Published May 2001 | Version v1
Journal article

ET-RR-2 reactor shielding calculations

  • 1. National Center for Nuclear Safety and Radiation Control, Cairo (Egypt)
  • 2. Reactor and Neutron Physics Department, Nuclear Reasearch Center, Energy Authority, Cairo (Egypt)

Description

Shielding calculations were carried out for Egypt's second research reactor ET-RR-2 using the three dimensional Monte Carlo code MULTIKENO after being modified by us to account for gamma attenuation. In this concern, MULTIKENO was developed from a Monte Carlo code for only neutron attenuation to a code for both neutron and gamma attenuation in shielding materials. Results for the total dose rate, gamma and total flux through the different reactor shielding materials in the radial direction as calculated by the new developed MULTIKENO Monte Carlo code are compared with those given in the safety analysis report (SAR) of the reactor, which are calculated using the one dimensional transport code ANISN. This comparison proved that all modifications introduced in the Monte Carlo code MULTIKENO were justified. (author)

Additional details

Publishing Information

Journal Title
Nuklearna tehnologija
Journal Volume
16
Journal Issue
1
Journal Page Range
p. 39-41
ISSN
0351-689X

Optional Information

Notes
refs. 4, figs. 3