A Monte Carlo study of radon detection in cylindrical diffusion chambers

The functioning of radon diffusion chambers was studied using the Monte Carlo code RAMMX developed here. The alpha particles from radon are assumed randomly produced in the volume of the cylinder, and those from the progeny are assumed to originate randomly at the cylindrical surface. The energy spectrum, the distribution of incident angles, and the distribution of path lengths of the alpha particles on the detector were obtained. These quantities vary depending on input parameters such as initial alpha particle energy, radius and depth of the diffusion chamber, detector size and atmospheric pressure. The calculated energy spectrum for both ²²²Rn and ²²⁰Rn was compared with experiment, permitting the identification of each peak and its origin, and a better understanding of radon monitoring. Three aspects not considered in previous calculations are progeny alphas coming from surfaces of the monitor, taking into account the atmospheric pressure, and including the isotope ²²⁰Rn.     

Arrival time and magnitude of airborne fission products from the Fukushima, Japan, reactor incident as measured in Seattle, WA, USA

We report results of air monitoring started due to the recent natural catastrophe on 11 March 2011 in Japan and the severe ensuing damage to the Fukushima Dai-ichi nuclear reactor complex. On 17-18 March 2011, we registered the first arrival of the airborne fission products ¹³¹I, ¹³²I, ¹³²Te, ¹³⁴Cs, and ¹³⁷Cs in Seattle, WA, USA, by identifying their characteristic gamma rays using a germanium detector. We measured the evolution of the activities over a period of 23 days at the end of which the activities had mostly fallen below our detection limit. The highest detected activity from radionuclides attached to particulate matter amounted to 4.4 ± 1.3 mBq m⁻³ of ¹³¹I on 19-20 March.     

Radioactivity in trinitite six decades later

The first nuclear explosion test, named the Trinity test, was conducted on July 16, 1945 near Alamogordo, New Mexico. In the tremendous heat of the explosion, the radioactive debris fused with the local soil into a glassy material named Trinitite. Selected Trinitite samples from ground zero (GZ) of the test site were investigated in detail for radioactivity. The techniques used included alpha spectrometry, high-efficiency gamma-ray spectrometry, and low-background beta counting, following the radiochemistry for selected radionuclides. Specific activities were determined for fission products (90Sr, 137Cs), activation products (60Co, 133Ba, 152Eu, 154Eu, 238Pu, 241Pu), and the remnants of the nuclear fuel (239Pu, 240Pu). Additionally, specific activities of three natural radionuclides (40K, 232Th, 238U) and their progeny were measured. The determined specific activities of radionuclides and their relationships are interpreted in the context of the fission process, chemical behavior of the elements, as well as the nuclear explosion phenomenology.     

Evaluation of 210Pb and 210Po in cigarette tobacco produced in Brazil

Cigarette smoking is one of the pathways that might contribute significantly to the increase in the radiation dose reaching man, due to the relatively large concentrations of 210Pb and 210Po found in tobacco leaves. In the present study, the concentrations of these two radionuclides were determined in eight of the most frequently sold cigarette brands produced in Brazil. 210Pb was determined by counting the beta activity of 210Bi with a gas flow proportional detector after radiochemical separation and precipitation of PbCrO4. 210Po was determined by alpha spectrometry using a surface barrier detector after radiochemical separation and spontaneous deposition of Po on a copper disk. The results showed concentrations ranging from 11.9 to 30.2 mBq per gram of dry tobacco for 210Pb and from 10.9 to 27.4 mBq per gram of dry tobacco for 210Po. The collective committed effective dose resulting from the use of cigarettes produced in Brazil per year is estimated to be 1.5 x 10(4) man-Sv.     

Radioactivity concentrations and dose assessment for soil samples around Adana, Turkey

The concentrations of natural radionuclides in surface soils around Adana, Turkey were determined using gamma ray spectrometry with an HPGe detector. The natural gamma ray radioactivity of the terrestrial radionuclides in air was calculated throughout different areas of Adana. The average activity concentrations of (238)U, (232)Th and (40)K were found to be 17.6, 21.1 and 297.5 Bq kg(-1), respectively. Outdoor gamma dose measurements in air 1m above ground level were determined by using a portable gamma scintillation detector. The gamma dose measurements in air were taken from the same places where soil samples were taken. Average outdoor gamma dose rates in sample stations were determined as 67 nGy h(-1). The annual effective dose to the public was found to be 82 microSv.     

