原文传递
Evaluation of gamma radiation shielding for nuclear waste shipping casks
| 题名： | Evaluation of gamma radiation shielding for nuclear waste shipping casks |
| 作者： | Liu, Y. Y.; Carlson, R. D.; Primeau, S. J.; Wangler, M. E. |
| 关键词： | Biological Shielding##Waste Transportation##Radioactive Wastes##Casks##Meetings##Gamma Radiation##Evaluation##Radiation Doses##Safety##EDB/420204##EDB/050900## |
| 摘要： | A method has been developed for evaluating gamma radiation shielding of shipping casks that are used to transport nuclear waste with ill-defined radionuclide contents. The method is based on calculations that establish individual limits for a comprehensive list of radionuclides in the waste, assuming that each radionuclide is uniformly distributed in a volumetric source in the cask. For multiple radionuclide mixtures, a linear fraction rule is used to restrict the total amount of radionuclides such that the sum of the fractions does not exceed 1. As long as the radionuclide limits and the linear fraction rule are followed, it can be shown that the regulatory dose rate requirements for a cask will be satisfied under normal conditions of transport and in a hypothetical accident during which the shielding thickness of the cask has been reduced by 40%. |
| 总页数： | 10 |
| 报告类型： | 科技报告 |
相关文献
- Analysis of radiation measurement data of the BUSS cask
- Overweight truck shipments to nuclear waste repositories: legal, political, administrative and operational considerations
- Verification and Validation of Monte Carlo N-Particle 6 for Computing Gamma Protection Factors.
- Verification and Validation of Monte Carlo N-Particle 6 for Computing Gamma Protection Factors.
- New Applications of Gamma Spectroscopy: Characterization Tools for D&D Process Development, Inventory Reduction Planning & Shipping, Safety Analysis & Facility Management During the Heavy Element Facility Risk Reduction Program
- Packaging Certification Program Methodology for Determining Dose Rates for Small Gram Quantities in Shipping Packagings
检索历史
应用推荐
