Author:
Štancar Žiga,Kaiba Tanja,Snoj Luka,Barbot Loïc,Destouches Christophe,Fourmentel Damien,Villard Jean-François
Abstract
A series of fission rate profile measurements with miniature fission chambers, developed by the Commisariat á l’énergie atomique et auxénergies alternatives, were performed at the Jožef Stefan Institute’s TRIGA research reactor. Two types of fission chambers with different fissionable coating (235U and 238U) were used to perform axial fission rate profile measurements at various radial positions and several control rod configurations. The experimental campaign was supported by an extensive set of computations, based on a validated Monte Carlo computational model of the TRIGA reactor. The computing effort included neutron transport calculations to support the planning and design of the experiments as well as calculations to aid the evaluation of experimental and computational uncertainties and major biases. The evaluation of uncertainties was performed by employing various types of sensitivity analyses such as experimental parameter perturbation and core reaction rate gradient calculations. It has been found that the experimental uncertainty of the measurements is sufficiently low, i.e. the total relative fission rate uncertainty being approximately 5 %, in order for the experiments to serve as benchmark experiments for validation of fission rate profiles. The effect of the neutron flux redistribution due to the control rod movement was studied by performing measurements and calculations of fission rates and fission chamber responses in different axial and radial positions at different control rod configurations. It was confirmed that the control rod movement affects the position of the maximum in the axial fission rate distribution, as well as the height of the local maxima. The optimal detector position, in which the redistributions would have minimum effect on its signal, was determined.
Reference20 articles.
1. Goorley J. T., James M. R., Booth T. E., Brown F. B., Bull J. S., Cox L. J., Durkee J. W., Elson J. S., Fensin M. L., Forster R. A., Hendricks J. S., Hughes H. G., Johns R. C., Kiedrowski B. C., Martz R. L., Mashnik S. G., McKinney G. W., Pelowitz D. B., Prael R. E., Sweezy J. E., Waters L. S., Wilcox T., and Zukaitis A. J., Initial MCNP6 Release Overview - MCNP6 Version 1.0, Los Alamos National Laboratory, 2014.
2. Snoj L. and Ravnik M., “Calculation of Power Density with MCNP in TRIGA Reactor,” in Proceedings of the International Conference Nuclear Energy for New Europe 2006. Portorož, Slovenia, 18-21 September: Nuclear Society of Slovenia, 2006.
3. Calculation of kinetic parameters for mixed TRIGA cores with Monte Carlo
4. Analysis of neutron flux distribution for the validation of computational methods for the optimization of research reactor utilization
5. Jeraj R. and Ravnik M., “TRIGA Mark II Reactor: U(20)- Zirconium Hydride Fuel Rods in Water with Graphite Reactor, IEU-COMP-THERM-003,” in International Handbook of Evaluated Criticality Safety Benchmark Experiments. Paris, France: NEA/NSC/DOC(95)03, OECD NEA, 2010.
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