Validation of gamma-ray true coincidence summing effects modeled by the Monte Carlo code MCNP-CP

When radionuclides decay by cascading photons, the accuracy of the measured nuclide activity may be affected by true coincidence summing effects. The effects can be quantified by Monte Carlo simulations that can handle correlated γ-and X-ray emissions from a radionuclide. Analysis techniques are also available commercially to correct for the effects due to cascading γ-rays. The MCNP-CP code was used to compute the effects in high purity germanium detectors for several commonly used nuclides and geometries and the results were compared to measurements and an analysis technique. Excellent agreement in true coincidence summing corrections predicted by MCNP-CP and the analysis technique was obtained. In addition, the X-ray true coincidence summing effects were evaluated.     

Current status and prospects of development of the NAAPRO code

The paper contains a summary of the recent developments of the prediction part of the NAAPRO (Neutron Activation Analysis PRognosis and Optimization) code. Specific details are given for the activation product yield calculation approach used in the program and for the nuclear data libraries. The prospects for the code development are discussed.     

Software for X- and gamma-ray spectrometry

Summary A computational approach to the true-coincidence summing correction factor evaluating was developed on the basis of the extended version of the MCNP - a general Monte Carlo N-particle transport code. A specially developed utility program generates the MCNP input on the basis of a routinely updated Evaluated Nuclear Structure Data File (ENSDF) library. Necessary information is automatically added to allow accurate simulating of the emission of correlated particles accompanying the decay of a particular radionuclide, including emission of annihilation quanta, K- and L- X-rays, β-particles and conversion electrons. Gamma-ray angular correlations as well as lifetimes of the nuclear excited states are also taken into account. The approach is applicable to correction factor evaluation for ordinary single- and multi-detector spectrometers as well as for Compton suppression systems. The paper describes the developed computational scheme as well as presents the results of its preliminary testing for the case of both point and volumetric sources.     

NAAPRO: A code for predicting results and performance of neutron activation analysis

Summary A code is described for predicting the results and main characteristics of neutron activation analysis (NAA) on the basis of a simulated gamma-ray spectrum of activation products, calculated for the specified analysis conditions. These are analysis time mode, analyzed sample mass and elemental composition, characteristics of the irradiating neutron flux and irradiation conditions, gamma-spectrometry measurement geometry and background conditions, as well as detector and spectrometry system parameters. Gamma-ray dose rates for different points of time after sample irradiation and input count rate of the spectrometry system are also predicted.     

Transuranium elements and fission products in technological channels of unit No. 2 of Chernobyl Nuclear Power Plant

A gamma-spectrometric and radiochemical analysis was carried out of a material (Zr-2.5% Nb alloy) of technological channels (TC) of Chernobyl Nuclear Power Plant (NPP) power unit No. 2 RBMK-1000 reactor, being under the beginning stage of decommissioning. Activities of ⁹⁰Sr, ¹³⁷Cs, ²³⁸Pu, ^239+240Pu, ²⁴¹Am and ²⁴⁴Cm were determined. It was established that the main source of the revealed actinides and fission products was an impurity of natural thorium and uranium in TC source material on the level of several tenths of ppm. Impurity analysis of TC source material was performed by neutron activation analysis (NAA) and inductively coupled plasma mass spectrometry (ICP-MS). Fission product and transuranium element activities measured were compared with the results of prognostic calculations performed with the help of the NAAPRO code.     

On the design and installation of a Compton–suppressed HPGe spectrometer at the Budapest neutron-induced prompt gamma spectroscopy (NIPS) facility

An important aspect of the ongoing upgrade at the Budapest PGAA-NIPS facility has been the design and installation of a second Compton-suppressed gamma spectrometer. The aim was to provide excellent spectroscopic conditions for future position sensitive and large sample prompt gamma activation analysis applications. The optimum geometry of the setup was determined by Monte Carlo calculations with the MCNP-CP code. The suppression factors for various layouts (co-axial, perpendicular), shapes (cylindrical, tapered), and thicknesses were compared at different gamma-ray energies. The optimum configuration, as a trade-off between performance and cost, was selected, purchased, and installed. Several characteristic features of a collimated, Compton-suppressed system could be revealed, which allowed us to achieve a better and cost-effective performance. The calculations were validated with a ¹⁴N(n,γ)¹⁵N calibration source.     

Black poplar-tree (<Emphasis Type="Italic">Populus nigra</Emphasis> L.) bark as an alternative indicator of urban air pollution by chemical elements

Capabilities of black poplar-tree (Populus nigra L.) bark as a biomonitor of atmospheric air pollution by chemical elements were tested against epiphytic lichens Xanthoria parietina (L.) and Physcia adscendens (Fr.). Concentrations of 40 macro and trace elements were determined using epicadmium and instrumental NAA. The data obtained were processed using non-parametric tests. A good correlation was found between concentrations of majority of elements in bark and lichens. On the accumulation capability bark turned out to be competitive with both lichens examined. The main inorganic components of black poplar-tree bark were revealed. A substrate influence on the concentrations of some elements in epiphytic lichens was established. An optimized procedure of bark pre-irradiation treatment was suggested.     

A Dynamic Link Library for calculating true-coincidence summing correction factors

A Dynamic Link Library (DLL) was created for calculating true-coincidence correction factors in γ- and X-ray spectrometry applications. Calculations are done by Monte-Carlo method on the basis of the Evaluated Nuclear Structure Data File (ENSDF). In calculations the emission of cascade gammas, as well as γ-X, γ-γ ₅₁₁ and X-X coincidences are appropriately taken into account. A set of measurement geometries implemented includes combinations of coaxial, planar, low and broad energy as well as well-type detectors with point, disk, spherical, cylindrical and Marinelli beaker sources. Together with true-coincidence correction factors full-energy-peak efficiencies are calculated and reported. The DLL was tested by comparing its results with experimental data and results of similar calculations.     

Validation of true coincidence summing correction in Genie 2000 V3.2

A new cascade summing correction method with the algorithm extended to include true coincidence summing effects from low-energy gamma-rays, KX-rays from Electron Capture and Internal Conversion, and to include the 511 keV positron annihilation photons has been developed and implemented in Genie 2000 V3.2 released in 2009. To validate the accuracy and precision of the extended correction method, measurements of calibrated sources containing cascading nuclides from various types of ISOCS/LabSOCS characterized High Purity Germanium detectors have been analyzed. Validation of the true coincidence summing correction factors for the extended correction method has been made by comparison to the results from the Monte Carlo code MCNP-CP. In addition, comparison between the measured and the known activities of the cascading nuclides was performed, which shows that the method is effective and accurate.