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Technical Paper

ENDF70: A Continuous-Energy MCNP Neutron Data Library Based on ENDF/B-VII.0

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Pages 832-836 | Published online: 10 Apr 2017

References

  • M. B. CHADWICK et al., “ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,” Nucl. Data Sheets, 107, 2931 (2006).
  • R. E. MacFARLANE and D. W. MUIR, “The NJOY Nuclear Data Processing System Version 91,” LA-12740-M, Los Alamos National Laboratory (Oct. 1994).
  • J. M. CAMPBELL, S. C. FRANKLE, and R. C. LITTLE, “ENDF66: A Continuous-Energy Neutron Data Library for MCNP4C,” LA-UR-02-3000, Los Alamos National Laboratory (2002).
  • J. L. CONLIN, F. B. BROWN, and R. D. MOSTELLER, “Temperature Corrections in MCNP for Calculating the Doppler Defect,” LA-UR-05-6225, Los Alamos National Laboratory (Aug. 2005).
  • G. AUDI et al., “Ame2003: Atomic Mass Evaluation, Nov. 2003,” Nov. 2007; available on the Internet at http://www.nndc.bnl.gov/amdc/web/masseval.html.
  • H. R. TRELLUE, R. C. LITTLE, and M. B. LEE, “The Processing of ENDF70 and ENDF70PROT: New ACEFormatted Neutron and Proton Libraries Based on ENDF/BVII.0,” LA-UR-08-1999, Los Alamos National Laboratory.

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