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2. Monte Carlo Criticality Methods and Analysis Capabilities in SCALE
3. ANSI/ANS-8.1-1998, “American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors,” American Nuclear Society, La Grange Park, Illinois.
4. ANSI/ANS-8.24-2007, “American National Standard for Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations,” American Nuclear Society, La Grange Park, Illinois.
5. Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques