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Hpge detector

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The HPGe detector is a type of radiation detector that uses high-purity germanium as the sensing material. It is primarily used for the detection and analysis of gamma radiation. The HPGe detector provides high-resolution spectroscopy capabilities, enabling the precise identification and quantification of gamma-emitting radionuclides.

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Lab products found in correlation

111in incl3, by Mallinckrodt (1 mentions) Ag1 x8 resin, by Bio-Rad (1 mentions)

12 protocols using hpge detector

1

Terbium-155 Activity Quantification

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The terbium-155 activities were determined before and after separation by γ-ray spectrometry using a high-purity germanium (HPGe) detector (Canberra, France), in combination with the Inter-Winner software package (version 7.1, Itech Instruments, France). The efficiency calibration was performed using an Eppendorf vial filled with a europium-152 solution (89.51 kBq ± 0.71%, reference date 20.02.2017) and placed at 1 m from the detector. A 5 µL aliquot of the final product ([155Tb]TbCl3) was introduced in an Eppendorf vial and measured with uncertainty ≤ 5% at 1 m from the detector. Moreover, a small aliquot of the solution obtained from the target dissolution (5 mL 7.0 M HNO3) was also measured with the same method. As a result, it was possible to calculate the production and separation yields, by decay correction and sample extrapolation, together with the activity obtained at the end of bombardment (EOB), and at the end of separation (EOS), respectively. The radionuclidic purity at EOS was assessed using the same method.
Favaretto C., Talip Z., Borgna F., Grundler P.V., Dellepiane G., Sommerhalder A., Zhang H., Schibli R., Braccini S., Müller C, & van der Meulen N.P. (2021). Cyclotron production and radiochemical purification of terbium-155 for SPECT imaging. EJNMMI Radiopharmacy and Chemistry, 6, 37.
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2

Cesium Adsorption Using PB/RGOF Composite

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The solutions containing radioactive 137Cs was prepared by diluting a stock solution to approximately 100 Bq/g. The required amount of adsorbent (1, 5, and 10 mg) was dispersed in a 10 mL 137Cs solution, after which the vial was shaken for 12 h. The aqueous solution was then filtered through a syringe type filter and the adsorption capacity was measured using an HPGe detector (Canberra, USA). The removal efficiency (%) and decontamination factor (DF) values, which were defined by the following equation to assess the adsorption capacity of the PB/RGOF composite towards 137Cs:


where C0 and Ce represent the initial and equilibrium concentrations of the Cs, respectively, and A0 and Af are the cesium radioactivity in the initial and final solutions after treatment, respectively.
Jang S.C., Haldorai Y., Lee G.W., Hwang S.K., Han Y.K., Roh C, & Huh Y.S. (2015). Porous three-dimensional graphene foam/Prussian blue composite for efficient removal of radioactive 137Cs. Scientific Reports, 5, 17510.
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3

Cesium-137 Removal via pH Adjustment

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The removal of 137Cs as a function of solution pH ranging from 4–10 was prepared by adjusting the pH using HCl and NH4OH. The initial 137Cs concentration was 100 Bq/g. All experiments were equilibrated for 12 h with stirring. The nanocomposite was then separated from the solution using a magnet, and the residual 137Cs concentration was measured using a HPGe detector (Canberra Inc., Meriden, CT, USA).
Jang S.C., Kang S.M., Kim G.Y., Rethinasabapathy M., Haldorai Y., Lee I., Han Y.K., Renshaw J.C., Roh C, & Huh Y.S. (2018). Versatile Poly(Diallyl Dimethyl Ammonium Chloride)-Layered Nanocomposites for Removal of Cesium in Water Purification. Materials, 11(6), 998.
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4

