31
Views
1
CrossRef citations to date
0
Altmetric
Technical Paper

Monte Carlo Interpretation of the AMMON/REF Experiment in EOLE for the JHR Reactor Neutron Calculations

, , , , , , , , , , , , , & show all
Pages 318-328 | Published online: 22 Mar 2017

REFERENCES

  • C. DÖDERLEIN et al., “The 3D Neutronics Scheme for the Development of the Jules-Horowitz-Reactor,” Proc. Int. Conf. PHYSOR 2008, Interlaken, Switzerland, September 14–19, 2008.
  • R. SANCHEZ et al., “APOLLO2 Year 2010,” Nucl. Eng. Technol., 42, 5, 474 (2010).
  • J. J. LAUTARD, S. LOUBIERE, and C. FEDON-MAGNAUD, “CRONOS, A Modular Computational System for Neutronic Core Calculations,” Proc. IAEA Specialists Mtg. Advanced Calculation Methods for Power Reactors, Cadarache, France, September 10–14, 1990.
  • A. SANTAMARINA et al., “The JEFF-3.1.1 Nuclear Data Library,” JEFF Report 22, NEA No. 6807, Organisation for Economic Co-operation and Development (2009).
  • C. VAGLIO-GAUDARD et al., “Monte Carlo Interpretation of the AMMON/REF Experiment in EOLE for the JHR Reactor Calculations,” Proc. Int. Conf. PHYSOR 2012, Knoxville, Tennessee, April 15–20, 2012, American Nuclear Society (2012).
  • J. C. KLEIN et al., “AMMON: An Experimental Program in the EOLE Critical Facility for the Validation of the Jules Horowitz Reactor Neutron and Photon HORUS3D Calculation Scheme,” Proc. Int. Conf. IGORR 2009, Beijing, China, October 28–31, 2009.
  • E. BRUN et al., “Overview of TRIPOLI-4© Version 7 Continuous-Energy Monte Carlo Transport Code,” Proc. Int. Conf. ICAPP 2011, Nice, France, May 2–6, 2011.
  • R. E. MacFARLANE, D. W. MUIR, and D. C. GEORGE, “NJOY99.0: Code System Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data,” PSR-480/NJOY99.0-RISCC, Peripheral Shielding Route Collection, Los Alamos National Laboratory (2000).
  • J. C. SUBLET, P. RIBON, and M. COSTE-DELCLAUX, “CALENDF-2005: User Manual,” CEA-R-6131, CEA (2006).
  • O. LERAY, “Détermination, maîtrise et réduction des biais et incertitudes sur la réactivité du Réacteur Jules Horowitz,” PhD Dissertation, Université de Grenoble, France (2012) (in French).
  • O. LERAY et al., “Innovative Statistical Method for Predicting the Uncertainty due to Technological Data on the Reactivity Parameter of Experimental Reactors—Application for the AMMON Program,” Proc. Int. Conf. RRFM 2013, Saint Petersburg, Russia, April 21–25, 2013.
  • O. LERAY et al., “Sensitivity and Uncertainty Analysis Applied to the JHR Reactivity Prediction,” Proc. Int. Conf. PHYSOR 2012, Knoxville, Tennessee, April 15–20, 2012, American Nuclear Society (2012).
  • V. V. ORLOV et al., “Problem of Fast Reactor Physics Related to Breeding,” At. Energy Rev., 18, 4, 989 (1980).
  • L. C. LEAL et al., “Aluminum Data Measurements and Evaluation for Criticality Safety Applications,” JEFDOC-913, Organisation for Economic Co-operation and Development (2002).
  • X-5 MONTE CARLO TEAM, “MCNP—A General Monte Carlo N-Particle Transport Code, Version 5. Volume I: Overview and Theory,” LA-UR-03-1987, Los Alamos National Laboratory (2005).
  • G. BIGNAN et al., “Handbook of Nuclear Engineering—Reactor Physics Experiments on Zero Power Reactors,” Vol. 18, Springer (2010).
  • P. LECONTE, “Developpement et optimization de techniques de mesure par spectrométrie gamma—maîtrise et reduction des incertitudes associées,” PhD Dissertation, Université de Clermont-Ferrand, France (2006) (in French).
  • C. E. COHN, “A Simplified Theory of Pile Noise,” Nucl. Sci. Eng., 7, 472 (1960).
  • Y. K. LEE and F. X. HUGOT, “Calculation of the Effective Delayed Neutron Fraction by TRIPOLI-4 Code for IPEN/MB-01 Research Reactor,” Proc. Int. Conf. M&C 2011, Rio de Janeiro, Brazil, May 8–12, 2011.
  • M. M. BRETSCHER, “Evaluation of Reactor Kinetic Parameters Without the Need for Perturbation Codes,” Int. Mtg. RERTR, Jackson Hole, Wyoming, October 5–10, 1997.
  • Y. NAUCHI and T. KAMEYAMA, “Proposal for Direct Calculation of Kinetic Parameters βeff and Λ Based on Continuous Energy Monte Carlo Method,” J. Nucl. Sci. Technol., 42, 503 (2005).
  • R. K. MEULEKAMP and S. C. VAN DER MARCK, “Calculating the Effective Delayed Neutron Fraction with Monte Carlo,” Nucl. Sci. Eng., 152, 142 (2006).
  • J. F. BRIESMEISTER, “MCNP—A General Monte Carlo N-Particle Transport Code, Version 4C,” LA-13709-M, Los Alamos National Laboratory (2000).
  • B. VERBOOMEN, W. HAECK, and P. BAETEN, “Monte Carlo Calculation of the Effective Neutron Generation Time,” Ann. Nucl. Energy, 33, 911 (2006).
  • C. VAGLIO-GAUDARD et al., “Monte Carlo Interpretation of the Photon Heating Measurements in the Integral AMMON/REF Experiment in the EOLE Facility,” IEEE Trans. Nucl. Sci. (submitted for publication).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.