Nuclear Engineering and Technology

  • 제37권1호
  • /
  • Pages.79-90
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  • 2005
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

EVOLUTION OF NUCLEAR FUEL MANAGEMENT AND REACTOR OPERATIONAL AID TOOLS

  • TURINSKY PAUL J. (Electric Power Research Center Department of Nuclear Engineering North Carolina State University) ;
  • KELLER PAUL M. (Electric Power Research Center Department of Nuclear Engineering North Carolina State University) ;
  • ABDEL-KHALIK HANY S. (Currently with Framatome ANP, Inc.)
  • 발행 : 2005.02.01
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초록

In this paper are reviewed the current status of nuclear fuel management and reactor operational aid tools. In addition, we indicate deficiencies in current capabilities and what future research is judged warranted. For the nuclear fuel management review the focus is on light water reactors and the utilization of stochastic optimization methods applied to the lattice, fuel bundle, core loading pattern, and for BWRs the control rod pattern/core flow design decision making problems. Significant progress in addressing separately each of these design problems on a single cycle basis is noted; however, the outstanding challenge of addressing the integrated design problem over multiple cycles under conditions of uncertainty remains to be addressed. For the reactor operational aid tools review the focus is on core simulators, used to both process core instrumentation signals and as an operator aid to predict future core behaviors under various operational strategies. After briefly reviewing the current status of capabilities, a more in depth review of adaptive core simulation capabilities, where core simulator input data are adjusted within their known uncertainties to improved agreement between prediction and measurement, is presented. This is done in support of the belief that further development of adaptive core simulation capabilities is required to further significantly advance the utility of core simulators in support of reactor operational aid tools.

