High-energy detector calibration data for k
            0-neutron activation analysis

Szentmiklósi, László; Maróti, Boglárka; Párkányi, Dénes; Harsányi, Ildikó; Révay, Zsolt

doi:10.1007/s10967-017-5651-x

Cited by 4 publications

(10 citation statements)

References 21 publications

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“…In practice, measuring or computing peak and total detection e ciency for a close detector to source distance is cumbersome and complicated and might yield biased results [12]. In addition, the relatively large deviation observed for 56 Co and 72 Ga (compared to 24 Na and 56 Mn) at short detector to source distances can be attributed to improper estimation of true coincidence correction due to their complicated decay schemes and/or insu cient general con dence in their nuclear data [3,8,[13][14][15].…”

Section: Resultsmentioning

confidence: 99%

Utilization of different radionuclides for high-energy extended efficiency calibration of HPGe for improved determination of calcium and sulfur using k0-INAA

Soliman

Mindil

Takamiya

2023

Preprint

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The present study reports on the performance of three reactor-produced radionuclides (24Na, 56Mn, and 72Ga) and one accelerator-produced radionuclide (56Co) for extending the full energy peak efficiency calibration of a coaxial HPGe detector up to ~3100 keV at different detector to source distance. The differences in the efficiency curves obtained with and without the use of high-energy gamma emitters radionuclides have a considerable impact on the accuracy of Na, Ca, and S determination by the k0-INAA as evidenced by analysis results of reference materials. The results revealed that the use of 24Na is the most suitable radionuclide for high-energy efficiency calibration due to its reasonable availability, low production cost, simple decay scheme, and well-defined decay properties.

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Section: Resultsmentioning

confidence: 99%

Utilization of different radionuclides for high-energy extended efficiency calibration of HPGe for improved determination of calcium and sulfur using k0-INAA

Soliman

Mindil

Takamiya

2023

Preprint

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“…The 3 h irradiation was performed in a rotating, well-thermalized channel of the Budapest Research Reactor [ 27 ]. Together with the samples, flux-monitor foils of Au, Zr, Fe or Ni were co-irradiated, which are essential for the concentration calculations by the k0-method [ 28 ]. The thermal equivalent neutron flux in the rotating irradiation channel (No.…”

Section: Methodsmentioning

confidence: 99%

Assessment of Long Lived Isotopes in Alkali-Silica Resistant Concrete Designed for Nuclear Installations

et al. 2021

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The design of concrete for radiation shielding structures is principally based on the selection of materials of adequate elemental composition and mix proportioning to achieve the long-term durability in nuclear environment. Concrete elements may become radioactive through exposure to neutron radiation from the nuclear reactor. A selection of constituent materials of greatly reduced content of long-lived residual radioisotopes would reduce the volume of low-level waste during plant decommissioning. The objective of this investigation is an assessment of trace elements with a large activation cross section in concrete constituents and simultaneous evaluation of susceptibility of concrete to detrimental alkali-silica reaction. Two isotopes 60Co and 152Eu were chosen as the dominant long-lived residual radioisotopes and evaluated using neutron activation analysis. The influence of selected mineral aggregates on the expansion due to alkali-silica reaction was tested. The content of 60Co and 152Eu activated by neutron radiation in fine and coarse aggregates, as well as in four types of Portland cement, is presented and discussed in respect to the chemical composition and rock origin. Conflicting results were obtained for quartzite coarse aggregate and siliceous river sand that, despite a low content, 60Co and 152Eu exhibited a high susceptibility to alkali-silica reaction in Portland cement concrete. The obtained results facilitate a multicriteria selection of constituents for radiation-shielding concrete.

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“…Concentrations of major and trace elements in cements were determined by prompt gamma activation analysis (PGAA), and the assessment of the trace elements with large activation cross section was perform by neutron activation analysis (NAA), both using the k0-standardization method, [15]. PGAA gives precise results for major elements like Si, Ti, Al, Fe, Mn, Mg, Ca, Na, K and H in cement specimens.…”

Section: Methodsmentioning

confidence: 99%

“…At the same time flux-monitor foils of Au, Zr, Fe or Ni were co-irradiated for concentration calculations by the k0-method, [15]. The thermal equivalent neutron flux in the rotating irradiation channel was 1.86x10 13 cm 2 s -1 .…”

Section: Methodsmentioning

confidence: 99%

Assessment of long-lived residual radioisotopes in cement induced by neutron radiation

et al. 2020

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During the decommissioning of nuclear power plants, a significant amount of cement based composites should be disposed as radioactive waste. The use of material with low-activation constituents could effectively reduce radioactivity of concrete. The subject of the paper is the content of trace elements with large activation cross section in concrete constituents due to their ability to be activated in radiation shielding structures. Various Portland cement specimens were subjected to elemental analysis by neutron activation analysis and prompt gamma activation analysis to assess the dominant long-lived residual radioisotopes. Concentrations of the radionuclides, such as Europium-152, Cobalt-60 and Caesium-134 were assessed. Their half-life time is 13.5, 5.27, and 2.07 years, respectively. On the basis of the obtained results, recommendations for cement selection for low-activation concrete are proposed in order to economize decommissioning cost by reducing a radioactive concrete waste.

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High-energy detector calibration data for k 0-neutron activation analysis

Cited by 4 publications

References 21 publications

Utilization of different radionuclides for high-energy extended efficiency calibration of HPGe for improved determination of calcium and sulfur using k0-INAA

Utilization of different radionuclides for high-energy extended efficiency calibration of HPGe for improved determination of calcium and sulfur using k0-INAA

Assessment of Long Lived Isotopes in Alkali-Silica Resistant Concrete Designed for Nuclear Installations

Assessment of long-lived residual radioisotopes in cement induced by neutron radiation

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