Transfort of 14 MeV and fission spectrum neutrons through spheres — an aid to shielding design

doi:10.1016/0029-554X(81)90377-3

Nuclear Instruments and Methods in Physics Research

Volume 187, Issues 2–3, 15 August 1981, Pages 483-488

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Abstract

The energy spectra of neutrons leaking from spheres with 14 MeV of fission sources at their centers have been calculated with a Monte Carlo neutron transport code as a function of spherical radius and material. These results can be used as a guide in the initial design of shielding and collimation for experiments where d-t fusion or fission spectrum neutrons are involved. Materials investigate are: CH₂, borated CH₂, magnetite, Fe, Cu, W, Pb, and ²³⁸U.

References (3)

MCNP-A general Monte Carlo code for neutron and photon transport, Los Alamos Group X-6, LA-7396-M,...

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Cited by (1)

Multiple scattering from an infinite plane slab
1983, Nuclear Instruments and Methods In Physics Research
A straightforward iterative procedure is used to calculate multiple scattering from an infinite slab over a wide range of slab thicknesses. For thin slabs, the calculations agree well with earlier work. In particular, we find that the ratio of total scattered to primary scattered neutron currents for a thin slab is represented by the function $1 (1−δ)$ , where δ is the ratio of secondary to primary currents. For thick slabs, the results are compared with Monte Carlo simulations of polyethylene and iron. The agreement is generally good, but the method exaggerates the ability of polyethylene to attenuate 10 MeV neutrons. A model of two parallel slabs is used to discuss the reflectivity of the walls of a neutron collimator.

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Nuclear Instruments and Methods in Physics Research

Transfort of 14 MeV and fission spectrum neutrons through spheres — an aid to shielding design

Abstract

Multiple scattering from an infinite plane slab