High Resolution HPGe Detector Research Articles

Development of an external PIGE method using nitrogen from atmospheric air as external beam current normalizer and its application to nondestructive quantification of total boron mass fraction in boron containing neutron absorbers

Beam current monitoring and normalization is a very important task in ion beam analysis experiments. Compared to current monitoring by conventional method, in situ or external beam current normalization is attractive in Particle Induced Gamma-ray Emission (PIGE), which involves simultaneous measurement of prompt gamma rays of analyte of interest and current normalizing element. In the present work, an external (in air) PIGE method has been standardized for quantification of low Z elements using nitrogen from atmospheric air as external current normalizer, in which 2313 keV of 14N(p,p’γ)14N is measured. It provides truly nondestructive and greener quantification method for low Z elements by external PIGE. The method was standardized by quantifying total boron mass fractions in ceramic/refractory boron-based samples using low energy proton beam from tandem accelerator. The samples were irradiated with 3.75 MeV proton beam and prompt gamma rays of analyte at 429, 718 and 2125 keV of 10B(p,αγ)7Be, 10B(p,p’γ)10B and 11B(p,p’γ)11B, respectively, and external current normalizers at 136 and 2313 keV were measured simultaneously using high resolution HPGe detector system. The obtained results were compared with external PIGE method using tantalum as external current normalizer, where 136 keV of 181Ta(p,p’γ)181Ta from beam exit window material (Ta) was used for current normalization. The developed method is found to be simple, rapid, convenient, reproducible, truly nondestructive and more economical as no additional beam monitoring instruments are required and it is especially advantageous for direct quantitative analysis of ‘as received’ samples.

Determination of positron emission intensity in the decay of 86gY

The β+- emitting radionuclide 86gY (t1/2 = 14.7 h) forms a matched-pair with the β--emitting therapeutic radionuclide 90Y (t1/2 = 2.7 d) for theranostic application in medicine. Precise knowledge of the positron emission probability of the PET nuclide is very important, which was rather uncertain for 86gY until recently. In this work, an 86gY source of high radionuclidic purity was prepared and the positron emission intensity per 100 decay of the parent (hereafter “positron emission intensity”) was determined by measuring the 511 keV annihilation γ-ray using high-resolution HPGe detector. The total source activity was obtained from known γ-ray emission probabilities. The electron capture (EC) intensity was also determined as an additional check by measuring the Kα and Kβ X-rays of energies 14.1 and 15.8 keV, respectively, using a low energy HPGe detector. From those measurements, normalized values of 27.2 ± 2.0% for β+ -emission and 72.8 ± 2.0% for EC were deduced. These results are in excellent agreement with values recently reported in the literature based on a detailed decay scheme study.

Assessment of heavy metals and radionuclides in groundwater and associated human health risk appraisal in the vicinity of Rooppur nuclear power plant, Bangladesh

This study was carried out to assess the groundwater quality through estimating trace and heavy metal concentration and radionuclide levels in the vicinity of the Rooppur Nuclear Power Plant (RNPP) sites. Twenty-six (26) parameters, including major cations (K, Na, Mg, Ca) and anions (SO4−2, NO3−), trace and heavy metals (Mn, Fe, Zn, Ni, Co, Pb, Cd, As, Hg, Cu, Li, Be, B, V, Ga, Sr, Ag, Ba) and radionuclides (137Cs, 226Ra, 228Ra, and 40K) were estimated in water samples in the study area. This study revealed that the concentration values (μg/L) of Mn (667.091 ± 7.481), Fe (191.477 ± 3.756), Sr (105.218 ± 13.424), and Zn (23.493 ± 1.134) were the dominant metals in the study area. Different pollution evaluation indices (i.e., HPI, HEI, NI, Cd) data revealed that the study area was under a low to medium level of pollution due to the presence of metals in water. Subsequently, non-carcinogenic and carcinogenic health risks assessments for both adults and children were conducted, which indicated that health risk for the carcinogenic metals were below the threshold level except As through oral exposure for both adult and children. The activity concentrations of 226Ra, 228Ra, and 40K were measured to demonstrate probable radioactivity pollution using Gamma-ray spectrometry (High-resolution HPGe detector). The highest activity concentration of 226Ra, 228Ra, and 40K in groundwater samples were 4.9 ± 1.24 Bq/L (RNPP-15), 1.71 ± 0.43 Bq/L (RNPP-15), and 15.43 ± 3.08 Bq/L (RNPP-15). Among the three studied radionuclides, 40K has the highest average activity concentration. The radiological indicators referred to the annual effective dose (AED) is 0.4273 mSv yr-1, which implies no significant cause of radiological risks and hazards (UNSCEAR guideline value). This study provides a baseline of trace and toxic metal contamination, radioactivity, and radiation levels in the groundwater of the nuclear power plant (being built) area.

