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Neutronic Analysis For Nuclear Reactor Systems pp 467–482Cite as

Numerical Modeling for Time-Dependent Problems

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Abstract

The possibility of a plutonium-fueled nuclear-powered reactor, such as a fast-breeder reactor that could produce more fuel than it consumed, was first raised during World War II in the United States by scientists involved in Manhattan Project and the US Atomic Bomb Program. In the past two decades, the Soviet Union, the United Kingdom, France, Germany, Japan, and India followed the United States in developing a nationalized plutonium-breeder reactor programs, while Belgium, Italy, and the Netherlands collaborated with the French and German programs. In all of these programs, the main driver of this effort was the hope of solving the long-term energy supply problem using the large-scale deployment of fissional nuclear energy for electric power. Breeder reactors, such as plutonium-fueled breeder reactors, appeared to offer a way to avoid a potential shortage of the low-cost uranium required to support such an ambitious vision using other kinds of reactors, including today’s new generation of power reactors known as GEN-IV.

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References

  1. T.B. Cochran, H.A. Feivesion, W. Patterson, G. Pshakin, M.V. Raman, M. Schneider, T. Suzuki, F. von Hipple, Fast Breeder Reactor Programs: History and Status. Research Report 8, International Panel on Fissile Materials, February 2010. Released by www.fissilematerials.org

  2. H. Kouts, The development of breeder reactors in the United States. Annu. Rev. Energy 8, 383 (1983)

    Article  Google Scholar 

  3. T.B. Cochran, The plutonium burner, in Proceeding of the International Conference on Plutonium, Omiya, Japan, November 2–4, 1991, pp. 119–151

    Google Scholar 

  4. B. Zohuri, Combined Cycle Driven Efficiency for Next Generation Nuclear Power Plants: An Innovative Design Approach (Springer, New York, 2015)

    Google Scholar 

  5. B. Zohuri, Application of Compact Heat Exchangers for Combined Cycle Driven Efficiency in Next Generation Nuclear Power Plants: A Novel Approach (Springer, Cham, 2015)

    Google Scholar 

  6. B. Zohuri, P.J. McDaniel, C.R. De Olivera, Advanced nuclear open air-Brayton cycles for highly efficient power conversion. Nucl. Technol. 192(1), 48–60 (2015)

    Article  Google Scholar 

  7. C. Forsberg, P.J. McDaniel, B. Zohuri, Variable electricity and steam from salt, helium, and sodium cooled base-load reactors with gas turbines and heat storage, in Proceedings of ICAPP 2015, May 03–06, 2015 – Nice (France) Paper 15115

    Google Scholar 

  8. B. Zohuri, P. McDaniel, Cassiano R. R. De Oliveira, A comparison of a recuperated open cycle (air) Brayton power conversion system with the traditional steam Rankine cycle for the next generation nuclear power plant. Nucl. Technol. 192(1), 48–60 (2015) https://doi.org/10.13182/NT14-42

    Article  Google Scholar 

  9. B. Zohuri, Innovative Open Air Brayton Combined Cycle Systems for the next Generation Nuclear Power Plants (University of New Mexico Publications, Albuquerque, 2014)

    Google Scholar 

  10. P.J. McDaniel, B. Zohuri, C.R.E. de Oliveira, A combined cycle power conversion system for small modular LMFBRs, in ANS Transactions, September 2014

    Google Scholar 

  11. B. Zohuri, P. McDaniel, C.R.E. de Oliveira, A comparison of a recuperated open cycle (air) Brayton power conversion system with the traditional steam Rankine cycle for the next generation nuclear power plant. Trans. Am. Nucl. Soc. 110, 391 (2014)

    Google Scholar 

  12. P.J. McDaniel, C.R.E. de Oliveira, B. Zohuri, J. Cole, A combined cycle power conversion system for the next generation nuclear power plant. Trans. Am. Nucl. Soc. 107, 858 (2012)

    Google Scholar 

  13. F. Alcaro, S. Dulla, G. Marleau, E.H. Mund, P. Ravetto, Development of dynamic models for neutron transport calculations. II Nuovo Cimento C 33, 13–20 (2010)

