Multigroup Coupled Neutron-Gamma Cross-Section Library for Deterministic and Monte Carlo Borehole-Logging Analysis

REFERENCES

• D. LEGRADY, “Improved Monte Carlo Methods with Application to Borehole Logging Simulation,” Thesis, Delft University of Technology, Delft, The Netherlands (2005).
   Google Scholar
• W. A. RHOADES et al., “DOORS 3.2, One-, Two-, Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System, CCC-650,” Radiation Safety Information Computational Center, Oak Ridge National Laboratory (1998).
   Google Scholar
• R. E. ALCOUFFE et al., “DANTSYS 3.0—A Diffusion-Accelerated, Neutral-Particle Transport Code System,” LA-12969-M, Los Alamos National Laboratory (1995) (CCC-0547/08 package).
   Google Scholar
• J. E. WHITE, D. T. INGERSOLL, C. O. SLATER, and R. W. ROUSSIN, “BUGLE-96: A Revised Multigroup Cross Section Library for LWR Applications Based on ENDF/B-VI Release 3,” Proc. Topl. Mtg. Radiation Protection and Shielding, No. Falmouth, Massachusetts, April 21–25, 1996, Vol. 2, p. 1071, American Nuclear Society (1996).
   Google Scholar
• M. HERMAN and A. B. PASHCHENKO, “Extension and Improvement of the FENDL Library for Fusion Applications (FENDL-2),” INDC(NDS)-373, International Atomic Energy Agency (1997).
   Google Scholar
• “MCNP—A General Monte Carlo N-Particle Transport Code, Version 4C,” LA-13709-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (2000).
   Google Scholar
• A. BADRUZZAMAN, “A Three-Dimensional Radiation Transport Problem in Well-Logging,” Proc. Int. Mtg. Advances in Nuclear Engineering Computational Methods, Knoxville, Tennessee, April 9–11, 1985, Vol. 1, p. 94, American Nuclear Society (1985).
   Google Scholar
• I. KODELI, “Multidimensional Deterministic Nuclear Data Sensitivity and Uncertainty Code System: Method and Application,” Nucl. Sci. Eng., 138, 45 (2001).
   Web of Science ®Google Scholar
• I. KODELI and D. ALDAMA, “Nuclear Well Logging Modeling Using Deterministic and Monte Carlo Transport Computer Codes,” Proc. 12th European Symp. Improved Oil Recovery, Kazan, Russia, September 8–10, 2003.
   Google Scholar
• E. SARTORI, “Standard Energy Group Structures of Cross Section Libraries for Reactor Shielding, Reactor Cell and Fusion Neutronics Applications,” NEA-1344 (ZZ-GROUPSTRUCTURES), Organisation for Economic Cooperation and Development/Nuclear Energy Agency Data Bank Code Package (1990).
   Google Scholar
• R. E. MACFARLANE, “NJOY99.0, Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data,” PSR-480, Los Alamos National Laboratory (2000).
   Google Scholar
• P. F. A. DE LEEGE, “NSLINK, A Code System to Link NJOY to SCALE,” Proc. Seminar NJOY-91 and THEMIS, Saclay, France, September 17–19, 1991, Nuclear Energy Agency Data Bank (1992).
   Google Scholar
• “SCALE4.4: Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation for Workstations and Personal Computer,” Code Package CCC-545, Radiation Safety Information Computational Center (2000).
   Google Scholar
• N. M. GREENE, W. E. FORD, L. M. PETRIE, and J. W. ARWOOD, “AMPX-77: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Cross Section Libraries from ENDF/B-IV and/or ENDF/B-V,” ORNL/CSD/TM-283, Oak Ridge National Laboratory (1992).
   Google Scholar
• R. E. MACFARLANE, “TRANSX 2: A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes,” LA-12312-MS, Los Alamos National Laboratory (1992).
   Google Scholar
• J. C. WAGNER et al., “MCNP: Multigroup/Adjoint Capabilities,” LA-12704, Los Alamos National Laboratory (1994).
   Google Scholar
• R. O. SAYER et al., “R-Matrix Evaluation of Cl Neutron Cross Section up to 1.2 MeV,” ORNL/TM-2003/50, Oak Ridge National Laboratory (2003).
   Google Scholar
• A. KONING, Nuclear Research and Consultancy Group, Personal Communication.
   Google Scholar
• G. A. WRIGHT, E. SHUTTLEWORTH, M. J. GRIM-STONE, and A. J. BIRD, “The Status of the General Radiation Transport Code MCBEND,” Proc 5th Int. Topl. Mtg. Industrial Radioisotope and Radiation Measurement Applications, Bologna, Italy, June 9–14, 2002.
   Google Scholar
• N. R. SMITH et al., “The Current Status and Future Plans for the Monte Carlo Codes MONK and MCBEND,” Proc. Int. Conf. Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, Lisbon, Portugal, October 23–26, 2000.
   Google Scholar
• R. ORSI, “BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0,” Nucl. Sci. Eng., 150, 368 (2005).
   Web of Science ®Google Scholar
• Y. OYAMA, K. KOSAKO, and H. MAEKAWA, “Measurement and Calculations of Angular Neutron Flux Spectra from Iron Slabs Bombarded with 14.8-MeV Neutrons,” Nucl. Sci. Eng., 115, 24 (1993).
   Web of Science ®Google Scholar
• I. KODELI, H. HUNTER, and E. SARTORI, “Radiation Shielding and Dosimetry Experiments Updates in the SINBAD Data Base,” Radiat. Prot. Dosim., 116, 1–4, 558 (2005); available on the Internet at http://www.nea.fr/html/science/shielding/sinbad/sinbadis.htm.
   Google Scholar
• A. I. SAUKOV, B. I. SUKHANOV, A. M. RYABININ, V. D. LYUTOV, V. M. SHMAKOV, and A. P. VASILIEV, “Photon Leakage from Spherical and Hemispherical Samples with a Central 14-MeV Neutron Source,” Nucl. Sci. Eng., 142, 158 (2002).
   Web of Science ®Google Scholar
• E. N. LIPILINA, Russian Federal Nuclear Centre, Institute of Technical Physics, Personal Communication.
   Google Scholar
• I. KODELI, D. L. ALDAMA, P. F. A. DE LEEGE, D. LEGRADY, and J. E. HOOGENBOOM, “ZZ-BOREHOLE-EB6.8-MG, Multi-Group Cross-Section Library for Deterministic and Monte Carlo Codes,” IAEA1398, Organisation for Economic Co-operation and Development/Nuclear Energy Agency Data Bank Code Package (2006).
   Google Scholar