New cross section measurements on tungsten isotopes around 14 MeV neutrons and their excitation functions * *Supported by the National Natural ScienceFoundation of China (11575090)

New cross sections of the 183W(n,α)180mHf, 186W(n,d*)185Ta, 182W(n,p)182Ta, 184W(n,p)184Ta, 182W(n,2n)181W, 184W(n,α)181Hf, and 186W(n,α)183Hf reactions were measured in the neutron energy range of 13.5-14.8 MeV via the activation technique to improve the database and resolve discrepancies. Monoenergetic neutrons in this energy range were produced via the T(d,n)4He reaction on a solid Ti-T target. The activities of the irradiated monitor foils and samples were measured using a well-calibrated high-resolution HPGe detector. Theoretical calculations of the excitation functions of the seven nuclear reactions mentioned above in the neutron energies from the threshold to 20 MeV were performed using the nuclear theoretical model program TALYS-1.9 to aid new evaluations of cross sections on tungsten isotopes. The experimental data obtained were analyzed and compared with that of previous experiments conducted by other researchers, and with the evaluated data available in the five major evaluated nuclear data libraries of IAEA (namely ENDF/B-VIII.0 or ENDF/B-VII.0, JEFF-3.3, JENDL-4.0u+, CENDL-3.2, and BROND-3.1 or ROSFOND-2010), and the theoretical values acquired using TALYS-1.9 nuclear-reaction modeling tools. The new cross section measurements agree with those of some recent experiments and theoretical excitation curves at the corresponding energies. The consistency of the theoretical excitation curves based on TALYS-1.9 with these experimental data is better than that of the evaluated curves available in the five major nuclear data libraries of IAEA.

Positron Emission Intensity in the Decay of 86gY for Use in Dosimetry Studies.

The β+-emitting radionuclide 86gY (t1/2 = 14.7 h) forms a matched-pair with the β−-emitting therapeutic radionuclide 90Y (t1/2 = 2.7 d) for theranostic application in medicine. This approach demands a precise knowledge of the positron emission probability of the PET nuclide which was until recently rather uncertain for 86gY. In this work, an 86gY source of high radionuclidic purity was prepared and a direct measurement of the positron emission intensity per 100 decay of the parent (hereafter “positron emission intensity”) was performed using high-resolution HPGe detector γ-ray spectroscopy. The electron capture intensity was also determined as an additional check by measuring the Kα and Kβ X-rays of energies 14.1 and 15.8 keV, respectively, using a low energy HPGe detector. From those measurements, normalized values of 27.2 ± 2.0% for β+-emission and 72.8 ± 2.0% for EC were obtained. These results are in excellent agreement with values recently reported in the literature based on a detailed decay scheme study.

Isotopically Enriched 192Os Target Preparation using the Electron-gun Beam Method at Target Preparation Laboratory, Daresbury, UK.

