Web24 mei 2024 · F4 is a flux tally, but instead of counting the neutrons going through it MCNP measures the total path length and divides it by the volume of the cell to calculate the … WebThe Monte Carlo N-Particle Transport Code MCNP version 4B perturbation capability has been extended to cross-section dependent tallies and to the track-length estimate of Iqff …
深贯穿问题脉冲高度计数减方差技巧_参考网
Web3 mrt. 2003 · MCNPX is a Monte Carlo N-Particle radiation transport code extending the capabilities of MCNP4C. As with MCNP, MCNPX uses nuclear data tables to transport neutrons, photons, and electrons. Web4 feb. 2002 · MCNP (Monte Carlo N-Particle Transport Code)3)と 原 研で開発されたMVP (Monte Carlo Vector Processing Code)4)で ある。原研や日本原子力学会の委員会活動で知 り得た情報によれば,前 者はモンテカルロ計算者の約70 %に 利用されており,後 者は約30%に 利用されている。 shwehosting
MCNP学习笔记-计数卡F6_百度文库
WebThe FM card mnltiplies the Fl, F2, F4 and F4 tallies by any continuos energy quantity available in the data libraries. These include for neutrons the absorption cross section, … Web最后推出的 F4 下的值 的单位应该是 rem/h(雷姆每小时)吧,我推倒就是按照这个单位来算的。 大家 .LOG 采用美国洛斯阿拉莫斯编制的蒙特卡罗软件 MCNP,对核工业航测遥感中心二级 放射性计量站的地面圆柱体放射性模型 (Fi220cmx60cm,底面直径*高度 ,以下简 称圆柱体模型) 表面及上方不同高度处的空气吸收剂量率进行了模拟计算。 在空气吸收剂量率模 … Web24 mei 2024 · F4 is a flux tally, but instead of counting the neutrons going through it MCNP measures the total path length and divides it by the volume of the cell to calculate the flux. It's only the cookie cutting later that gives (1 2 3) finite volume. So the function to find the volume fails and MCNP freaks. the pashtuns book