Skip to main content

The State of Mathematical Modeling for Power Plant Training Simulators

  • Conference paper
Nuclear Simulation
  • 142 Accesses

Summary

This paper provides a survey of modeling technology used in power plant training simulators, identifying the capability of existing models, and commenting on the areas where modeling advances are expected to occur.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 39.99
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 54.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. “American National Standard Nuclear Power Plant Simulators for Use in Operator Training,” ANSI/ANS-3.5 - 1985.

    Google Scholar 

  2. “Analytic Simulator Qualification Methodology,” NP-3873 Research Project 2054-1, Prepared for the Electric Power Research Institute, March 1985.

    Google Scholar 

  3. Andersen, P.S., and Fabic, S., “Theoretical Foundation of an Advanced Simulation Method for Power Plant Thermo-Hydraulics,” International Conference on Simulation for Nuclear Reactor Technology, Cambridge, U.K., April 1984.

    Google Scholar 

  4. Avery, R., “Theory of Coupled Reactors,” Proceedings, 2nd International Conference on Peaceful Uses of Atomic Energy, Geneva, September 1958, pp. 182-191.

    Google Scholar 

  5. Birsa, J.J., Personal Communication, June 1987,

    Google Scholar 

  6. Boire, R., “HYDRA: An Interactive Tool for Automatic Generation of FORTRAN Code for Hydraulic Circuits,” Proceedings, Summer Simulation Conference, Society for Computer Simulation, Reno, Nevada, July 1986.

    Google Scholar 

  7. Chan, T.C., and Luffey, F.C., “Real Time Simulation of PWR Reactor Core System Transients,” paper presented at the Summer Computer Simulation Conference, Society for Computer Simulation, Denver, Colorado, July 1982.

    Google Scholar 

  8. Chan, T.C., “An Advanced Simulator Reactor Core System Model,” Proceedings, Tenth IMACS World Congress on System Simulation and Scientific Computation, Montreal, Canada, August 1982.

    Google Scholar 

  9. Chan, T.C., Personal Communication, June 1987.

    Google Scholar 

  10. Chan, T.C., “An Expansion-Based Reactor Core Model for Training Simulators,” Specialists’ Meeting on Training Simulators for Nuclear Power Plants, Toronto, Canada, September 1987.

    Google Scholar 

  11. Chao, Y.A., Suo, C.A., and Penkrot, J.A., “On the Theory of Interface Flux Nodal Method,” Proceedings, CNS/ANS International Conference on Numerical Methods in Nuclear Engineering, Montreal, Canada, September 6-9, 1983, p. 307, Canadian Nuclear Society (1983).

    Google Scholar 

  12. Chao, Y.A., Hu, C.W., and Suo, C.A., “A Theory of Fuel Management via Backward Diffusion Calculation,” Nuclear Science and Engineering 93, 78–87 (1986).

    Google Scholar 

  13. Chao,, Y.A., and Penkrot, J.A., “Diffusive Homogeneity—The Principle of the Superfast Multi-Dimensional Nodal Code, SUPERNOVA,” paper to be presented at ANS Winter Meeting, Los Angeles, California, November 15-19, 1987.

    Google Scholar 

  14. Chow, S.G., Guardalben, G.V., Wight, A.L., and Chou, Q. B., “Experience in Generation and Implementation of Coupling Coefficients for a Space-Time Kinetics Model in BWR and PWR Nuclear Training Simulators,” Supplementary Proceedings9 Eastern Simulation Conference, Society for Computer Simulation, Norfolk, Virginia, March 1986.

    Google Scholar 

  15. Deaton, I.V., Lin, E.K., Fabic, S., and Anderson, P., “Validation of the Real-Time Advanced Core and Thermohydraulic (RETACT) Code for Nuclear Power Plant Engineering Simulation,” Proceedings, Eastern Simulation Conference, Society for Computer Simulation, Orlando, Florida, April 1987.

    Google Scholar 

  16. Espinosa, R.J., Doherty, P.K., and McBeth, R.L., “Application of Thermal-Hydraulic Design Codes to Real Time PWR Simulation,” Fifth Power Plant Dynamics, Control and Testing Symposium, March 21-23, 1983, Knoxville, Tennessee.

    Google Scholar 

  17. Fabic, S., “Thermal Hydraulics in Nuclear Power Plant Simulators,” Proceedings, Third International Topical Meeting on Reactor Thermal Hydraulics, Newport, Rhode Island, October 1985.

    Google Scholar 

  18. Gregory, M.V., Aviles, B.N., and Yakura, S.J., “A Three-Dimensional Neutronics Model for Reactor Training Simulators,” Nuclear Science and Engineering 92, 372–381 (1986)

    Google Scholar 

  19. Hoang, T.D., and Morin, P., “A Method of Calculation of Coupling Coefficients for a Reactor Core Nodal Model,” Proceedings, Summer Simulation Conference, Society for Computer Simulation, Reno, Nevada, July 1986.

    Google Scholar 

  20. Hsu, H.H., Lea, K.C., and Shen, P., “Three-Dimensional Core Model for Nuclear Power Plant Simulation,” Proceedings, Summer Simulation Conference, Society for Computer Simulation, Vancouver, B.C., July 1983.

    Google Scholar 

  21. IDCOR Technical Summary Report, “Nuclear Power Plant Response to Severe Accidents,” Technology for Energy Corporation, Knoxville, Tennessee, November 1984.

    Google Scholar 

  22. Lin, E.K., Jen, C.L., Fabic, S., and Andersen, P.S., “Advanced Modeling of Power Plant Simulators,” International Conference on Simulation for Nuclear Reactor Technology, Cambridge, U.K., April 1984.

