Commissioning Dosimetry and Dose Mapping of the Tunisian Gamma Irradiation Facility and Comparison with MCNP Monte Carlo Simulation
Creators
- 1. Laboratory of Energy and Matter for Development of Nuclear Science (LR16CNSTN02), NationalCenter of Nuclear Science and Technology, Sidi-Thabet Technopark 2020 Ariana (Tunisia)
- 2. Université de Sousse, Institut Supérieur du Transport et de la Logistique, Sousse, 4023 (Tunisia)
Description
Cobalt-60 irradiation facility has been put into operation at the National Centre of Nuclear Sciences and Technology at Sidi-Thabet in Tunisia. Technical specifications were checked by dosimetry commissioning experiments and compared to Monte Carlo simulation data using MCNP. Installation qualification has been carried out to measure absorbed dose distribution in the irradiation cell and products. Two dosimeter systems were employed for measurements: Red and Amber Perspex and Cellulose Triacetate (CTA). The regions of minimum and maximum absorbed dose within a homogeneous dummy products and the dose uniformity ratio were determined. The products were loaded in carrier by sawdust with a bulk density of 0.114 g/cm3, potato with a bulk density 0.58 g/cm3 and syringe with a bulk density 0.123 g/cm3. The isodose curves and the three dimensional views were built using the kriging method. An acceptable agreement in most sets between Monte Carlo simulation results and the experimental values.
Additional details
Publishing Information
- Imprint Title
- International Conference on Radiation Safety: Improving Radiation Protection in Practice. Extended Abstracts (Virtual Event)
- Imprint Pagination
- 612 p.
- Journal Page Range
- p. 583
- Report number
- IAEA-CN--279
Conference
- Title
- Improving Radiation Protection in Practice
- Acronym
- International Conference on Radiation Safety
- Dates
- 9-20 Nov 2020
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52124316
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S07: ISOTOPES AND RADIATION SOURCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ABSORBED RADIATION DOSES; BULK DENSITY; CELLULOSE; COBALT 60; COMPUTERIZED SIMULATION; DOSEMETERS; DOSIMETRY; GAMMA RADIATION; IRRADIATION; IRRADIATION PLANTS; ISODOSE CURVES; KRIGING; MAPPING; MONTE CARLO METHOD; OPERATION; PERSPEX; RADIATION DOSE DISTRIBUTIONS; SPECIFICATIONS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; CARBOHYDRATES; COBALT ISOTOPES; DENSITY; DOSES; ELECTROMAGNETIC RADIATION; ESTERS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IONIZING RADIATIONS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MATHEMATICS; MEASURING INSTRUMENTS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FACILITIES; NUCLEI; ODD-ODD NUCLEI; ORGANIC COMPOUNDS; ORGANIC POLYMERS; PETROCHEMICALS; PETROLEUM PRODUCTS; PHYSICAL PROPERTIES; PLASTICS; POLYACRYLATES; POLYMERS; POLYSACCHARIDES; POLYVINYLS; RADIATION DOSES; RADIATIONS; RADIOISOTOPES; SACCHARIDES; SIMULATION; STATISTICS; SYNTHETIC MATERIALS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 3 refs.
- Secondary number(s)
- IAEA-CN--279-367