Monte Carlo Eigenvalue Calculations with ENDF/B-VI.8, JEFF-3.0, and JENDL-3.3 Cross Sections for a Selection of International Criticality Safety Benchmark Evaluation Project Handbook Benchmarks
Author:
Affiliation:
1. Bettis Atomic Power Laboratory West Mifflin, Pennsylvania 15122
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE03-A2377
Reference8 articles.
1. “International Handbook of Evaluated Criticality Safety Benchmark Experiments,” NEA/NSC/DOC(95)03, J. B. BRIGGS, Ed. Organisation for Economic Co-operation and Development/Nuclear Energy Agency (2001).
2. J. R. PARRINGTON, H. D. KNOX, S. L. BRENEMAN, E. M. BAUM, and F. FEINER, “Nuclides and Isotopes (Chart of the Nuclides),” 15th ed. General Electric Nuclear Energy (1996).
3. L. A. ONDIS II, L. J. TYBURSKI, and B. S. MOSKO-WITZ, “RCP01—A Monte Carlo Program for Solving Neutron and Photon Transport Problems in Three Dimensional Geometry and Detailed Energy Description and Depletion Capability,” B-TM-1638, Bettis Atomic Power Laboratory (Mar 2000)
4. J. K. FOX, L. W. GILLEY, and D. CALLIHAN, “Critical Mass Studies, Part IX, Aqueous235U Solutions (Continued),” ORNL-2367, p. 22, Oak Ridge National Laboratory (1958).
5. Analysis of a Set of Critical Homogeneous U-H2O Spheres
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