Doctoral Dissertations

Keywords and Phrases

Border Protection; Dosimeter; Localization; Neutron Generator; Nuclear Nonproliferation; Radiation Detection

Abstract

"At certain threshold, nuclear radiation (like x-rays and gamma-rays) may adversely impact the health of living tissues. The exposure to these radiations in nuclear facilities is measured by devices called dosimeters. The devices are generally worn on the torso and are monitored by health physics division to report the radiation dose received by the personnel. However, this approach is not proactive--since the dosimeters reflect the dose that has already been absorbed in the body of the wearer.

This work presents a scheme to proactively avoid large dose acquisition at radiation-prone facilities. The work was divided into three major segments: (i) identify and characterize radioactive source(s), (ii) determine the impact of localized source(s), and (iii) estimate the integrated doses in traversing/evacuating the facility. The scope of this work does not extend to the development of "proactive" dosimeter. However, the approaches developed in these segments will be integrated into a dose monitoring system that would prevent or mitigate large dose acquisition. This work also has applications in nuclear facilities, hospitals, homeland security, and border protection"--Abstract, page iv.

Advisor(s)

Alajo, Ayodeji Babatunde

Committee Member(s)

Lee, Hyoung-Koo
Liu, Xin (Mining & Nuclear Engr)
Usman, Shoaib
Fikru, Mahelet

Department(s)

Mining and Nuclear Engineering

Degree Name

Ph. D. in Nuclear Engineering

Sponsor(s)

U.S. Nuclear Regulatory Commission

Publisher

Missouri University of Science and Technology

Publication Date

Summer 2016

Journal article titles appearing in thesis/dissertation

  • Three-dimensional localization of low activity gamma-ray sources in real-time scenarios
  • MCNP modeling of a neutron generator and its shielding at Missouri University of Science and Technology
  • Adjoint acceleration of Monte Carlo Simulations using SCALE: A radiation shielding evaluation of the neutron generator room at Missouri S&T
  • Integrated doses calculation in evacuation scenarios of the neutron generator facility at Missouri S&T

Pagination

xii, 103 pages

Note about bibliography

Includes bibliographic references.

Rights

© 2016 Manish Kumar Sharma, All rights reserved.

Document Type

Dissertation - Open Access

File Type

text

Language

English

Library of Congress Subject Headings

Radiation -- Detection
Medical radiology
Radiation dosimetry
Shielding (Radiation

Thesis Number

T 10981

Electronic OCLC #

958281154

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