修订美国国家标准协会/美国核协会6.1.1-1991标准的基础。

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