Fission Density Distribution Research Articles

Validation of ENDF/B-VI.2, JEF-2.2 and JENDL-3.2 through MCNP analysis of BWR-simulated critical experiments

The ENDF/B-VI.2, JEF-2.2 and JENDL-3.2 evaluated nuclear data were validated and intercompared for applications in light water reactor analyses. A set of twelve BWR-simulated critical experiments at temperatures representative of cold as well as operating conditions was analyzed by using the MCNP-4A code with continuous energy data. Calculated eigenvalue and fission density distribution results from the MCNP simulations coupled with each of three different nuclear data files showed good agreements with the measurements in the all considered cores.

Automated calculation of fission events in experiments on critical assemblies

The problems of automating the calculation of fission fragments in experiments to estimate fission density distribution in critical assemblies are considered.

Fine Structure Measurement of Fission Density Distribution in UO2Cell Using Solid

Fine Structure Measurement of Fission Density Distribution in UO₂Cell Using Solid

Fine Structure Measurement of Fission Density Distribution in UO2 Cell Using Solid State Track Detector

Fine Structure Measurement of Fission Density Distribution in UO2 Cell Using Solid State Track Detector

On the use of solid state nuclear track detectors in reactor physics experiments

Abstract Solid state nuclear track detectors of silver-activated phosphate glass and polycarbonate plastic have provided intracell fission density and fast neutron flux distributions in the zero-power critical facility NORA (Institutt for Atomenergi, Kjeller, Norway). The fission density distributions were measured in a clean lattice and within fuel elements in the vicinity of grey absorber control elements. The measured intracell fast neutron flux distributions were used for the evaluation of the so-called ‘fast advantage factors’ (fuel-to-moderator neutron flux ratios at fission energies). Integral measurements of the fast advantage factors were performed by foil activation. As far as the experimental results presented here could be compared with theoretical calculations a good agreement was found. For the measurement of the track density distributions along the detector surface a method was developed which replaces the counting procedure of tracks under a microscope. This method is based upon the relation between track density and intensity of transmitted light through irradiated and etched detectors, whereby a microdensitometer is used for the measurement of the light transmission. Some remarks about the fast neutron sensitivity of Makrofol polycarbonate plastic will be made.