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Technical Paper

Random Adjustment of the H in H2O Neutron Thermal Scattering Data

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Pages 287-299 | Published online: 13 May 2017

REFERENCES

  • M. MATTES and J. KEINERT, “Thermal Neutron Scattering Data for the Moderator Materials H2O, D2O and ZrHx in ENDF-6 Format and as ACE Library for MCNP (X) Codes,” INDC(NDS)-0470, International Atomic Energy Agency (Apr. 2005).
  • R. E. MacFARLANE, “New Thermal Neutron Scattering Files for ENDF/B-VI Release 2,” LA-12639-MS, Los Alamos National Laboratory (Aug. 1994).
  • “International Handbook of Evaluated Criticality Safety Benchmark Experiments,” NEA/NSC/DOC(95)03/I, Organisation for Economic Co-operation and Development, Nuclear Energy Agency, J. B. BRIGGS, Ed. (2004).
  • D. ROCHMAN and A. J. KONING, “How to Randomly Evaluate Nuclear Data: A New Data Adjustment Method Applied to 239Pu,” Nucl. Sci. Eng, 169, 68 (2011).
  • D. ROCHMAN and A. J. KONING, “Evaluation and Ad-justment of the Neutron-Induced Reactions of 63,65Cu,” Nucl. Sci. Eng, 170, 265 (2012).
  • A. TRKOV and M. MATTES, “On the Thermal Scattering Law Data for Reactor Lattice Calculations,” Proc. Int. Conf. Nuclear Energy for New Europe 2004, Portoroz, Slovenia, September 6–9, 2004, p. 201.1 (2004).
  • M. B. CHADWICK et al., Nucl. Data Sheets, 107, 2931 (2006).
  • A. SANTAMARINA et al., “The JEFF-3.1.1 Nuclear Data Library,” OECD/NEA JEFF Report 22, Organisation for Economic Co-operation and Development, Nuclear Energy Agency (2009).
  • K. SHIBATA et al., J. Nucl. Sci. Technol, 48, 1 (2011).
  • “MCNP—A General Monte Carlo N-Particle Transport Code, Version 4C,” LA-13709-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (2000).
  • D. ROCHMAN and A. J. KONING, “500 Random Evaluations of 239Pu,” OECD/NEA JEF/DOC-1327, Organisation for Economic Co-operation and Development, Nuclear Energy Agency (May 2010).
  • A. J. KONING, S. HILAIRE, and M. C. DUIJVESTIJN, “TALYS-1.0,” Proc. Int. Conf. Nuclear Data for Science and Technology (ND2007), Nice, France, May 22–27, 2007; www.talys.eu.
  • R. E. MacFARLANE and A. C. KAHLER, Nucl. Data Sheets, 111, 2739 (2010).
  • R. E. MacFARLANE, “NJOY99—Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data,” RSIC PSR-480, Los Alamos National Laboratory (2000).
  • A. J. KONING and D. ROCHMAN, Ann. Nucl. Energy, 35, 2024 (2008).
  • C. J. DEAN, Personal Communication (Dec. 2011).

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