General Handling Calculations for the Modified Hospital Can
- Y-12 National Security Complex, Oak Ridge, TN (United States)
Containers are evaluated using a Monte-Carlo N-Particle transport code (MCNP). The code calculated keff is compared to critical experiment benchmarks to determine a bias. Additional margin of safety is added to the bias to establish an upper subcritical limit (USL). Modeled cases are considered subcritical if the neutron multiplication factor plus two sigma remains below the USL. Net weight limits allow for any amount of fissile/moderator mixture to exist so long as it meets the weight requirement, therefore all mixture types must be evaluated. Cases that exceed the USL must either be controlled against or have justification why that configuration cannot reasonably exist. Current and legacy loadings and container dimensions must be taken into consideration.
- Research Organization:
- Oak Ridge Y-12 Plant (Y-12), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-NA0001942
- OSTI ID:
- 1582020
- Report Number(s):
- IROS13213
- Resource Relation:
- Conference: Nuclear Criticality Safety Division Topical Meeting
- Country of Publication:
- United States
- Language:
- English
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