Measurement of excitation functions in proton induced reactions on natural copper from their threshold to 43MeV
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Abstract We examined the suitability of taking smear tests (DIN ISO 7503.1) to evaluate surface activity. Special respect was given to mixtures of nuclides typical for the nuclear industry. We analysed the nuclides of samples of different fuel pools to evaluate the smear test measurement technique. Special calculations were carried out to examine the amount of nuclides that are difficult to measure due to their low maximum decay energy of less then 0.15 MeV (e. g. 55Fe, 63Ni). The response characteristic, detection sensitivity and the influence of the nuclide used for calibration were examined in detail on the basis of the nuclide vectors of fuel pool samples. We learned that especially the isotope standard used for calibration has a major influence for the suitability of the measurements. Calculation of the amount of these nuclides in relation to the effective dose (inhalation, ingestion) and the skin dose showed that they contribute little to the complete exposition.
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Low- and intermediate-level radioactive wastes (L-ILW) generated at nuclear power plants are disposed of in various countries. In the disposal of such wastes, it is required that the radioactivity concentrations of waste packages should be declared with respect to difficult-to-measure nuclides (DTM nuclides), such as C-14, Ni-63 and α-emitting nuclides, which are often limited to maximum values in disposal licenses, safety cases and/or regulations for maximum radioactive concentrations. To fulfill this requirement, the Scaling Factor method (SF method) has been applied in various countries as a principal method for determining the concentrations of DTM nuclides. In the SF method, the concentrations of DTM nuclides are determined by multiplying the concentrations of certain key nuclides by SF values (the determined ratios of radioactive concentration between DTM nuclides and those key nuclides). The SF values used as conversion factors are determined from the correlation between DTM nuclides and key nuclides such as Co-60. The concentrations of key nuclides are determined by γ ray measurements which can be made comparatively easily from outside the waste package. The SF values are calculated based on the data obtained from the radiochemical analysis of waste samples. The use of SFs, which are empirically based on analytical data, has become established as a widely recognized “de facto standard”. A number of countries have independently collected nuclide data by analysis over many years and each has developed its own SF method, but all the SF methods that have been adopted are similar. The project team for standardization had been organized for establishing this SF method as a “de jure standard” in the international standardization system of the International Organization for Standardization (ISO). The project team for standardization has advanced the standardization through technical studies, based upon each country’s study results and analysis data. The conclusions reached by the project team was published as ISO International Standard 21238:2007 “The Scaling Factor method to determine the radioactivity of low- and intermediate-level radioactive waste packages generated at nuclear power plants” [1]. This paper gives an introduction to the international standardization process for the SF method and the contents of the recently published International Standard.
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The irradiation effect of high energy heavy ions in a foil has been investigated by secondary ions spectroscopy in the energy region where the electronic stopping power is dominant. We observed significant enhancement of the secondary ion yield above the threshold value of the electronic stopping power, where the irradiation effect in high Tc super conductors and metallic materials becomes remarkable.
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one on the high-energy side. A step-like background function can be used with each component. The program will automatically recycle to add one or more components to a region if needed to improve the fit. The ..gamma..-ray energies and intensities are computed from the resulting Gaussian positions and peak areas. From a comparison of these peak energies and the ..gamma..-ray energies for various nuclides in a nuclide library, the nuclides that may be present are identified. The user may edit this nuclide list. The program identifies secondary ..gamma.. rays that should be present for these nuclides and obtains peak areas for them, if the areas are not already available. All of the peak areas are then analyzed to obtain the best nuclidic activities. The peak areas for any one nuclide and those for nuclides that have interfering lines are analyzed in one least-squares ft. Nuclides whose activities are essentially 0, and peaks which cannot be accounted for are removed from the analysis. Besides the nuclidic activities, a peak-by-peak summary is provided. This program is intended to analyze large groups of spectra as well as an individual spectrum.
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