    Google Scholar 

  14. R.C. Aiken, Stiff Computation (Oxford University Press, New York, Oxford, 1985)

    MATH  Google Scholar 

  15. A. Aboanber, Tanta University stiffness treatment of differential equations for the point reactor dynamic systems. Prog. Nucl. Energy 71, 248–257 (2014)

    Article  Google Scholar 

  16. F. Alcaro, S. Dulla, P. Ravetto, R. Le Tellier, C. Suteau, Implementation of the quasi-static method for neutron transport, in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011) Rio de Janeiro, RJ, Brazil, May 8–12, 2011, on CD-ROM, Latin American Section (LAS)/American Nuclear Society (ANS) ISBN 978-85-63688-00-2

    Google Scholar 

  17. K.O. Ott, D.A. Meneley, Accuracy of the quasistatic treatment of spatial reactor kinetics. Nucl. Sci. Eng. 36, 402–411 (1969)

    Article  Google Scholar 

  18. J. Devooght, Quasistatic solutions of reactor kinetics. Ann. Nucl. Energy 7, 47–58 (1980)

    Article  Google Scholar 

  19. J. Devooght, E.H. Mund, Generalized quasistatic method for space-time kinetics. Nucl. Sci. Eng. 76, 10–17 (1980)

    Article  Google Scholar 

  20. S. Dulla, E.H. Mund, P. Ravetto, The quasi-static method revisited. Prog. Nucl. Energy 50, 908–920 (2008)

    Article  Google Scholar 

  21. P. Picca, S. Dulla, E.H. Mund, P. Ravetto, G. Marleau, Quasi-static time-dependent computational tool using the DRAGON transport code, in PHYSOR2008, Interlaken, September 14–19, 2008

    Google Scholar 

  22. S. Goluoglu, H.L. Dodds, A time-dependent, three-dimensional neutron transport methodology. Nucl. Sci. Eng. 139, 248–261 (2001)

    Article  Google Scholar 

  23. S. Yun, J.W. Kim, N.Z. Cho, Monte Carlo space-time reactor kinetics method and its verification with time-dependent SN method, in PHYSOR 2008, Interlaken, September 14–19, 2008

    Google Scholar 

  24. S. Dulla, E.H. Mund, The quasi-static method revisited. Prog. Nucl. Energy 50(8), 908–920 (2008)

    Article  Google Scholar 

  25. H.A. Bethe, J.H. Tait, An estimate of the order of magnitude of the explosion when the core of a fast reactor collapses. UKAEA-RHM, 1956

    Google Scholar 

  26. B. Zohuri, Applied Technology Publication on inherent shutdown heat removal system for fast breeder reactors for Division of Reactor Research and Technology, U.S. Department of Energy

    Google Scholar 

  27. B. Zohuri, Heat Pipe Design and Technology: Modern Applications for Practical Thermal Management, 2nd edn. (Springer, Switzerland, 2016)

    Book  Google Scholar 

  28. B. Zohuri, Heat Pipe Design and Technology: A Practical Approach (CRC and Francis Taylor Publishing Company, CRC Press, Boca Raton, FL, 2012)

    Google Scholar 

  29. R. Webb, Catastrophic nuclear accident hazards – a warning for Europe, Hinkley Point C Inquiry document S1982, p. 83

    Google Scholar 

  30. W.T. Sha, A.E. Walter, An integrated model for analyzing disruptive accident in fast reactors. Nucl. Sci. Eng. 44(2), 135–156 (1971)

    Article  Google Scholar 

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Authors and Affiliations

  1. Galaxy Advanced Engineering, Inc., University of New Mexico, Albuquerque, NM, USA

    Bahman Zohuri

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Zohuri, B. (2019). Numerical Modeling for Time-Dependent Problems. In: Neutronic Analysis For Nuclear Reactor Systems. Springer, Cham. https://doi.org/10.1007/978-3-030-04906-5_14

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  • DOI: https://doi.org/10.1007/978-3-030-04906-5_14

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  • Publisher Name: Springer, Cham

  • Print ISBN: 978-3-030-04905-8

  • Online ISBN: 978-3-030-04906-5

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