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Technical Paper

Application of Time-Dependent Neutron Transport Theory to High-Temperature Reactors of Pebble Bed Type

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Pages 93-114 | Published online: 12 May 2017

References

  • S. GOLUOGLU and H. L. DODDS, “A Time-Dependent, Three-Dimensional Neutron Transport Methodology,” Nucl. Sci. Eng., 139, 248 (2001).
  • R. E. ALCOUFFE and R. S. BAKER, “Time-Dependent Deterministic Transport on Parallel Architectures Using PARTISN,” Proc. Topl. Conf. Radiation Protection and Shielding, Nashville, Tennessee, April 19–23, 1998, Vol. 1, p. 335, American Nuclear Society (1998).
  • C. R. E. DE OLIVEIRA and A. J. H. GODDARD, “EVENT: A Multidimensional Finite Element Spherical Harmonics Radiation Transport Code, in 3D Deterministic Radiation Transport Computer Programs,” Paris, France, December, 2–3, 1996.
  • A. PAUTZ and A. BIRKHOFER, “DORT-TD: A Transient Neutron Transport Code with Fully Implicit Time Integration,” Nucl. Sci. Eng., 145, 299 (2003).
  • A. PAUTZ and A. BIRKHOFER, “Coupling of Time-Dependent Neutron Transport Theory with the Thermal Hydraulics Code ATHLET and Application to the Research Reactor FRM-II,” Nucl. Sci. Eng., 145, 320 (2003).
  • A. SEUBERT, K. VELKOV, and S. LANGENBUCH, “The Time-Dependent 3-D Discrete Ordinates Code TORT-TD Coupled with the Thermal-Hydraulics System Code ATHLET,” Proc. PHYSOR 2008, Interlaken, Switzerland, September 14–19, 2008.
  • F. REITSMA, G. STRYDOM, J. B. M. DE HAAS, K. IVANOV, B. TYOBEKA, R. MPHAHLELE, T. J. DOWNAR, V. SEKER, H. D. GOUGAR, and D. F. DA CRUZ, “The PBMR Steady State and Coupled Kinetics Core Thermal-Hydraulics Benchmark Test Problems,” Nucl. Eng. Des., 236, 657 (2006).
  • S. GOLUOGLU et al., “Development of a Time-Dependent Three-Dimensional Deterministic Neutron Transport Method,” Trans. Am. Nucl. Soc., 76, 219 (1997).
  • K. L. GOLUOGLU, C. L. BENTLEY, R. V. DEMEGLIO, S. GOLUOGLU, R. E. PEVEY, I. SUSLOV, and H. L. DODDS, “Application of TDKENO for the Analysis of Criticality Excursion Experiments,” Trans. Am. Nucl. Soc., 78, 145 (1998).
  • J. O. JOHNSON, “A User’s Manual for MASH 1.0, A Monte Carlo Adjoint Shielding Code System,” ORNL/TM-11778, Oak Ridge National Laboratory (1992).
  • S. STRUTH, “DIREKT—A Computer Program for Non-Steady, Two-Dimensional Simulation of Thermo-Hydraulic Transients,” JìL-1702, Forschungszentrum JÜlich (1999).
  • D. FERGUSON and K. HANSEN, “Solutions of the Space-Dependent Reactor Kinetics Equations in Three-Dimensions,” MIT-3903-4, Massachusetts Institute of Technology (Aug. 1971).
  • D. MATHEWS, “An Improved Version of the MICROX-2 Code,” PSI Bericht Nr. 97-11, Paul Scherrer Institute (1997).
  • B. TYOBEKA, K. IVANOV, and A. PAUTZ, “Evaluation of PBMR Control Rod Worth Using Full Three-Dimensional Deterministic Transport Methods,” Ann. Nucl. Energy, 35, 6, 1050 (2008).
  • B. TYOBEKA, A. PAUTZ, and K. IVANOV, “Preliminary Investigations on the Importance of Using Transport Methods for the Analysis of the PBMR,” Trans. Am. Nucl. Soc., 93, 939 (2005).
  • H. GERWIN and G. SCHERER, “Treatment of the Upper Cavity in a Pebble Bed High-Temperature Gas-Cooled Reactor by Diffusion Theory,” Nucl. Sci. Eng., 97, 9 (1987).
  • J. C. KUIJPER et al., “Plutonium and Minor Actinide Management in Thermal High-Temperature Gas-Cooled Reactors,” Publishable Final Activity Report, (June 2010); http://janleenkloosterman.nl/reports/puma_final_201006.pdf (current as of November, 15, 2010).
  • NIST Core Math LIBrary CMLIB, in “Guide to Available Mathematical Software”; http://gams.nist.gov/serve.cgi/Package/CMLIB (2002) (current as of July 26, 2010).
  • F. REITSMA et al., “OECD/NEA/NSC PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark: The PBMR-400 Core Design,” presented at 1st Organisation for Economic Co-operation and Development Benchmark Workshop, Paris, France, June 16–17, 2005; http://www.nea.fr/science/wprs/pbmr400 (current as of July 26, 2010).
  • ANL Benchmark Problem Book, ANL-7416, Supplements 2 and 3, Argonne National Laboratory (1985).
  • F. REITSMA, J. HAN, K. IVANOV, and E. SARTORI, “The OECD/NEA/NSC PBMR400 MW Coupled Neutronics Thermal Hydraulics Transient Benchmark—Steady-State Results and Status,” Proc. PHYSOR 2008, Interlaken, Switzerland, September 14–19, 2008.
  • G. STRYDOM, F. REITSMA, P. NGELEKA, and K. IVANOV, “The OECD/NEA/NSC PBMR 400 MW Coupled Neutronics Thermal Hydraulics Transient Benchmark: Transient Results,” Proc. pHySOR 2010, Pittsburgh, Pennsylvania, May 9–14, 2010.
  • A. SEUBERT, A. SUREDA, J. BADER, J. LAPINS, M. BUCK, E. LAURIEN, “The 3-D Time-Dependent Transport Code TORT-TD and Its Coupling with the 3D Thermal-Hydraulic Code ATTICA-3D for HTGR Applications,” Proc. 5th Int. Conf. High Temperature Reactor Technology, Prague, Czech Republic, October 18–20, 2010.

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