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참고문헌

  1. P. J. Turinsky and G. T. Parks, Chapter: Advances in Nuclear Fuel Management Optimization for Light Water Reactors, Advances in Nuclear Science and Technology, 21, 137, Kluwer Academic/Plenum Publishers, NYC, 1999
  2. C. C. Oyarzun, D. J. Kropaczek, S. B. Sutton and W. E. Russell, 'The Global Nuclear Fuel Optimization System for BWR Fuel Cycle Management,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003.
  3. H. Q. Lam, D. Sato, D.C. Little and F. D. Popa, 'LP-FUN Applications to Reload Design,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  4. I. A. Ben Hmaida, J. N. Carter, C. R. E. de Oliviera. A. J. H. Goddard and G. T. Parks, 'Nuclear In-Core Fuel Management Optimization using the Tabu Search Method,' Proceedings of Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, 1658, 1999
  5. F. Glover, 'Tabu Search Part I,' ORSA Journal on Computing, 1, 190, 1989 https://doi.org/10.1287/ijoc.1.3.190
  6. C. Martin del Campo and J. L. Fracois, 'A Two Steps Optimization Process Using Genetic Algorithms and TABU Search Methods for the BWR Axial Fuel Assembly Design,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  7. P. J. M. van Laarhoveen and E. H. L. Aarts, Simulated Annealing: Theory and Applications, D. Reidel Publishing Company, Dordrecht, Holland, 1987
  8. E. Aarts and J. Korst, Simulated Annealing and Boltzmann Machines ？ A Stochastic Approach to Combinatorial Optimization and Neural Computing, John Wiley and Sons, New York, 1989
  9. D. J. Kropaczek, P. J. Turinsky, G. I. Maldonado and G. T. Parks, 'The Efficiency and Fidelity of the In-Core Fuel Management Code FROMOSA-P,' International Conference on Reactor Physics and Reactor Computations, Tel Aviv, 572, INS/ENS, 1994
  10. D. J. Kropaczek and P. J. Turinsky, 'In-Core Nuclear Fuel Management Optimization for PWRs Utilizing Simulated Annealing,' Nuclear Technology, 95, 9, 1991
  11. B. R. Moore, P. J. Turinsky and A. A. Karve, 'FORMOSA - B: A Boiling Water Reactor In-Core Fuel Management Optimization Package,' Nuclear Technology, 126, 153, 1999
  12. A. A. Karve and P. J. Turinsky, 'FORMOSA-B: A Boiling Water Reactor Incore Fuel Management Optimization Package II,' Nuclear Technology, 131, 48, 2000
  13. A. A. Karve and P. J. Turinsky, 'FORMOSA-B: A Boiling Water Reactor Incore Fuel Management Optimization Package III,' Nuclear Technology, 135, 241, 2001
  14. G. T. Parks, P. J. Turinsky and G. I. Maldonado, 'Solving the PWR Reload Core Optimization Problem,' Paper CIN-90-0095-I, 1991 IBM Supercomputing Competition, Third Prize- Engineering Category, 281, 1991
  15. A. Yamamoto and H. Hashimoto, 'Applications of Temperature Parallel Simulated Annealing to Loading Pattern Optimizations of Pressurized Water Reactors,' Proceedings of Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, 1445, 1999
  16. I. M. Stancu-Minasian, Stochastic Programming with Multiple Objective Functions, D. Reidel Publishing Company, Hingham, MA, 1984
  17. G. T. Parks and A. Suppapitnarm, 'Multiobjective Optimization of PWR Reload Core Designs using Simulated Annealing,' Proceedings of Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, 1435, 1999
  18. P. Engrand, 'A Multi-Objective Approach Based on Simulated Annealing and its Application to Nuclear Fuel Management,' Proceedings of 5th International Conference on Nuclear Engineering, Nice, France, 1997
  19. D. E. Goldberg, Genetic Algorithms in Search, Optimization and Machine Learning, Addison-Wesley Publishing Company, New York, 1989
  20. P. M. Keller, 'Adaptive Constrained Multiobjective Genetic Algorithm for Incore Fuel Management Optimization,' Transactions of the American Nuclear Society, 92, 2005
  21. A. K. Ziver, J. N. Carter, C. C. Pain, C. R. E. de Oliveira, A. J. H. Goddard and R. S. Overton, 'An Automated Tool Based on Genetic Algorithms to Optimize the Design of Individual Fuel Assemblies,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  22. E. W. Klee, T. Gou and G. I. Maldonado, 'A Coupling of Within-Bundle Loading Optimization to Lattice Physics Calculations,' Proceedings of Advances In Nuclear Fuel Management II Topical Meeting, 17-47, Myrtle Beach, SC, 1997
  23. Y. Hirano, K. Hida, K. Sakurada and M. Yamamoto, 'Optimization of Fuel Rod Enrichment Distribution for BWR Fuel Assembly,' PHYSOR'96 Topical Meeting, Mito, Japan (1996)