In this work, we have discussed a novel electron gun beam method used for the preparation of an Osmium foil sample at Daresbury Target Preparatory Laboratory, UK, which was used during the 192Os(18O, 16O)194Os 2 neutron transfer reaction at IFIN-HH Bucharest. The successful measurement of gamma energies associated with the 194Os isotopic nucleus recorded from the experiment with the high resolution HPGe detectors from this clean target of 192Os showed that this method has proven very efficient in preparing the most difficult osmium target which other methods like the sputtering, thermal evaporation could not get it prepared due to the high melting point of about 3000 0C found in the Osmium foil.

EFFECTS OF LOCAL BUILDING MATERIALS ON INDOOR GAMMA DOSES AND RELATED RADIOLOGICAL HEALTH RISKS, AYVACIK, ÇANAKKALE/TURKEY.

In situ indoor gamma dose rate measurements were held in 79 dwellings by NaI(Tl) scintillation probe connected portable dose rate meter. For the building materials and impurities (nodules), spectrometric gamma analysis was applied by a high-resolution HpGe detector. For Ahmetçe and Nusratlı villages in Ayvacik/Çanakkale (Turkey), the measured in situ indoor gamma dose rates and related indoor annual effective dose equivalents (AEDEin) were 3 and 3.3 times, and indoor excess lifetime cancer risks (ELCRin) were 4.25 and 4.68 times higher than those of the world averages, respectively. The used local rocks were mostly ignimbrite and dacitic-rhyolitic tuffaceous (Arıklı tuff), and wall plasters were made of local soil. The highest in situ indoor gamma dose rates of the region belonged to Nusratlı village due to the intense impurities (nodules) and hydrothermal alterations in Arıklı tuff. Spectrometric gamma results revealed that 40K has an important effect on the indoor gamma doses.

Measurement of the quadrupole moment of Re185 and Re187 from the hyperfine structure of muonic X rays

The hyperfine splitting of the 5g -> 4f transitions in muonic 185,187-Re has been measured using high resolution HPGe detectors and compared to state-of-the-art atomic theoretical predictions. The spectroscopic quadrupole moment has been extracted using modern fitting procedures and compared to the values available in literature obtained from muonic X rays of natural rhenium. The extracted values of the nuclear spectroscopic quadrupole moment are 2.07(5) barn and 1.94(5) barn, respectively for 185-Re and 187-Re. This work is part of a larger effort at the Paul Scherrer Institut towards the measurement of the nuclear charge radii of radioactive elements.

Instrumental Neutron Activation Analysis of Egyptian Phosphate Samples and Adsorption Studies of Their Elemental Contents

Samples of Egyptian phosphate ore obtained from Om Salmah mine at El-Sibaiya, Nile valley, were analyzed for some lanthanides and concomitant elements by instrumental neutron activation analysis. The use of a high-resolution HPGe detector connected to a PC-based multichannel analyzer enabled simultaneous nondestructive multielement analysis in a single irradiation run with good accuracy. The following elements were determined after relatively short cooling time (5 days): lanthanides (La, Ce, Eu, Nd, Sm, Gd, Tb, Yb), concomitant elements (Ba, Br, Ca, Co, Cr, Fe, Hf, Na, Rb, Sb, Sc, Se, Sr, Zn, Zr), and actinides (Th, U). After longer cooling time, the following elements were determined: La, Ce, Nd, Eu, Gd, Tb, Yb, and the concomitant elements: Cr, Fe, Hf, Nb, Sc, Th, Co, Zn, and Zr. Adsorption experiments were performed on synthesized inorganic ion exchangers: zirconium titanium phosphate (ZTP) with different Zr : Ti molar ratios and ceric tungstate (CeW), as well as on organic cation and anion exchangers: Dowex-50×8 and Dowex-1×8, respectively. The adsorption was performed from solutions containing dilute HCl and HNO3, formed by dissolving the irradiated phosphate samples in aqua regia, diluting, and cooling for a certain time. The effect of some factors on the adsorption was studied. Some options for separating the elements were suggested.

