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Extrapolation Lengths in Pulsed Neutron Diffusion Measurements

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Advances in Nuclear Science and Technology

Part of the book series: Advances in Nuclear Science and Technology ((ACRE,volume 10))

Abstract

The pulsed neutron source method has been widely used for the determination of thermal neutron diffusion parameters of various materials. Descriptions of the method and reviews of performed work have been given by several authors (1, 2, 3, 4). As can be seen from these works, there are many difficulties both on the experimental side and in the theoretical interpretation. In fact, several discrepancies exist between the results of different experimentalists and also between results from the pulsed source method and from other types of experiments. In later years, many theoretical papers have considerably advanced the understanding of the problems. It is regrettable that they were not available when most of the experiments were performed.

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Authors and Affiliations

  1. Department of Reactor Physics, Chalmers University of Technology, S-40220, Göteborg, Sweden

    N. G. Sjöstrand

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  1. N. G. Sjöstrand
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Editors and Affiliations

  1. University of Houston, Houston, Texas, USA

    Ernest J. Henley

  2. University of London, London, England

    Jeffery Lewins

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

    Martin Becker

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© 1977 Plenum Press, New York

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Sjöstrand, N.G. (1977). Extrapolation Lengths in Pulsed Neutron Diffusion Measurements. In: Henley, E.J., Lewins, J., Becker, M. (eds) Advances in Nuclear Science and Technology. Advances in Nuclear Science and Technology, vol 10. Springer, Boston, MA. https://doi.org/10.1007/978-1-4613-9913-1_2

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