Extraction of full absorption peaks in airborne gamma-spectrometry by filtering techniques coupled with a study of the derivatives. Comparison with the window method

In this paper, an adaptation of a spectral profile analysis method, currently used in high-resolution spectrometry, to airborne gamma measurements is presented. A new algorithm has been developed for extraction of full absorption peaks by studying the variations in the spectral profile of data recorded with large-volume NaI detectors (16 l) with a short sampling time (2 s). The use of digital filters, taking into consideration the characteristics of the absorption peaks, significantly reduced the counting fluctuations, making detection possible based on study of the first and second derivatives. The absorption peaks are then obtained by modelling, followed by subtraction of the Compton continuum in the detection window. Compared to the conventional stripping ratio method, spectral profile analysis offers similar performance for the natural radioelements. The 137Cs 1SD detection limit is approximately 1200 Bq/m2 in a natural background of 200 Bq/kg 40K, 33 Bq/kg 238U and 33 Bq/kg 232Th. At low energy the very high continuum leads to detection limits similar to those obtained by the windows method, but the results obtained are more reliable. In the presence of peak overlaps, however, analysis of the spectral profile alone is not sufficient to separate the peaks, and further processing is necessary. Within the framework of environmental monitoring studies, spectral profile analysis is of great interest because it does not require any assumptions about the nature of the nuclides. The calculation of the concentrations from the results obtained is simple and reliable, since only the full absorption contributions are taken into consideration. A quantitative estimate of radioactive anomalies can thus be obtained rapidly.     

Uranium decay products found on Mir space blanket mitt

The space blanket mitt which covered the Trek detector on Mir during four years of orbital flight has been measured for gamma radiation with HPGe and multidimensional spectrometers. Difference spectra from very-long-period spectrometer runs on the mitt and on a similar non-deployed mitt from the same manufacturer show that the mitt has acquired small but significant amounts of gamma radioactivity during orbital flight. Twelve gamma-ray peaks have been measured in the difference spectra, including peaks identified as due to 214Bi and 214Pb from the uranium-radium alpha decay series, and others possibly due to the uranium-actinium series. This implies the presence of a sparse population of uranium decay products in lower orbital space which can only have come from nuclear explosions, burned-up satellite nuclear batteries, the solar wind, or supernova fragments in the local interstellar medium.     

A note on 207Bi in environmental samples

Traces of the radionuclide (207)Bi were identified in soil and cryoconite (glacier sediment) samples from Alpine regions of Austria. This nuclide has been produced in thermonuclear explosions mainly in the early 1960s and subsequently dispersed in the atmosphere. Activity concentrations up to 22 Bq/kg d.m. have been found. The ratio (207)Bi:(137)Cs(global fallout) equals (1.70+/-0.12)10(-3), which is in accordance with literature data. When low levels of (207)Bi are assessed by gamma spectrometry, corrections must be made for a gamma line produced in the lead shield by neutron activation due to cosmic neutrons.     

Fission Product tin in sediments

We describe a method for the determination of long-lived tin isotopes arising from nuclear fission. The isotopes are extracted from sediments with hydrochloric acid and separated by methylisobutylketone extraction, ion-exchange chromatography, precipitation of cesium hexachlorostannate and ferric hydroxide coprecipitation. The 100 000-year ¹²⁶Sn was not detected but beta activity consistent with ^121mSn (55 year) was found in sediment samples from a location known to be contaminated with fission products.     

A code to simulate nuclear reactor inventories and associated gamma-ray spectra

A computer code has been developed to simulate the gamma-ray spectra that would be measured by airborne gamma spectrometry (AGS) systems from sources containing short-lived fission products. The code uses simple numerical methods to simulate the production and decay of fission products and generates spectra for sodium iodide (NaI) detectors using Monte Carlo codes. A new Monte Carlo code using a virtual array of detectors to reduce simulation times for airborne geometries is described. Spectra generated for a short irradiation and laboratory geometry have been compared with an experimental data set. The agreement is good. Spectra have also been generated for airborne geometries and longer irradiation periods. The application of this code to generate AGS spectra for accident scenarios and their uses in the development and evaluation of spectral analysis methods for such situations are discussed.     

