2007 International RERTR Meeting
Abstracts and Available Papers Presented at the Meeting
Measurement of Gamma Field Parameters in Core with LEU Fuel IRT-4M Using TL Detectors
T. Bily
Department of Nuclear Reactors
Faculty of Nuclear Sciences and Physical Engineering
Czech Technical University in Prague
V Holesovickach 2, 180 00, Prague 8, Czech Republic
ABSTRACT
Thermoluminescent dosimeters represent very useful tool for gamma fields parameters measurements at nuclear research reactors, especially at zero power ones. 7LiF:Mg,Ti and 7LiF:Mg,Cu,P type TL dosimeters enable determination of only gamma component in mixed neutron - gamma field. At VR-1 reactor operated within the Faculty of Nuclear Sciences and Physical Engineering at the Czech Technical University in Prague the integral characteristics of gamma rays field were investigated, especially its spatial distribution and time behaviour, i.e. the non-saturated delayed gamma ray emission influence. Measured spatial distributions were compared with monte carlo code MCNP5 calculations. Although MCNP cannot generate delayed gamma rays from fission, the relative gamma dose rate distribution is within ± 15% with measured values. The experiments were carried out with core configuration C1 consisting of LEU fuel IRT-4M (19.7 %).
Full paper in PDF format
- Measurement of
Gamma Field Parameters in Core with LEU Fuel IRT-4M
Using TL Detectors, T. Bily
[PDF, 243KB, 7 pages]
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Contact:
Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161