Shielding calculations for neutron calibration bunker using Monte Carlo code MCNP-4C
Creators
- 1. Atomic Energy Commission, Damascus (Syrian Arab Republic), Division of Nuclear and Radiation Regulatory
Description
In this work, the dose arising from an Am-Be source of 108 neutron/sec strength located inside the newly constructed neutron calibration bunker in the National Radiation Metrology Laboratories, was calculated using MCNP-4C code. It was found that the shielding of the neutron calibration bunker is sufficient. As the calculated dose is not expected to exceed in inhabited areas 0.183 μSv/hr, which is 10 times smaller than the regulatory dose constraints. Hence, it can be concluded that the calibration bunker can house - from the external exposure point of view - an Am-Be neutron source of 109 neutron/sec strength. It turned out that the neutron dose from the source is few times greater than the photon dose. The sky shine was found to contribute significantly to the total dose. This contribution was estimated to be 60% of the neutron dose and 10% of the photon dose. The systematic uncertainties due to various factors have been assessed and was found to be between 4 and 10% due to concrete density variations; 15% due to the dose estimation method; 4 -10% due to weather variations (temperature and moisture). The calculated dose was highly sensitive to the changes in source spectra. The uncertainty due to the use of two different neutron spectra is about 70%.(author)
Availability note (English)
Available from INIS in electronic formFiles
39110487.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 28 p.
- Report number
- AECS-TN/RSS--763
INIS
- Country of Publication
- Syrian Arab Republic
- Country of Input or Organization
- Syrian Arab Republic
- INIS RN
- 39110487
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Numerical Data
- Is Lead record
- Yes
- Descriptors DEI
- AMERICIUM; BERYLLIUM; CALIBRATION; COMPUTERIZED SIMULATION; DOSE RATES; EXPERIMENTAL DATA; M CODES; MONTE CARLO METHOD; NEUTRON SOURCES; NEUTRON SPECTRA; NEUTRONS; SHIELDING; SHIELDING MATERIALS
- Descriptors DEC
- ACTINIDES; ALKALINE EARTH METALS; BARYONS; CALCULATION METHODS; COMPUTER CODES; DATA; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; HADRONS; INFORMATION; MATERIALS; METALS; NUCLEONS; NUMERICAL DATA; PARTICLE SOURCES; RADIATION SOURCES; SIMULATION; SPECTRA; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 12 refs., 7 tabs., 14 figs.