The capacity of a research reactor for utilization in terms of radioisotope production, materials testing, neutron transmutation and neutron diffraction is directly related to the magnitude of the neutron flux and to the nature of the neutron spectra present at the irradiation sites. Hence, the optimization of neutron fluxes and spectra in experimental channels is of great concern in research reactor utilization. A general safety analysis approach used at the NUR research reactor prior to neutron flux optimization in irradiation channels is presented in this paper. The approach is, essentially, based upon a judicious optimization of core configuration, combined with the improvement of reflector characteristics. In order to allow the implementation of a new core configuration into the operation scheme of the reactor, a demonstration that such a configuration is safe and in conformity with the safety standards in application at the NUR reactor [1], as well as the IAEA standard safety guide recommendation [2], is required. A standardized safety analyses for research reactors was proposed by the IAEA [3] concerning core conversion from the use of highly enriched uranium fuel to the use of low-enriched uranium fuel. Within this framework, a detailed study, including static and dynamic calculations using advanced computational tools, has been carried out.
Safety analysis for neutron flux optimization in irradiation channels at NUR research reactor
D'AURIA, FRANCESCO SAVERIO
2006-01-01
Abstract
The capacity of a research reactor for utilization in terms of radioisotope production, materials testing, neutron transmutation and neutron diffraction is directly related to the magnitude of the neutron flux and to the nature of the neutron spectra present at the irradiation sites. Hence, the optimization of neutron fluxes and spectra in experimental channels is of great concern in research reactor utilization. A general safety analysis approach used at the NUR research reactor prior to neutron flux optimization in irradiation channels is presented in this paper. The approach is, essentially, based upon a judicious optimization of core configuration, combined with the improvement of reflector characteristics. In order to allow the implementation of a new core configuration into the operation scheme of the reactor, a demonstration that such a configuration is safe and in conformity with the safety standards in application at the NUR reactor [1], as well as the IAEA standard safety guide recommendation [2], is required. A standardized safety analyses for research reactors was proposed by the IAEA [3] concerning core conversion from the use of highly enriched uranium fuel to the use of low-enriched uranium fuel. Within this framework, a detailed study, including static and dynamic calculations using advanced computational tools, has been carried out.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
