Analysis of gamma-ray dosimetry experiments in the zero power MINERVE facility
- CEA, DEN, DER, F-13108 Saint-Paul-lez-Durance (France)
- Aix-Marseille Univ., LCP UMR 6264, 13397, Marseille (France)
The objective of this study is to develop nuclear heating measurement methods in zero power experimental reactors. These developments contribute to the qualification of photonics calculation schemes for the assessment of gamma heating in the future Jules Horowitz Material Testing Reactor. This paper presents the analysis of thermoluminescent detector (TLD) experiments in the UO{sub 2} core of the MINERVE Research Reactor at the French Alternative Energies and Atomic Energy Commission center in Cadarache. The experimental sources of uncertainty in the gamma dose have been reduced by improving the measurement conditions and the repeatability of the calibration step for each individual TLD. The interpretation of these measurements needs to take into account the calculation of cavity correction factors related to calibration and irradiation configurations, as well as neutron correction calculations. These calculations are based on Monte Carlo simulations of neutron-gamma and gamma-electron transport coupled particles. The comparison between calculated and measured integral gamma-ray absorbed doses in the aluminum material surrounding the TLD shows that calculations slightly overestimate the measurement, with a calculated versus experimental ratio equal to 1.04 {+-} 5.7 % (k=2). (authors)
- Research Organization:
- American Society for Testing and Materials - ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA, 19428-2959 (United States); European Working Group on Reactor Dosimetry - EWGRD, SCK.CEN, Mol (Belgium)
- OSTI ID:
- 22086960
- Report Number(s):
- INIS-US--13-ISRD-14-os5p-4
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALUMINIUM
CALIBRATION
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CORRECTIONS
DOSIMETRY
ELECTRONS
GAMMA RADIATION
IRRADIATION
JULES HOROWITZ REACTOR
MATERIALS TESTING
MONTE CARLO METHOD
NEUTRONS
RADIATION DOSES
RADIATION HEATING
RADIATION TRANSPORT
RESEARCH REACTORS
URANIUM DIOXIDE