Torkzadeh F, Taheri M
Atom Energy Organisation of Iran, Department Radiation Protection Division: Dosimetry, Avenue North Kargar, P.O. Box 14155-4494, Tehran, Iran.
Radiat Prot Dosimetry. 2007;125(1-4):224-8. doi: 10.1093/rpd/ncl121. Epub 2006 Sep 16.
The Neutriran albedo neutron dosemeter has been improved and calibrated for neutron personal dosimetry. The Monte Carlo code MCNP4b was used to calculate the thermal neutrons backscattered from the body (albedo factor). Backscattering from the wall, ceiling and floor in calibration room was considered also via simulation by MCNP4C. A semi automated counting system applying a high-resolution scanner was used for counting of tracks. An 241Am source was used to produce similar alpha particles from 10B (n,alpha)7Li reaction for the optimisation of scanner parameters to distinguish and separate the tracks in SSNTD, which lead to a better distinction between etched alpha tracks and, consequently, a higher linear region of dose characteristic.
Neutriran反照率中子剂量计已得到改进并针对中子个人剂量测定进行了校准。使用蒙特卡罗代码MCNP4b计算从人体反向散射的热中子（反照率因子）。在校准室中，还通过MCNP4C模拟考虑了来自墙壁、天花板和地板的反向散射。一个应用高分辨率扫描仪的半自动计数系统用于径迹计数。使用241Am源通过10B（n，α）7Li反应产生类似的α粒子，以优化扫描仪参数，以便在固体径迹探测器中区分和分离径迹，这导致蚀刻α径迹之间有更好的区分，从而剂量特性的线性区域更高。
