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The Definition and Computation of Average Neutron Lifetimes

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Advances in Nuclear Science and Technology

Part of the book series: Advances in Nuclear Science and Technology ((ANST,volume 15))

Abstract

A precise physical definition is offered for a class of average lifetimes for neutrons in an assembly of materials, either multiplying or not, or if the former, critical or not. A compact theoretical expression for the general member of this class is derived in terms of solutions to the transport equation. Three specific definitions are considered. Particular exact expressions for these are derived and reduced to simple algebraic formulas for one-group and two-group homogeneous bare-core models.

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References

  1. Beckurts, K. H., Nuclear Instruments and Methods 11, Pages 144–168, 1961.

    Article  ADS  Google Scholar 

  2. DeSaussure, G., Nuclear Science Engineering 12, Pages 433–435, 1962.

    Google Scholar 

  3. Simmons, B. E. and King, J. S., “A Pulsed Neutron Technique for Reactivity Determination,” Nuclear Science and Engineering 3, Pages 595–608, 1958.

    Google Scholar 

  4. Orndoff, J. D., “Prompt Neutron Periods of Metal Critical Assemblies,” Nuclear Science and Engineering, 2, Pages 450–460, 1957.

    Google Scholar 

  5. Henry, A. F., “The Application of Reactor Kinetics to the Analysis of Experiments,” Nuclear Science and Engineering, 3, Pages 52–70, 1958.

    Google Scholar 

  6. Marotta, C. R., “Neutron Utilization Parameter for Complex Coupled Systems,” Nuclear Science and Engineering, 77, Page 107, 1981.

    Google Scholar 

  7. Doming, J. J., “Point Kinetics with ω-Mode Shape Function Via Multiple-Time-Scale Asymptotics,” Transactions American Nuclear Society, 34, Page 281, 1980.

    Google Scholar 

  8. Ussachoff, L. N., “Equations for Importance of Neutrons, Reactor Kinetics and Perturbation Theory,” Proceedings International Conference on the Peaceful Uses of Atomic Energy, Vol. 5, Pages 503–570, 1955.

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Author information

Authors and Affiliations

  1. Department of Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts, USA

    Allan F. Henry

Authors
  1. Allan F. Henry
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Editor information

Editors and Affiliations

  1. Cambridge University, Cambridge, England

    Jeffery Lewins

  2. Rensselaer Polytechnic Institute, Troy, New York, USA

    Martin Becker

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© 1983 Plenum Press, New York

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Henry, A.F. (1983). The Definition and Computation of Average Neutron Lifetimes. In: Lewins, J., Becker, M. (eds) Advances in Nuclear Science and Technology. Advances in Nuclear Science and Technology, vol 15. Springer, Boston, MA. https://doi.org/10.1007/978-1-4613-3757-7_2

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  • DOI: https://doi.org/10.1007/978-1-4613-3757-7_2

  • Publisher Name: Springer, Boston, MA

  • Print ISBN: 978-1-4613-3759-1

  • Online ISBN: 978-1-4613-3757-7

  • eBook Packages: Springer Book Archive

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