CR-39 autoradiographic micromapping of rock sections of various alpha emitters content--calibration approach

The autoradiographic micromapping of rocks with various U and Th contents has been performed by means of CR-39 solid-state nuclear track detector (SSNTD). The optical track density was found to be highly correlated (r=0.92) with total alpha emitters activity calculated on the basis of field gamma spectrometric measurements of rock outcrops. The method was tested not only for the wide range activities of alpha emitters but various types of surface distribution (including highly radioactive mineral grains) as well.     

Measuring the radium-226 activity using a multidetector γ-ray coincidence spectrometer

Bиccлoвaнияx вoэмocy;жнocтeф пpимeн eния мeтoдoв coвaдeниф дффeктив нoгo cхeтa иэиuхaтeлeф пoхитpoнoв в б oльщиx oбpaэцax, pнpимeня жидкocт ныф cцинтлляциoнныф cхeтхик 4π для вceгo, cocтoяшиф иэ 2-x дeтeктocy;pныx кaмep 2π. Пpeждe вceгo иэuхaлocв oбpaэoвaниe фoн a, кaк oтвeтнaя peaция в мeтoдe co coвпaдeниф. B peэuлвтaтe импuлвcoв coвпaдeни ф в oбoиx дeтeктopныx кaмepax нaблю энaхитeлвныф uхacтoк фoнa. Иэuхaлacvcy; пoдaвлeни я фoнa пuтa cхeтa пueтa cхeтa aнт иcoвпaдeнeниф, нo этoт мeтoд нe oкaэaлcя uля uлu oхыхныx гaммa-иэлucy;хaтaeлeф. oднaк o, в cлнaяx, кoгпa в oбpaэцax coдepж aлиcв тaкиe иэлuхaтeли пoэитpoнoв, кaк ²²Na и ⁵⁸ co, фoн мoжнo былo энaхитeлвнo пoд aвитв и cхeтнuю cтaтиcтикu нa нa мнoгo юл юхшитв пpимeняя пpимeняя cпoco бы ы coвпaдeниф. Этoт мeтoд нe тoдвкo uмeнвщaeт фoн, нo тaкиe мoнoгaмм-иэлuхaтeли, кaк ¹³⁷Cs ⁴⁰К. Taким oбким oбpaэoм, этoт мeт oд нaпpaшивaeтcя caм coбoф для иэ peния иэлuхaтeлeф пoэитpoнoв в хeлoвeкe, гдe ¹³⁷Cs ⁴⁰К п pиcuтcтвuют, кaк интepфиpuюшиф фoн:.

Zusammenfassung

Ein 4π-Flüssigkeits-“Ganzkörper”-Szintillationszähler, bestehend aus 2π-Detektrortanks wurde dazu verwendet, die mögliche Anwendung von Koinzidenzarbeitsweisen zur wirksamen Zählung von Positronenemittern in grossen Proben zu studieren. Zunächst wurde die Hintergrundemp-findlichkeit für die Koinzidenzform untersucht. Man beobachtete, dass ein ansehnlicher Teil des Hintergrundes von Impulsen in der Koinzidenz in beiden Detektortanks herrührte. Die Möglichkeit einer Unterdrückung des Hintergrundes durch Antikoinzidenzzählung wurde erforscht, aber dies stellte sich als unbrauchbar für eine Verbesserung der Zählstatistik zum Zählen gewöhnlicher Gammaemitter heraus. Wenn die Proben jedoch Positronenemitter wie ²²Na and ⁵⁸Co enthalten, so könnte der Hintergrund weitgehend unterdrückt und die Zählstatistik beträchtlich verbessert werden, wenn man Koinzidenzzählverfahren anwendet. Das Verfahren verminderte nicht nur den Hintergrund, sondern es diskriminierte auch gegenüber solchen Monogammaemittern wie ¹³⁷Cs und ⁴⁰K. Das Verfahren eignet sich somit zur Messung von Positronenemittern im Menschen, wo ¹³⁷Cs und ⁴⁰K als “Störhintergrund” zugegen sind.