Neutron Activation of Radioisotopes

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Radiotracers of 85Sr,60Co and 152+154 Eu were obtained via the activation reaction (n, γ) by the neutron irradiation of 0.05 g weight of metal chloride salt double wrapped in aluminum foil and transferred via the rabbit system to the vertical irradiation channels inside the core of the second Egyptian Training Research Reactor ETRR-2. 137Cs was obtained from a standard radioactive solution purchased from Eckert and Ziegler.
The radioactivity level of the activated samples was measured using coaxial-p type HPGe detector (Canberra, USA) connected to multi-channel analyzer with 16,000 channels (Canberra, USA). The obtained results were analyzed using Gennie 2000 software after energy and efficiency calibration.
Abdel-Galil E.A., Kasem A.E, & Mahrous S.S. (2023). Elaboration and characterization of molybdenum titanium tungsto-phosphate towards the decontamination of radioactive liquid waste from 137 Cs and 85Sr. Environmental Science and Pollution Research International, 31(2), 2732-2744.
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5

Dissolution of Irradiated Palladium Targets

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Dissolution of the irradiated Pd target was accomplished with some modifications as previously described.[21 (link), 22 ] Briefly, irradiated Palladium wire (4 – 6 mg Pd, 111Ag ranging from 44.4 to 118.4 MBq) was dissolved in 2 mL of a conc. HCl: conc. HNO3 (1:1) mixture by gentle heating. To prevent the formation of insoluble oxide precipitates,[23 ] the resultant brownish red solution was heated gently to near dryness and reconstituted in 3 M HNO3 twice and heated to near dryness each time to expel traces of HCl. After allowing the resulting volume (0.5 – 0.65 mL) to cool to room temperature, an additional 2 mL of 3 M HNO3 was added and the final volume measured, typically 2.5 – 2.65 mL. A 10 μL aliquot was removed and diluted in 1 mL 3 M HNO3 for gamma spectroscopy analysis on a high purity germanium (HPGe) detector (Canberra).
Aweda T.A., Zhang S., Mupanomunda C., Burkemper J., Heo G.S., Bandara N., Lin M., Cutler C.S., Cannon C.L., Youngs W., Wooley K.L, & Lapi S.E. (2015). Investigating the pharmacokinetics and biological distribution of silver-loaded polyphosphoester-based nanoparticles using 111Ag as a radiotracer. Journal of labelled compounds & radiopharmaceuticals, 58(6), 234-241.
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6

Production and Characterization of Radionuclides

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Solutions of [18F]F−, [64Cu]CuCl2 and [131Ba]Ba(NO3)2 were produced in‐house by proton bombardment of the respective liquid or solid target at the TR‐FLEX Cyclotron from ASCI.30 All cyclotron‐based radionuclides are non‐carrier‐added products. [224Ra]Ra(NO3)2 was separated from a 228Th‐source by ion exchange chromatography and was obtained as non‐carrier‐added solution. [177Lu]LuCl3 was purchased by ITG and [111In]InCl3 by Mallinckrodt. [89Zr]Zr(C2O4)2 was purchased by Perkin Elmer and [133Ba]BaCl2 from Polatom. The specific activity from the manufacturers’ certificate was 50 MBq/mg Ba. Activity count rates were measured using the ISOMED 2160 (MED) sodium iodide detector and the ISOMED 2100 dose calibrator (MED). High‐precision measurements were performed using a HPGe detector by Canberra.
Reissig F., Zarschler K., Hübner R., Pietzsch H., Kopka K, & Mamat C. (2020). Sub‐10 nm Radiolabeled Barium Sulfate Nanoparticles as Carriers for Theranostic Applications and Targeted Alpha Therapy. ChemistryOpen, 9(8), 797-805.
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7

Cesium Adsorption Capacity Determination

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The solution containing radioactive cesium was prepared by diluting a stock solution to approximately 130 Bq/g. The required amount of adsorbent (10 mg) was dispersed in 10 mL of the radioactive cesium solution, after which the vial was shaken for 12 h. Next, the aqueous solution was filtered through a syringe filter, and the adsorption capacity was measured using the HPGe detector (Canberra, USA).
Jang S.C., Kang S.M., Haldorai Y., Giribabu K., Lee G.W., Lee Y.C., Hyun M.S., Han Y.K., Roh C, & Huh Y.S. (2016). Synergistically strengthened 3D micro-scavenger cage adsorbent for selective removal of radioactive cesium. Scientific Reports, 6, 38384.
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8

