SLAC National Accelerator Laboratory, Menlo Park, CA 94025-7015, United States of America.
Institut de Radioprotection et de Sûreté Nucléaire, 92260 Fontenay-aux-Roses, France.
J Radiol Prot. 2024 Jul 26;44(3). doi: 10.1088/1361-6498/ad6453.
This paper presents a proposed revision of the International Atomic Energy Agency transport regulations, related to theandlimit values used to determine the radioactive transport classification. Based on the 'system', a novel methodology was introduced to deriveandvalues related to scenarios involving external exposure from a distant source. These values are key parameters that respectively represent the total effective dose and total equivalent dose to the skin, from all primary and secondary particles contributing to radiation exposure. The International Working Group (WG/) is established and associated with the TRANSSC Technical Expert Group on Radiation Protection. A review of theandvalues is performed in response to identified limitations within the existingsystem. The followed approach is based on Monte Carlo simulations that enabled the development of transfer functions aimed at reducing computational time and increasing the flexibility of dose evaluations for any radionuclide with known particle emission spectra. This method allows updating theandvalues to account for future data evolutions (decay data, fluence-to-dose conversion coefficients) and standardizing the calculation of regulation limits across all referenced radionuclides and scenarios related to external exposure. The transfer functions are established using three Monte Carlo simulation codes-FLUKA, Geant4, and MCNP-and address the previous limitations of the 'system', reflecting the latest International Commission for Radiation Protection recommendations and improvements in calculation techniques. The results of the WG show consistent agreement across the codes, with minor discrepancies observed at low primary energies due to statistical uncertainties and different handling of stopping power for electrons/positrons in the codes. This revised approach aligns with current standards and recommendations, ensuring that the radiological consequences of transport accidents are acceptable for the newandlimits from a radiological protection perspective.
本文提出了对国际原子能机构运输法规的修订建议,涉及用于确定放射性运输分类的和限值。基于“系统”,引入了一种新的方法来推导与来自远距离源的外部照射相关的和值。这些值是关键参数,分别代表来自所有对辐射暴露有贡献的初级和次级粒子的总有效剂量和皮肤总当量剂量。国际工作组(WG/)成立,并与 TRANSSC 辐射防护技术专家组相关联。为了应对现有“系统”内的局限性,对和值进行了审查。所采用的方法基于蒙特卡罗模拟,开发了传递函数,旨在减少计算时间并提高对任何具有已知粒子发射谱的放射性核素的剂量评估的灵活性。该方法允许更新和值,以考虑未来的数据演变(衰变数据、注量-剂量转换系数),并使所有参考放射性核素和与外部照射相关的场景的法规限值的计算标准化。传递函数是使用三个蒙特卡罗模拟代码(FLUKA、Geant4 和 MCNP)建立的,解决了“系统”的先前局限性,反映了最新的国际辐射防护委员会建议和计算技术的改进。WG 的结果在代码之间具有一致的一致性,由于统计不确定性和代码中电子/正电子停止能力的不同处理,在低初级能量下观察到较小的差异。这种修订方法符合当前标准和建议,确保从辐射防护角度来看,运输事故的放射性后果可接受新的和限值。