Absorbed dose in target cell nuclei and dose conversion coefficient of radon progeny in the human lung

To calculate the absorbed dose in the human lung due to inhaled radon progeny, ICRP focussed on the layers containing the target cells, i.e., the basal and secretory cells. Such an approach did not consider details of the sensitive cells in the layers. The present work uses the microdosimetric approach and determines the absorbed alpha-particle energy in non-spherical nuclei of target cells (basal and secretory cells). The absorbed energy for alpha particles emitted by radon progeny in the human respiratory tract was calculated in basal- and secretory-cell nuclei, assuming conical and ellipsoidal forms for these cells. Distributions of specific energy for different combinations of alpha-particle sources, energies and targets are calculated and shown. The dose conversion coefficient for radon progeny is reduced for about 2mSv/WLM when conical and ellipsoidal cell nuclei are considered instead of the layers. While changes in the geometry of secretory-cell nuclei do not have significant effects on their absorbed dose, changes from spherical to conical basal-cell nuclei have significantly reduced their absorbed dose from approximately 4 to approximately 3mGy/WLM. This is expected because basal cells are situated close to the end of the range of 6MeV alpha particles. This also underlines the significance of better and more precise information on targets in the T-B tree. A further change in the dose conversion coefficient can be achieved if a different weighting scheme is adopted for the doses for the cells. The results demonstrate the necessity for better information on the target cells for more accurate dosimetry for radon progeny.     

Simultaneous biological removal of endosulfan (alpha+beta) and nitrates from drinking waters using wheat straw as substrate

Nitrate and endosulfan (alpha+beta) removal was studied in an upflow biological denitrification reactor packed with wheat straw as carbon source and support particles for microorganisms. While almost complete nitrate elimination and between 65% and 70% endosulfan (alpha+beta) elimination occurred when the temperature was higher than 20 degrees C; below that value, nitrate removal efficiency decreased to about 10%. Nitrate, dissolved organic carbon (DOC), and endosulfan (alpha+beta) removal efficiencies decreased considerably at 1500 microg/l endosulfan concentration in the batch experiments. Although a high removal efficiency was observed for endosulfan (alpha+beta) and nitrate in the biological denitrification continuous reactor, the effluent water could not be used for drinking purpose because of the unacceptable levels of endosulfan (alpha+beta), colour and dissolved organic content. During the continuous study, 23.4% of the initial weight of wheat straw was lost and 24 g was consumed per gram of nitrogen removed. The results of the continuous study showed that 21.3% of the endosulfan removal was achieved by adsorption onto the wheat straw and 68.2% of the endosulfan removal occurred by biological activity and the remaining portion was detected in the effluent water.     

Assessment of the environmental contamination with long-lived radionuclides around an operating RBMK reactor station

The presence of man-made gamma emitting radionuclides in the region within 32km radius of the Ignalina NPP/Lithuania has been investigated during the period 2001-2004, prior to the closure of the first of the two operating RBMK 1500-type reactors. Gamma spectrometric measurements of various terrestrial and aquatic plants as well as of soil samples showed moderate environmental contamination with the fission product (137)Cs and with the neutron activation products (60)Co and (54)Mn. Traces of the activation products (65)Zn and (110m)Ag were found in the nearest vicinity of the NPP. Activity concentrations were inhomogeneously distributed in the area of interest. Moss and algae samples showed the highest uptake of radionuclides. In addition to the gamma spectrometric measurements, the levels of (14)C were determined in the same bio-indicator samples using accelerator mass spectrometry.     

Development of an energy discriminate CR-39(®) nuclear track etch dosimeter for Radon-220 gas measurements

An energy discriminate CR-39^® nuclear track etch dosimeter for use in a ²²⁰Rn and ²²²Rn gas monitor has been developed and experimentally assessed. It utilises a thin film of Mylar^® C to attenuate the alpha particle energies to allow only the damage tracks created by the 8.785 MeV alpha particles emitted from ²¹²Po of the ²³²Th decay chain to be registered in the CR-39^® plaque, allowing for the direct measurement of ²²⁰Rn gas concentrations. The dosimeter was developed through a combination of experimental investigations and theoretical simulations using the Monte Carlo ion transport modelling program Stopping and Range of Ions in Materials (SRIM 2008). A film thickness of 54 μm has been shown to attenuate all alpha energies less then 7.7 MeV.     

