Improved Hybrid Modeling of Spent Fuel Storage Facilities [electronic resource]
This work developed a new computational method for improving the ability to calculate the neutron flux in deep-penetration radiation shielding problems that contain areas with strong streaming. The "gold standard" method for radiation transport is Monte Carlo (MC) as it samples the physics...
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| Online Access: |
Online Access (via OSTI) |
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| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Office of the Assistant Secretary for Nuclear Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2018.
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| Subjects: |
Internet
Online Access (via OSTI)Online
| Call Number: |
E 1.99:14-6378
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| E 1.99:14-6378 | Available |