الفهرس 
Chapter One: IntroductionOnly 14 pages are availabe for public view
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Abstract
Protection against artificial radioactivity including neutrons and gamma radiations is a necessary goal and not an easy task. This work is mainly
aimed to construct a neutron – shield material, in order to protect
radiation workers and public with an acceptable degree of success.
During the first part of this work, neutron shielding properties of concrete
containing different amounts of addibond- 65 and sika bond compounds
were investigated. The second part concerned with CR-39 detectors that
irradiated with fission fragments and neutron source in order to study the
optical and chemical properties after irradiation.
This thesis contains three chapters viz., introduction, experimental
techniques, and results and discussion.
Chapter one discusses different topics, such as radiation shielding, x-rays
and gamma rays shielding, lead as gamma shielding, neutron shielding,
iron as shield, neutron discovery, properties, sources interaction,
classification, and detection. Also this chapter discusses and shed light
on solid-state nuclear track detectors (SSNTDs), etching and chemical
processes.
Chapter two includes, in details, the structure of the prepared samples
used in this study, the steps of preparation, some information about the
devices used in this study as XRF machine, compressive strength
machine, irradiation facility, etching facility, and track counting system
(optical microscope).
Chapter three contains the overall results from this work such as data
analysis and the extracted results such as the half value layer, linear and
mass attenuation coefficients for the two prepared groups. It contains
also a study of the dependences of the induced proton track density on
the fast neutron doses using Am-Be neutron source,
In addition, modifications of structural, optical, and carbonaceous
clusters in neutron irradiated CR-39 polymeric detector have been
measured using UV-Visible spectrometer and FTIR spectroscopy. Also
a calibration factor between track density – optical absorbance for using
CR-39 in neutron dosimetry was discussed in this chapter.