He mass spectrometry for very low-level measurement of organic tritium in environmental samples

The design, setup and performance of a mass spectrometric system for the analysis of low to very low-level tritium in environmental samples are described. The tritium concentration is measured indirectly by the ³He ingrowth from radioactive decay after complete initial degassing of the sample. The analytical system is fully computer-controlled and consists in a commercial helium isotope mass spectrometer coupled with a high vacuum inlet system. A detection limit of 0.15 Bq/kg is routinely obtainable for sample sizes of 20 g of water equivalent and an accumulation time of three months. Larger samples (and/or longer accumulation time) can be used to obtain lower detection limits. In addition to the benefit of a lower detection limit, another advantage of this non-destructive method lies in the simplicity of the analytical procedure which strongly limits the risk of contamination. An inter-comparison was successfully performed with the conventional beta counting technique on lyophilized grass samples, in a range of tritium concentrations of environmental interest. It shows that the ³He mass spectrometry method yields results that are fully consistent with the conventional liquid scintillation technique over a wide range of tritium concentrations.     

Estimating the date corresponding to the horizon of the first detection of 137Cs and 239+240Pu in sediment cores

The anthropogenic bomb fallout nuclides 137Cs and plutonium isotopes (240Pu, 239Pu) are important chronometers for the determination of recent sediment accumulation rates using sediment cores collected from various water bodies. One of the crucial time horizons used to date sediment core profiles corresponds to the date of first detection of these nuclides. Although atmospheric nuclear testing began during the mid-1940s, the year corresponding to a nuclide's first detection when measured in 2006 depends on a number of factors including fallout history, radioactive half-life, gamma/alpha detection limits, geographic latitude and the accumulated thickness of the sediment section. This paper reports estimations of the year of first detection in sediment profiles of fallout 137Cs and Pu measured by gamma and alpha spectrometry, respectively. We find that for the latitude 30-40 degrees south of the equator the year of first detection for 137Cs is 1955. The date is earlier in the northern hemisphere due to higher fallout rates. Due to better measurement sensitivity first detection of Pu is generally earlier than 137Cs by 1-2 years.     

Intercomparison of alpha and gamma spectrometry techniques used in (210)Pb geochronology

(210)Pb geochronology is a widely used tool in sedimentological studies aimed at the absolute ages of modern sediments (up to 100 years). (210)Pb activities required to model sedimentation regimes are measured using either alpha, gamma or beta spectrometry. Sediment accumulation rates derived from (210)Pb activity profiles measured by these methods are often used interchangeably in mass balance studies. Yet there is a lack of investigations considering the comparability of data derived using different analytical methods. Differences between methods could be caused by different behaviors of (210)Pb and (210)Po (used for alpha measurement) in the marine environment. In gamma spectrometry errors may arise when many gamma emitters are measured simultaneously and their activity peaks overlap. In alpha spectrometry chemical separation of (210)Po may result in analytical error due to incomplete sample dissolution. In the present study we evaluate total, supported and excess (210)Pb activities and their use in deriving sediment accumulation rates and (210)Pb excess inventories for three sediment cores collected from the Barents Sea. (210)Pb activities derived by alpha and gamma methods are shown to agree within counting error and there is also good agreement in the derived sediment accumulation rates. The inherent compatibility of analytical results based on alpha or gamma techniques is established.     

Depleted uranium particles in selected Kosovo samples

Selected soil samples, collected in Kosovo locations where DU ammunition was expended during the 1999 Balkan conflict, have been investigated by secondary ion mass spectrometry (SIMS), X-ray fluorescence imaging using a micro-beam (micro-XRF) and scanning electron microscopy equipped with an energy dispersive X-ray fluorescence detector (SEM-EDXRF), with the objective to test the suitability of these techniques to identify the presence of small DU particles and measure their size distribution and the 235U/238U isotopic ratio (SIMS). Although the results do not permit any legitimate extrapolation to all the sites hit by the DU rounds used during the conflict, they indicated that there can be "spots ' where hundreds of thousands of particles may be present in a few milligrams of DU contaminated soil. The particle size distribution showed that most of the DU particles were <5 microm in diameter and more than 50% of the particles had a diameter <1.5 microm. Knowledge on DU particles is needed as a basis for the assessment of the potential environmental and health impacts of military use of DU, since it provides information on possible re-suspension and inhalation.