Neutron and gamma ray total dose rate determination using anisn

• Published in: Radiation physics and chemistry (Oxford, England : 1993) Vol. 44; no. 1-2; pp. 119 - 123
• Main Authors: Amin, E., Ashoub, N., Elkady, A.
• Format: Journal Article
• Language: English
• Published: Elsevier Ltd 01.07.1994
• ISSN: 0969-806X; 1879-0895
• DOI: 10.1016/0969-806X(94)90117-1

The National Center for Nuclear Safety and Radiation Control is in the process of acquiring a computer software library based mainly on internationally widely used computer codes. These codes are to be used as basic tools in safety analysis and radiation control and risk assessment. A complementary part of this activity is to validate the computer codes and set standard procedures with the limits of confidence for the different areas of applications of the one or the other code or set of codes. The present work has been then initiated in order to develop a standard shielding calculating procedure to be applied for the different applications of interest to the center, namely: shielding of nuclear installations, such as the ET-RR-1 reactor, the gamma unit, nuclear accelerator, radiotherapy units; shielding of nuclear sources (mainly neutron and gamma sources); shielding of transportation containers. In developing such a standard method, the sources of error to the final results (i.e. the dose rate and dose rate distribution) have to been identified and the error to be quantified. Through applying the developed procedure to benchmark PWR shielding problems, and to documented results for fission sources in water and concrete, the levels of confidence of the procedure in different application areas have been set.