References
- J. E. SWEEZY et al., “MCNP—A General Monte Carlo N-Particle Transport Code, Version 5,” LA-UR-03-1987, Los Alamos National Laboratory Report (Apr. 2003).
- R. E. ALCOUFFE et al., “PARTISN: A Time-Dependent Parallel Neutral Particle Transport Code System, Version 5,” LA-UR-05-3925, LosAlamos National Laboratory Report (May 2005).
- S. C. VAN DER MARCK, “Benchmarking ENDF/BVII.0,” Nucl. Data Sheets, 107, 12, 3061 (2006).
- M. B. CHADWICK et al, “ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,” Nucl. Data Sheets, 107, 12, 2931 (2006).
- W. HAECK, “JEFF 3.1Validation Results on LLNLPulsed Spheres,” JEF0DOC-1141, Nuclear Energy Agency Nuclear Science Committee (2006).
- M. LUTZ, Programming Python, 3rd ed., O’Reilly Media Inc., Sebastopol, California (2006).
- International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NCS/DOC(95)03, J. B. BRIGGS, Ed., NEA Nuclear Science Committee Report, Nuclear Energy Agency (2007).
- “ENDF-202, Cross Section Evaluation Working Group Benchmark Specifications,” BNL19302 (ENDF-202) with various revisions, R. McKNIGHT, Ed., Brookhaven National Laboratory (1974).
- Extensible Markup Language (XML); available online at www.w3.org/XML.
- A. C. KAHLER, “Monte Carlo Eigenvalue Calculations with ENDF0B-VI.8, JEFF-3.0, and JENDL-3.3 Cross Sections for a Selection of International Criticality Safety Benchmark Evaluation Project Handbook Benchmarks,” Nucl. Sci. Eng., 145, 213 (2003).
- R. D. MOSTELLER, “Comparison of Results for theMCNP Criticality Validation Suite Using ENDF0B-VII.0 and Other Nuclear Data Libraries,” Trans. Am. Nucl. Soc., 96, 417 (2007).