학술논문

Transport of Accelerator Produced Neutrons in a Concrete Room
Document Type
Periodical
Source
IEEE Transactions on Nuclear Science IEEE Trans. Nucl. Sci. Nuclear Science, IEEE Transactions on. 26(1):1593-1602 Feb, 1979
Subject
Nuclear Engineering
Bioengineering
Neutrons
Concrete
Production
Electron accelerators
Personnel
Protection
Building materials
Radioactive materials
Monte Carlo methods
Degradation
Language
ISSN
0018-9499
1558-1578
Abstract
The production of photoneutrons by electron accelerators is an unavoidable process at operating energies above about 10 MeV. These photoneutrons create problems in shielding, personnel protection, and induced radioactivity. This paper attempts to describe the neutron field spectral and intensity distributions. The initial spectrum and modifying effects of photon shielding materials and concrete room shielding are considered. The relative yields of neutrons and photons as a function of the primary electron energy are described. Both experimental and Monte Carlo results are presented. It is shown that the average energy of the neutron spectrum is a useful parameter for shielding calculations, fluence-to-dose equivalent conversions, and spectral degradation calculations.