Photonuclear Physics in Radiation Transport—II: Implementation
Author:
Affiliation:
1. University of California, Los Alamos National Laboratory, Los Alamos, New Mexico 87545
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE144-174
Reference20 articles.
1. V. McLANE, C. L. DUNFORD, and P. F. ROSE, Eds. “ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6,” BNL-NCS-44945, Brookhaven National Laboratory (1997).
2. Photonuclear Physics in Radiation Transport—I: Cross Sections and Spectra
3. “MCNP—A General Monte Carlo N-Particle Transport Code,” LA-13709-M, J. F. BRIESMEISTER, Ed. Los Alamos National Laboratory (2000).
4. “MCNPX User’s Manual,” LA-UR-99-6058, L. S. WATERS, Ed. Los Alamos National Laboratory (1999).
5. M. C. WHITE, “Development and Implementation of Photonuclear Cross-Section Data for Mutually Coupled Neutron-Photon Transport Calculations in the Monte Carlo N-Particle (MCNP) Radiation Transport Code,” Thesis, University of Florida (2000).
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