Analysis and recent advances in gamma heating measurements in MINERVE facility by using TLD and OSLD techniques
- CEA, DEN, DER/SPEx, Cadarache, F-13108 St-Paul-Lez-Durance (France)
- Laboratoire Chimie Provence, UMR 6264-Universite Aix-Marseille, Centre de Saint Jerome, F-13397 Marseille Cedex 20 (France)
The objective of this study is to develop nuclear heating measurement methods in Zero Power experimental reactors. This paper presents the analysis of Thermo-Luminescent Detector (TLD) and Optically Stimulated Luminescent Detectors (OSLD) experiments in the UO{sub 2} core of the MINERVE research reactor at the CEA Cadarache. The experimental sources of uncertainties on the gamma dose have been reduced by improving the conditions, as well as the repeatability, of the calibration step for each individual TLD. The interpretation of these measurements needs to take into account calculation of cavity correction factors, related to calibration and irradiation configurations, as well as neutron corrections calculations. These calculations are based on Monte Carlo simulations of neutron-gamma and gamma-electron transport coupled particles. TLD and OSLD are positioned inside aluminum pillboxes. The comparison between calculated and measured integral gamma-ray absorbed doses using TLD, shows that calculation slightly overestimates the measurement with a C/E value equal to 1.05 {+-} 5.3 % (k = 2). By using OSLD, the calculation slightly underestimates the measurement with a C/E value equal to 0.96 {+-} 7.0% (k = 2. (authors)
- OSTI ID:
- 22039778
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
ALUMINIUM
CALIBRATION
CEA CADARACHE
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CORRECTIONS
ELECTRON TRANSFER
GAMMA RADIATION
GAMMA TRANSPORT THEORY
IRRADIATION
MINERVE REACTOR
MONTE CARLO METHOD
NEUTRON TRANSPORT
RADIATION DOSES
RADIATION HEATING
THERMOLUMINESCENT DOSEMETERS
URANIUM DIOXIDE