45 research outputs found

    An updated analysis of NN elastic scattering data to 1.6 GeV

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    An energy-dependent and set of single-energy partial-wave analyses of NNNN elastic scattering data have been completed. The fit to 1.6~GeV has been supplemented with a low-energy analysis to 400 MeV. Using the low-energy fit, we study the sensitivity of our analysis to the choice of πNN\pi NN coupling constant. We also comment on the possibility of fitting npnp data alone. These results are compared with those found in the recent Nijmegen analyses. (Figures may be obtained from the authors upon request.)Comment: 17 pages of text, VPI-CAPS-7/

    LEU-HTR critical experiment program for the PROTEUS facility in Switzerland

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    New critical experiments in the framework of an IAEA Coordinated Research Program on `Validation of Safety Related Reactor Physics Calculations for Low-Enriched HTR's' are planned at the PSI PROTEUS facility. The experiments are designed to supplement the experimental data base and reduce the design and licensing uncertainties for small- and medium-sized helium-cooled reactors using low-enriched uranium (LEU) and graphite high temperature fuel. The main objectives of the new experiments are to provide first-of-a-kind high quality experimental data on: (1) the criticality of sample, easy to interpret, single core region LEU HTR systems for several moderator-to-fuel ratios and several lattice geometries; (2) the changes in reactivity, neutron balance components and control rod effectiveness caused by water ingress into this type of reactor; and (3) the effects of the boron and/or hafnium absorbers that are used to modify the reactivity and the power distributions in typical HTR systems. Work on the design and licensing of the modified PROTEUS critical facility is now in progress with the HTR experiments scheduled to begin early in 199

    Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples

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    Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission products and a high abundance of major and minor actinides. Of particular interest is the change in the reactivity of the fuel as a function of burnup and the capability of modern codes to predict this change. In addition, the neutron emission from burnt fuel has important implications for the design of transport and storage facilities. Measurements have been made of the reactivity effects and the neutron emission rates of highly burnt uranium oxide and mixed oxide fuel rod samples coming from a pressurised water reactor (PWR). The reactivity measurements have been made in a PWR lattice in the PROTEUS zero-energy reactor moderated in turn with: water, a water and heavy water mixture and water containing boron. A combined transport flask and sample changer was used to insert the 400mm long burnt fuel rod segments into the reactor. Both control rod compensation and reactor period methods were used to determine the reactivities of the samples. For the range of burnup values investigated, an interesting exponential relationship has been found between the neutron emission rate and the measured reactivity. [All rights reserved Elsevier
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