  24. C. A. Daubert, D. J. Kropaczek and W. E. Russell, 'Fuel Rod Optimization for Coupled BWR Fuel Bundle and Core Design,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  25. M. A. Jessee, Coupled Bundle-Core Design Using Fuel Rod Optimization for Boiling Water Reactors, Master of Nuclear Engineering Project Report, Department of Nuclear Engineering, North Carolina State University, 2005
  26. G. I. Maldonado and P. J. Turinsky, 'Application of Non-Linear Nodal Diffusion Generalized Perturbation Theory to Nuclear Fuel Reload Optimization,' Nuclear Technology, 110, 198, 1995
  27. G. I. Maldonado, P. J. Turinsky and D. J. Kropaczek, 'Constrained Minimization of Fresh Reload Fuel Enrichment Within the FORMOSA Codes Nodal GPT Optimization Framework,' Nuclear Science and Engineering, 121, 312, 1995
  28. X. Mouney, 'ARPEGE, The EDF Tool for Core Reload Design,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  29. F. C. M. Verhagen and P. H. Wakker, 'ROSA, A Flexible Loading Pattern Optimization Tool for PWRs,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  30. P. M. Keller, 'FORMOSA-P Advanced GA Methodology,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  31. J. A. Van de Velde, J. K. Axmann and H.-W. Bolloni, 'Recent Issues in Automated Fuel Management Optimization with Adaptive Evolutionary Algorithms,' Proceedings of Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, 1479, 1999
  32. Y. P. Mahlers, 'Core Reload Optimization for Equilibrium Cycles Using Simulated Annealing and Successive Linear Programming,' Annals of Nuclear Energy, 22(11), 1327, 2002 https://doi.org/10.1016/S0306-4549(01)00113-X
  33. J. E. Hoogenboom, R. van Geemert, A. J. Quist, T. Terlaky and C. Roos, 'New Ways for Optimizing Equilibrium Reactor Reload Patterns,' Proceedings of Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, 1469, 1999
  34. S. Jagawa, 'Improved Control Rod Adjustment Model in the Loading Pattern Optimization Code FINELOAD-3,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  35. P. M. Keller and P. J. Turinsky, 'FORMOSA-P 3-D/2-D Geometry Collapse Methodology,' Nuclear Science and Engineering, 139, 235, 2001
  36. H. Zhang, 'GNF BWR Core Simulator Improved Instrument Adaptive and Rejection Method for On-line Core Monitoring,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  37. A. S. DiGiovine and A. Noel, 'GARDEL-PWR: Studsvik's Online Monitoring and Reactivity Management System,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  38. L. J. Covington and A. Noel, 'GARDEL-BWR: Advanced BWR Online Core Monitoring,' Proceedings of Advances In Nuclear Fuel Management III Topical Meeting, Hilton Head, SC, 2003
  39. Y. A. Chao, D. M. Chapman, D. J. Hill and L. R. Grobmyer, 'Dynamic Rod Worth Measurement,' Nuclear Technology, 132, 403, 2000
  40. H. W. Engl, M. Hanke and A. Neubauer, Regularization of Inverse Problems, Kluwer Academic Publishers, 1996
  41. A. N. Tikhonoiv, 'Regularization of incorrectly posed problems,' Soviet Mathematics Doklady, 4, 1624, 1963
  42. A. Tarantola, Inverse Problem Theory Methods for Data Fitting and Model Parameter Estimation, Elsevier Science Publishers B. V., 1998
  43. A. N. Tikhonov, Numerical Methods for the Solution of Ill-Posed Problems, Kluwer Academic Publishers, 1995
  44. M. Bertero and P. Boccacci, Introduction to Inverse Problems in Imaging, Institute of Physics Publishing, Bristol, 1998
  45. H. S. Abdel-Khalik and P. J. Turinsky, 'Adaptive Core Simulation, Part I: Theory,' Nuclear Technology, 150, 2005
  46. H. S. Abdel-Khalik and P. J. Turinsky, 'Adaptive Core Simulation, Part II: Numerical Experiments,' Nuclear Technology, 150, 2005
  47. H. S. Abdel-Khalik, Adaptive Core Simulation, Ph.D. Dissertation, Department of Nuclear Engineering, North Carolina State University, 2004
  48. H. S. Abdel-Khalik and P. J. Turinsky, 'Evaluation of Core Attributes Uncertainties due to Input Data Uncertainties,' Transactions of the American Nuclear Society, 92, 2005
  49. H. W. Engl and W. Grever, 'Using the L-Curve for determining optimal regularization parameters,' Numerische Mathematik, 69, 25, 1994 https://doi.org/10.1007/s002110050078
  50. H. S. Abdel-Khalik and P. J. Turinsky, 'Inverse Method Applied to adaptive Core Simulation,' Mathematics and Computation 2003: Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew, Gatlinburg, 064, 2003
  51. H. S. Abdel-Khalik and P. J. Turinsky, 'Adaptive Core Simulation: Efficient Sensitivity Analysis,' Proceedings of Advances in Nuclear Fuel Management-III Topical Meeting, ANS, Hilton Head, 19-08, 2003