    Google Scholar 

  23. Lin, E.K., Jen, C.L., Fabic, S., and Andersen, P.S., “Thermo-Hydraulic Models in Link’s Advanced Power Plant Simulator,” 23rd ASME/AIChE/ANS National Heat Transfer Conference, August 6-9, 1985, Denver, Colorado.

    Google Scholar 

  24. Luffey, F.C., Murphy, J.H., and Meyer, P.E., “Advanced Techniques for Real Time Simulation of Reactor Coolant Two-Phase Transients,” paper presented at the CSNI Specialists’ Meeting on Operator Training and Qualifications, Charlotte, NC, October 1981.

    Google Scholar 

  25. Luffey, F.C., Murphy, J.H., Garratt, C., and Wyatt, P. W., “Advanced Techniques for Real-time Simulation of Reactor Coolant System Two-Phase Transients,” Nuclear Europe, March 1983.

    Google Scholar 

  26. McFadden, J.H., et al., “RETRAN 02 Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems,” EPRI, NP-1850-CCM, May 1981.

    Google Scholar 

  27. Meyer, P.E., Spencer, A.C., and Porsching, T.A., “An Advanced Simulator Reactor Coolant System Model,” Trans. Amer. Nucl. Soc. 38, p. 678 (June, 1981)

    Google Scholar 

  28. Moore, K V., and Rettig, W.H., “RELAP5 - A Computer Program for Transient Thermal-Hydraulic Analysis,” ANCR-1127, Revision 1, March 1975. See also “RELAP5/MOD1 Code Manual” (Vols. 1 to 3), NUREG/CR-1826.

    Google Scholar 

  29. Murphy, J.H., Redfield, J.A., and Davis, V.C., “FLASH-3: A FORTRAN IV Program for the Simulation of Reactor Plant Transients in Space and Time,” WAPD-TM-800, July 1968.

    Google Scholar 

  30. Popa, F., and Marlatt, G., “Real Time Boiling Water Reactor Core Simulation,” Proceedings, 1987 Summer Simulation Conference, Society for Computer Simulation, Montreal, Canada, July 1987.

    Google Scholar 

  31. Porsching, T.A., “A Finite Difference Method for Thermally Expandable Fluid Transients,” Nuclear Science and Engineering 64, 177–186 (1977)

    Google Scholar 

  32. Rinsma, R.S., and Shemony, R.A., Personal Communication, June 1987.

    Google Scholar 

  33. Shesler, A.T., and Wagner, S.G., “A Three-Dimensional Core Model for Personal Computers,” Proceedings, Summer Simulation Conference, Society for Computer Simulation, Reno, Nevada, July 1986.

    Google Scholar 

  34. .Siebert, W.M., Circuits, Signals, and Systems, The MIT Press, Cambridge, Massachusetts, 1986.

    Google Scholar 

  35. Ward, E.J., Chow, S., and Chou, Q.B., “Development of a Real-Time Spatial Simulation for a CANDU-Type Nuclear Reactor Using Modal Techniques,” Proceedings, Eastern Simulation Conference, Society for Computer Simulation, Orlando, Florida, April 1987.

    Google Scholar 

  36. Wulff, W., “PWR Training Simulator, An Evaluation of the Thermohydraulic Models For Its Main Steam Supply System,” BNL-NUREG-28955, September 1980.

    Google Scholar 

  37. Wulff, W., “BWR Training Simulator, An Evaluation of the Thermohydraulic Models For Its Main Steam Supply System,” BNL-NUREG-29815, March 1981.

    Google Scholar 

  38. Wyatt, P.W., Kumar, S., and Luffey, F.C., “Verified Simulation of Reactor Transients in Real Time: The TMI-2 Stuck Relief Valve and the Prairie Island Steam Generator Tube Leak,” WCAP-10028, Westinghouse Electric Corporation, February 1982.

    Google Scholar 

  39. Wyatt, P.W., and Kumar, S., “Verified Simulation of a Nuclear Reactor Transient in Real Time: Steam Generator Tube Leak,” paper presented at the Summer Computer Simulation Conference, Society for Computer Simulation, Denver, Colorado, July 1982.

    Google Scholar 

  40. Wyatt, P.W., and Luffey, F.C., “Verified Simulation of a Nuclear Reactor Transient in Real Time: Stuck Pressurizer Relief Valve,” paper presented at the 10th IMACS World Congress on System Simulation and Scientific Computation, Montreal, Canada, August 1982.

    Google Scholar 

  41. Wyatt, P.W., and Kumar. S., “Real Time Solutions of Multi-Phase Multi-Component Fluid Networks,” Proceedings, Japan Society for Simulation Technology, JSST Conference on Recent Advances in Simulation of Complex Systems, Keidamren-Kaikan, Tokyo, Japan, July 15-17, 1986.

    Google Scholar 

  42. Wyatt, P.W., Kumar, S., and Zelnis, D.G., “Applications of Various Conservation Equations to Real Time Simulation,” Proceedings, Eastern Simulation Conference, Society for Computer Simulation, Orlando, Florida, April 1987.

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Editor information

Editors and Affiliations

Rights and permissions

Reprints and permissions

Copyright information

© 1987 Springer-Verlag, Berlin, Heidelberg

About this paper

Cite this paper

Foulke, L.R. (1987). The State of Mathematical Modeling for Power Plant Training Simulators. In: Heller, M.R. (eds) Nuclear Simulation. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-83221-5_10

Download citation

  • DOI: https://doi.org/10.1007/978-3-642-83221-5_10

  • Publisher Name: Springer, Berlin, Heidelberg

  • Print ISBN: 978-3-642-83223-9

  • Online ISBN: 978-3-642-83221-5

  • eBook Packages: Springer Book Archive

Publish with us

Policies and ethics