Neutron Thermalization and Diffusion in Pulsed Media
- 1 February 1961
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 9 (2) , 157-167
- https://doi.org/10.13182/nse61-a15601
Abstract
A general formalism for determining the lower time eigenvalues associated with a decaying pulse of neutrons in a finite multiplying as well as nonmultiplying medium has been developed. This formalism is based upon the expansion of each energy eigenfunction by a complete sum of the associated Laguerre polynomials of first order. The eigenvalues are expressed in terms of the energy transfer moments of the scattering kernel of the medium, weighted by the Maxwellian distribution. The importance of the first eigenvalue in the establishment of the final asymptotic energy distribution is discussed. In the case of a nonabsorbing infinite medium, the reciprocal of the first eigenvalue is shown to be equal to the thermalization time constant, with which the Maxwellian velocity distribution of neutrons is attained. The thermalization time constant was estimated for various moderators. For the heavy-gas case, the thermalization time constant was was found to be equal to (1.274 ° ζ∑s0υ0)−1. It is also established in this study that only two polynomials are required to obtain the relation between the thermalization time constant and the diffusion cooling coefficient derived previously from the Rayleigh-Ritz variational principle. The formalism presented in this paper is general and avoids the concept of neutron temperature in defining the thermalization time constant. The decay of a neutron pulse in a nonmultiplying medium is discussed in detail. For the case of multiplying medium, an analysis of an experiment is presented to indicate the importance of the time-dependent nonleakage probability in the expression of the zeroth eigenvalue.Keywords
This publication has 7 references indexed in Scilit:
- The Decay of a Thermalized Neutron PulseNuclear Science and Engineering, 1960
- Theory of Pulsed Neutron Experiments in Multiplying MediaNuclear Science and Engineering, 1959
- The Thermal Neutron Spectrum in a Diffusing MediumNuclear Science and Engineering, 1958
- Measurements with a Pulsed Neutron SourceNuclear Science and Engineering, 1957
- Special Functions of Mathematical Physics and ChemistryPhysics Today, 1956
- Diffusion Parameters of Thermal Neutrons in WaterPhysical Review B, 1954
- Current Status of Nuclear Reactor TheoryAmerican Journal of Physics, 1952