Evaluation of Simplified Models for Estimating Public Dose from Spent Nuclear Fuel Shipments
This paper investigates the dose rate as a function of distance from a representative high-capacity SNF rail-type transportation cask. It uses the SCALE suite of radiation transport modeling and simulation codes to determine neutron and gamma radiation dose rates. The SCALE calculated dose rate is compared with simplified analytical methods historically used for these calculations. The SCALE dose rate calculation presented in this paper employs a very detailed transportation cask model (e.g., pin-by-pin modeling of fuel assembly) and a new hybrid computational transport method. Because it includes pin-level heterogeneity and models ample air and soil outside the cask to simulate scattering of gamma and neutron radiation, this detailed SCALE model is expected to yield more accurate results than previously used models which made more simplistic assumptions (e.g., fuel assembly treated as a point or line source, simple 1-D model of environment outside of cask). The results in this paper are preliminary and, as progress is made on developing and validating improved models, results may be subject to change as models and estimates become more refined and better information leads to more accurate assumptions.
- Publication Date:
- OSTI Identifier:
- DOE Contract Number:
- Resource Type:
- Resource Relation:
- Conference: 2015 ANS Winter Meeting and Nuclear Technology Expo, Washington, DC (United States), 8-11 Nov 2015
- Research Org:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org:
- USDOE Office of Nuclear Energy (NE)
- Country of Publication:
- United States
- 61 RADIATION PROTECTION AND DOSIMETRY; COMPARATIVE EVALUATIONS; NEUTRONS; SPENT FUEL CASKS; DOSE RATES; GAMMA RADIATION; AIR; COMPUTERIZED SIMULATION; FUEL ASSEMBLIES; SCALE MODELS; RADIATION DOSES; RADIATION DOSE DISTRIBUTIONS; SCATTERING; SOILS
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