Isomeric Cross Section Study of Neutron Induced Reactions on Ge Isotopes

In the present work, natural Ge targets have been irradiated by neutron beams of 17.7 and 19.3 MeV, at the 5MV tandem accelerator of NCSR "Demokritos". The cross section of the 72,74Ge(n,α)69,71Zn and 76Ge(n,2n)75Ge reactions, leading to the population of isomeric states, has been deduced with respect to the 27Al(n,α)24Na and 93Nb(n,2n)92mNb reference reactions. After the neutron irradiations, the induced γ-ray activity of the Ge target and reference foils, was measured with high-resolution HPGe detectors.

The use of self-induced X-ray fluorescence in gamma-ray spectroscopy of uranium ore samples

Gamma logging for uranium exploration are currently based on total counting with Geiger Müller gas detectors or NaI (TI) scintillators. However, the total count rate interpretation in terms of uranium concentration may be impaired in case of roll fronts, when the radioactive equilibrium of the natural 238U radioactive chain is modified by differential leaching of uranium and its daughter radioisotopes of thorium, radium, radon, etc. Indeed, in case of secular equilibrium, more than 95 % of gamma rays emitted by uranium ores come from 214Pb and 214Bi isotopes, which are in the back-end of 238U chain. Consequently, these last might produce an intense gamma signal even when uranium is not present, or with a much smaller activity, in the ore. Therefore, gamma spectroscopy measurements of core samples are performed in surface with high-resolution hyper-pure germanium HPGe detectors to directly characterize uranium activity from the 1001 keV gamma ray of 234mPa, which is in the beginning of 238U chain. However, due to the low intensity of this gamma ray, i.e. 0.84 %, acquisitions of several hours are needed. In view to characterize uranium concentration within a few minutes, we propose here a method using both the 92 keV gamma ray of 234Th and the 98.4 keV uranium X-ray. This last is due to uranium self-induced fluorescence caused by gamma radiations of 214Pb and 214Bi, which create a significant Compton scattering continuum acting as a fluorescence source and resulting in the emission of uranium fluorescence X-rays. The comparison of the uranium activity obtained with the 92 keV and 98.4 keV lines allows detecting a uranium heterogeneity in the ore. Indeed, in case of uranium nugget, the 92 keV line leads to underestimated uranium concentration due to gamma self-absorption, but on the contrary the 98.4 keV line leads to an overestimation because of increased fluorescence. In order to test this new approach, several tens of uranium ore samples have been measured with a handheld HPGe FALCON 5000 detector.

In vivo measurement of pre-operational spallation source workers: baseline body burden levels and detection limits of relevant gamma emitters using high-resolution gamma spectrometry

As a measure to prepare for long-term internal dose monitoring of workers at the European Spallation Source (ESS) in Lund, Sweden, operated by the European Research Infrastructure Consortium (ERIC), as well as to enhance emergency preparedness against accidental releases, a series of in vivo measurements were conducted using a high-resolution HPGe detector with a 123% relative efficiency (1.332 MeV). This study describes the whole-body counting set-up, calibration procedure, and subsequent validation measurements using conventional NaI(Tl)-scanning-bed geometry on a selection of workers from the ESS. Detection limits for the relevant gamma emitters 7Be, 172Hf, and 182Ta were determined to be 65 Bq, 130 Bq, and 22 Bq, respectively, using a 2400 s acquisition time. The baseline measurements suggest that care must be taken to ensure that the fluctuations in the presence of radon daughters 214Bi and 214Pb are minimised by, for example, ensuring a minimum air exchange between the measuring room and the ambient air, and by demanding that the measured subjects change clothes and shower before measurement. Furthermore, in a monitoring program for internal doses to spallation source workers, the presence of radionuclides originating from non-work-related sources (such as 226Ra from private water wells or 137Cs from intakes of Chernobyl contaminated foodstuffs), or radionuclides from previous work history (such as 60Co within the nuclear power industry), must be considered.