Separation and Analysis of Cobalt-55

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For processing, targets were placed in 10 mL of 9 M HCl and heated with reflux for approximately one hour in order to dissolve the nickel from the gold disk. Once the solution cooled it was placed in a 1 cm × 10 cm glass column (Biorad, USA) with 2.5 g AG1-X8 resin (Biorad, USA). In order to determine separation conditions, the eluate along with 10–40 mL of 9 M HCl were collected followed by another 10 mL of 0.5 M HCl to elute the 55Co. Fractions of 1 mL were collected and analyzed using an High Purity Germanium (HPGe) detector (Canberra, USA) and the final 55Co fractions were evaporated to dryness and reconstituted with 20 µL Milli-Q water. 55Co productions were analyzed using Ion Chromatography (28 (link)) for transition metal contamination.
Mastren T., Marquez B.V., Sultan D.E., Bollinger E., Eisenbeis P., Voller T, & Lapi S.E. (2015). Cyclotron production of high specific activity 55Co and in vivo evaluation of the stability of 55Co metal-chelate-peptide complexes. Molecular imaging, 14, 526-533.
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9

Whole Mouse Radioactivity Quantification

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Whole mice were counted in a Canberra HPGe detector for 5 × 104 s. The concentration of 134Cs and 137Cs were determined for each mouse in Bq g-1. The internal dose was computed using internal dose factors from Perri and Johnson (Perri and Johnson 2019 (link)). Mouse blood samples were paired with concentrations of 134Cs and 137Cs in the mouse from which the blood was drawn. The dose calculations assumed that the concentration was the same throughout the lifetime of the mouse. No corrections for decay were made since no mouse was older than 18 months, and no significant changes in concentration were assumed. The concentration was assumed to be the same throughout the lifetime of the animal because the home range of the large Japanese field mouse is small enough that they would likely not move into or out of areas of lesser or greater environmental contamination for where they were captured (Shioya et al. 1990 ). Additional methodology for internal dosimetry may be found in Appendix 1.
Sproull M., Hayes J., Ishiniwa H., Nanba K., Shankavaram U., Camphausen K, & Johnson T.E. (2021). Proteomic biomarker analysis of serum from Japanese field mice (Apodemus speciosus) collected within the Fukushima difficult to return zone. Health physics, 121(6), 564-573.
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10

Standardization of 169Er Activity Measurements

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Gamma-ray spectra of the gold foils were taken before and after leaching of the Zn layer, using a high-purity germanium (HPGe) detector (Canberra, France), in combination with the Inter-Winner software package (version 7.1, Itech Instruments, France) (Supplementary Figure 2).
Purified 169Er in 0.1 M HCl (stock solution) was divided into two parts, named Er1 and Er2, respectively (Figure 2). They were accurately weighed using a Mettler-Toledo XS225DU balance. Sample Er1 was sent to the Institute of Radiation Physics (IRA, Lausanne) for activity standardization using the TDCR technique. The activity concentration of the Er1 solution was used to prepare 169Er quench series to calibrate LSC using Er2 solution (Supplementary Figure 3A). The counting efficiency for typical samples was ~97%.
The 169Er activity measurements of the mass-separated samples were performed after chemical separation using liquid scintillation counting (LSC; LSC Packard Tri-Carb 2250 CA) (Supplementary Figure 3B). Further details about activity standardization measurements of 169Er are described in the Supplementary Material.
Talip Z., Borgna F., Müller C., Ulrich J., Duchemin C., Ramos J.P., Stora T., Köster U., Nedjadi Y., Gadelshin V., Fedosseev V.N., Juget F., Bailat C., Fankhauser A., Wilkins S.G., Lambert L., Marsh B., Fedorov D., Chevallay E., Fernier P., Schibli R, & van der Meulen N.P. (2021). Production of Mass-Separated Erbium-169 Towards the First Preclinical in vitro Investigations. Frontiers in Medicine, 8, 643175.
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