References
- J. C. WAGNER and A. HAGHIGHAT, “Automated Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint Function,” Nucl. Sci. Eng., 128, 186 (1998).
- A. HAGHIGHAT and J. C. WAGNER, “Monte Carlo Variance Reduction with Deterministic Importance Functions,” Prog. Nucl. Energy, 42, 25 (2003).
- D. E. PEPLOW, “MAVRIC: MONACO with Automated Variance Reduction Using Importance Calculations,” ORNL/TM-2005/39, Version 6, Vol. I, Sec. S6, Oak Ridge National Laboratory (2009).
- “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations,” ORNL/TM-2005/39, Version 6, Vols. I, II, and III, Oak Ridge National Laboratory (2009).
- J. S. TANG and M. B. EMMETT, “SAS4: A Monte Carlo Cask Shielding Analysis Module Using an Automated Biasing Procedure,” ORNL/TM-2005/39, Version 5.1, Vol. I, Sec. S4, Oak Ridge National Laboratory (2006).
- H. THIELE and F.-M. BORST, “Shielding Benchmark Calculations with SCALE/MAVRIC and Comparison with Measurements for the German Cask Castor HAW 20/28 CG,” Nucl. Technol., 168, 867 (2009).
- S. P. SIMNER and C. E. SANDERS, “Shielding Analysis of Yucca Mountain Aging Casks Using MAVRIC,” Trans. Am. Nucl. Soc., 99, 605 (2008).
- “MCNP—A General Monte Carlo N-Particle Transport Code,” Version 4C, LA-13709-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (2000).
- A. Y. CHEN, Y. F. CHEN, J. N. WANG, R. J. SHEU, Y.-W. H. LIU, and S. H. JIANG, “A Comparison of Dose Rate Calculations for a Spent Fuel Storage Cask by Using MCNP and SAS4,” Ann. Nucl. Energy, 35, 2296 (2008).
- “Safety Analysis Report for the Independent Spent Fuel Storage Installation in Nuclear Power Plant 1,” Taiwan Power Company (2007).
- “Neutron and Gamma-Ray Fluence-to-Dose Factors,” ANSI/ANS-6.1.1-1991, American Nuclear Society, La Grange Park, Illinois (1991).