Performance assessment of a 500 mm3 CZT and a 2x2 inch LaBr3(Ce) detectors for the determination of the uranium enrichment using the enrichment-meter method and calibration standards for safeguards applications

Determination of the uranium enrichment is an important safeguards verification task, routinely carried out using non-destructive assay methods. The enrichment-meter method is one of the most widely used passive non-destructive X- and gamma-ray based methods used for such tasks. Among its advantages is the highly constrained physical nature of its underlying formalism, allowing it to be used with high-resolution HPGe detectors, as well as with low-resolution NaI detectors. Due to attractive features and spectroscopic performance, CdZnTe and LaBr3(Ce) detectors raised interest in their application to such tasks as well. However, their spectroscopic performance is different to that of the traditional detectors in many ways. Application of the enrichment-meter method requires determination of the net peak areas corresponding to 235U signature photopeaks. The latter requires an adequate algorithm to select the region-of-interest boundaries, which may be sensitive to asymmetrical photopeaks of CZT detectors. In this paper we conduct a performance assessment of a 500 mm3 CZT detector of a quasi-hemispherical design and a 2 × 2 inch LaBr3(Ce) scintillator with the enrichment-meter method using a set of certified uranium standards with enrichment degrees from 0.31% to 4.46% of 235U atomic abundance. We investigate the impact of different methods used for net peak area determination, statistical quality of acquired spectra and size of region-of-interest boundaries on accuracy and uncertainty. We propose an algorithm for symmetrical/asymmetrical region-of-interest boundaries determination and make recommendations on the best combinations of the region-of-interest size and method used for the net peak area determination for each of the detectors. The underlying routines of the algorithm and analysis procedures are described in detail and results are presented.

Determination of the 193Ir(n, 2n) reaction cross section and correction methodology for the 191Ir(n,$ \gamma$) contamination

The cross section of the 193Ir(n, 2n)192Ir reaction has been determined by means of the activation technique, relative to the 27Al (n,$ \alpha$) and 197Au(n, 2n) reference reactions cross sections, at neutron beam energies ranging from 10 to 21 MeV. The quasi-monoenergetic neutron beams were produced at the 5.5 MV Tandem T11/25 Accelerator Laboratory of NCSR “Demokritos” via the 2H(d, n) and 3H(d, n) reactions. The induced $ \gamma$-ray activity of the irradiated target and reference foils was measured with high resolution HPGe detectors. In order to correct for the contribution of the 191Ir(n,$ \gamma$)192Ir reaction, which is open to low energy parasitic neutrons, a recently developed analysis method was implemented and it is presented in great detail. Furthermore, cross section theoretical calculations were carried out using the EMPIRE and TALYS codes over a wide energy range.

Fragment production in proton–induced reaction on Bi209 target at intermediate energy range

We used the phasotron of the Laboratory of Nuclear Problems at JINR to irradiate isotopically pure $^{209}\mathrm{Bi}$ target with 660 MeV protons. Cross sections of the fragment production with mass numbers $24\ensuremath{\le}A\ensuremath{\le}210$ u were measured for the first time using the direct $\ensuremath{\gamma}$-spectrometry method with a high-resolution HpGe detector. The $\ensuremath{\gamma}$ lines of the fragments have been identified, and the cross sections determined by the deimos code. The results of the measured nuclide cross section have been parametrized in terms of a three-parameter equation in order to reproduce the real isobaric distribution. Fission and spallation mass yields have been reconstructed on the base of charge distribution of reaction products. The main reaction results have been compared with other experimental data obtained from the proton-induced reaction at 600 MeV as well as with theoretical model calculations using the crisp code.

Activation cross sections of alpha-induced reactions on natural ytterbium up to 50 MeV

Activation cross sections of α-particle induced reactions on natYb were measured. The stacked foil technique, the activation method and the γ-ray spectrometry were used. The stacked target consisted of natYb and natTi foils was irradiated with a 51.0-MeV α beam at the RIKEN AVF cyclotron. The γ rays emitted from the irradiated foils were measured using a high-resolution HPGe detector. Production cross sections of 170,171,172,173,175Hf, 171,172,173,177gLu and 169Yb were determined. The results were compared with previous experimental studies and theoretical calculations. For most of the reactions a consistent agreement was found.

