Published January 1999
| Version v1
Journal article
Shielding calculations for ETRR-1 reactor
Creators
- 1. Reactor departement, Nuclear Research Center Cairo (Egypt)
- 2. National Center for Nuclear safety Atomic Energy Authority, Cairo, (Egypt)
Description
The flux and dose through ETRR-1 reactor shielding are calculated using ANISN code. The neutron and gamma radiation sources in the reactor core are determined by using Madland Nix Model (MNM Model ). The results show that the flux in the core is in good agreement with the reactor flux. The dose in the radial and axial shields at outside boundary is less than the maximum allowable dose
Additional details
Publishing Information
- Journal Title
- Arab Journal of Nuclear Sciences and Applications
- Journal Volume
- 33
- Journal Issue
- 3
- Journal Page Range
- p. 167-175
- ISSN
- 1110-0451
INIS
- Country of Publication
- Egypt
- Country of Input or Organization
- Egypt
- INIS RN
- 32041739
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CALCULATION METHODS; DOSE RATES; ETRR-1 REACTOR; GAMMA RADIATION; NEUTRON FLUX; NEUTRON SOURCES; POWER DISTRIBUTION; RADIATION SOURCES; REACTOR CORES; SHIELDING
- Descriptors DEC
- ELECTROMAGNETIC RADIATION; IONIZING RADIATIONS; PARTICLE SOURCES; RADIATION FLUX; RADIATION SOURCES; RADIATIONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS