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Corrigendum to “Neutron and gamma-ray signatures for the control of alpha-emitting materials in uranium production: A Nedis2m-MCNP6 simulation” [Radiat. Phys. Chem. 208 (2023) 110919]

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Corrigendum to “Neutron and gamma-ray signatures for the control of alpha-emitting materials in uranium production: A Nedis2m-MCNP6 simulation” [Radiat. Phys. Chem. 208 (2023) 110919]

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The total (α, n) reaction cross section for19F has been measured as a function of alpha energy in the energy range 2·6 to 5·1 MeV with a thin target. The excitation function exhibits a large number of resonances. The prominent amongst these for which theJ π values are known have been analysed to extract the partial widthsΓ α and Γn . Statistical analysis of the data in terms of strength function and average level spacing distribution has also been performed.
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Fluorine has a relatively large (α,n) production cross-section in the MeV range, the energy range of interest for special nuclear materials. In the uranium fuel cycle enriched UF6 in particular is a reasonably prolific source of (α,n) neutrons because along with 235U, 234U becomes enriched and it has a relatively short half-life. This enables the mass content of storage cylinders containing UF6 to be verified by neutron counting methods.In association with such measurements high resolution gamma-ray spectrometry (HRGS) measurements using a high-purity Ge detector are often undertaken to determine the 235U enrichment based off the intensity of the direct 186 keV line. The specific (α,n) neutron production, neutrons per second per gram of U, is sensitive to the relative isotopic composition, particularly the 234U concentration, and the traditional gross neutron counting approach is needed to quantitatively interpret the data.In addition to F(α,n) neutrons, α-induced reaction γ-rays are generated, notably at 110, 197, 582, 891, 1236 and 1275 keV. If one could observe 19F(α,xγ) gamma-lines in the HRGS spectra the thought was that perhaps the α-activity could be estimated directly, and in turn the 234U abundance obtained. For example, by utilizing the ratio of the detected 197–186 keV full energy peaks. However, until now there has been no readily available estimate of the expected strength of the reaction gamma-rays nor any serious consideration as to whether they might be diagnostic or not.In this work we compute the thick target yields of the chief reaction gamma-rays in UF6 using published thin target data. Comparisons are made to the neutron production rates to obtain γ/n estimates, and also to the 235U decay line at 186 keV which we take as a fiducial line. It is shown that the reaction gamma-rays are produced but are far too weak for practical safeguards purposes.Now that the underlying numerical data is readily available however, it can be used to support neutron and gamma production calculations in other fluorine compounds, for example impure plutonium reference materials where fluorine may be present only at the parts per million by weight level yet still present a serious nuisance addition to the neutron production rate.
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Thick-target (..cap alpha..,n) neutron yields have been measured for /sup 6,7,NAT/Li, /sup 9/Be, /sup 10,11,NAT/B, Pb/sup 19/F/sub 2/, Zn /sup 19/F/sub 2/, /sup NAT/Mg, /sup 27/Al, /sup NAT/Si, and /sup 28/Si/sup NAT/O/sub 2/. From the Pb/sup 19/F/sub 2/ and Zn/sup 19/F/sub 2/ data, we have extracted the neutron yield that would result from the (..cap alpha..,n) reaction on a thick target of pure fluorine. Using the /sup 28/Si/sup NAT/O/sub 2/ data, the yield that would result from the (..cap alpha..,n) reaction on a thick target of pure /sup NAT/O/sub 2/ and the /sup NAT/O(..cap alpha..,n) cross section at alpha-particle energies above those for which measurements previously existed have been extracted. In addition, the thin-target oxygen cross section to obtain a correction to the previously measured values. Thick-target yields are calculated from the cross-section values for carbon and oxygen and are compared to the experimental thick-target data. Thick-target yields for /sup 238/U/sup NAT/O/sub 2/ and for /sup 238/U/sup NAT/C are calculated from the thin-target cross sections. Results are compared to existing experiment and calculations.
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The measurement of the 235U enrichment and the mass of UF6 in 30B and 48Y transit cylinders are important safeguards verification tasks of IAEA. In the framework of a project aiming to establish an unattended measurement station at isotope enrichment facilities (Lebrun, 2007) [1], a study was carried out to describe the state-of-the-art of non-destructive assay methods applicable to UF6 cylinders.The objective of the present work is to provide a feasibility assessment study of all known NDA techniques applicable to the quantitative verification of all uranium categories involved in an enrichment processing plant. Based on this investigation, the most appropriate techniques were then investigated for suitability of use in an unattended measurement station.
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Neutrons from (α,n) reactions through thorium and uranium decays are important sources of background for direct dark matter detection. The neutron yields and energy spectra from a range of materials that are used to build dark matter detectors are calculated and tabulated. In addition to thorium and uranium decays, we found that α-particles from samarium, often the dopant of the window materials of photomultiplier tubes (PMT), are also an important source of neutron yield. The results in this paper can be used as the input to Monte Carlo simulations for many materials that will be used for next generation experiments.
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