New measurement of the 241Am(n,2n)240Am cross section

Cross section for 241Am(n,2n)240Am reaction has been measured at the VdG Tandem accelerator of NCSR “Demokritos", at neutron beam energy 10.4 MeV, using the activation technique. The high purity and high radioactivity (5GBq) Am target has been constructed at IRMM, Belgium and consisted of 40 mg Am in the form of AmO2 pressed into pellet with Al2O3 and encapsulated into Al container. The absolute flux of the beam was obtained with respect to the 27Al(n,α)24Na reference reaction. The induced gamma-ray activity of 240Am and 24Na was measured with high resolution HPGe detectors.

Activation cross section for the (n,2n) reaction on 197Au

The cross section of the reaction channels 197Au(n,2n)196Aug+m1 and 197Au(n,2n)196Aum2 has been experimentally determined at 15.3 MeV, relative to the 27Al(n,α)24Na reference reaction, using the activation technique. The irradiation was carried out at the 5 MV tandem T11/25 Accelerator Laboratory of NCSR "Demokritos" with monoenergetic neutron beam provided by means of the 3H(d,n)4He reaction, using a new Ti-tritiated target of 373 GBq activity. The induced γ- ray activity was measured with a high resolution HPGe detector.

Environmental Impact Assessment of Natural Radioactivity, Heavy and Major Metals in Primary Schools’ Drinking Water

Measurement of natural radioactivity levels of major and heavy metals concentration was carried out for water samples collected from primary schools in Jeddah city, Saudi Arabia. The estimations were done for two different age groups, children (students 7 - 12 y) and adults (teachers and workers > 17 y) at the schools. The chemical analysis was performed by an Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES) and a high-resolution HPGe detector was used for the natural radionuclides measurement. The obtained results for the heavy metals (Fe, Cu, and Zn) and major and heavy elements (Na, K, Ca and Mg) concentrations in all water samples did not exceed the limits of WHO, EPA and TSE-266 guidelines for drinking water. Only Pb exceeded the safe limit. Generally, heavy metals and major elements’ concentrations in water samples were found decrease in sequence of Ca > Na > Mg > K > Zn > Pb > Cu > Fe. The radioactivity concentrations of 226Ra, 232Th and 40K in all studied samples were below the permissible safe limit value. The total average annual effective doses of (226Ra + 232Th + 40K) radionuclides were 0.259 mSv.y-1 for the children and 0.112 mSv.y-1 for adults, which are below the recommended annual dose level 1.0 mSv.y-1 as reported by WHO (2006). The present drinking waters are high quality waters and safe in terms of natural radioactivity and the results of the HQ values for the individual heavy metals showed that there was no health risk for humans due to consumption of these waters.

Radiation protective qualities of some selected lead and bismuth salts in the wide gamma energy region

Abstract The lead element or its salts are good radiation shielding materials. However, their toxic effects are high. Due to less toxicity of bismuth salts, the radiation shielding properties of the bismuth salts have been investigated and compared to that of lead salts to establish them as a better alternative to radiation shielding material to the lead element or its salts. The transmission geometry was utilized to measure the mass attenuation coefficient (μ/ρ) of different salts containing lead and bismuth using a high-resolution HPGe detector and different energies (between 81 and 1333 keV) emitted from point sources of 133Ba, 57Co, 22Na, 54Mn, 137Cs, and 60Co. The experimental μ/ρ results are compared with the theoretical values obtained through WinXCOM program. The theoretical calculations are in good agreement with their experimental ones. The radiation protection efficiencies, mean free paths, effective atomic numbers and electron densities for the present compounds were determined. The bismuth fluoride (BiF3) is found to have maximum radiation protection efficiency among the selected salts. The results showed that present salts are more effective for reducing the intensity of gamma photons at low energy region.