bluuebunny/crossref_metadata_2025_split huggingface dataset:
Human Population Exposure to Cosmic Radiation
Authors: Bouville A. , Lowder (INVITED) W.M. 
Published: February 2017

Abstract
Critical evaluations of existing data on cosmic radiation in the atmosphere and in interplanetary space have been carried out in order to estimate the exposure of the world's population to this important component of natural background radiation. Data on population distribution and mean terrain heights on a 1 x 1 degree grid have been folded in to estimate regional and global dose distributions. The per caput annual dose equivalent at ground altitudes is estimated to be 270 µSv from charged particles and 50 µSv from neutrons. More than 100 million people receive more than 1 mSv in a year, and two million in excess of 5 mSv. Aircraft flight crews and frequent flyers receive an additional annual dose equivalent on the order of 1 mSv, though the global per caput annual dose equivalent from airplane flights is only about 1 µSv. Future space travellers on extended missions are likely to receive dose equivalents in the range 0.1-1 Sv, with the possibility of higher doses at relatively high dose rates from unusually large solar flares. These results indicate a critical need for a better understanding of the biological significance of chronic neutron and heavy charged particle exposure.
Contribution to the Study of Portuguese Population Exposure to Gamma Radiation
Authors: Vaz Carreiro J. , Mateus do Amaral E. , Severo A. 
Published: February 2017

Abstract
The initiation and development of a programme of surveying gamma radiation in Portugal is reported. Outdoor measurements of gamma radiation levels were carried out all over the country, contributing first estimates towards the establishment of a radiological map. Three specific regions were studied in more detail. One of them is well known as a high background area where uranium mines are in operation and the other two are related to sites selected for the installation of nuclear power plants. Indoor measurements in dwellings were made in two specific areas, Distrito de Viseu and Distrito de Braganca, respectively, of high and medium radiation levels. These values are insufficient to give a complete picture of the population exposure but they give an overview of the average dose rates in the country and an estimate of the average population doses for two particular regions.
Radon Inhalation Studies in Animals
Authors: Cross F.T. 
Published: February 2017

Abstract
A summary of updated biological effects data resulting from chronic radon inhalation exposures of animals is presented. Emphasis is placed on the carcinogenic effects of radon and radon decay products, including the influences of radon progeny exposure rate, unattached fraction and disequilibrium, and co-exposures to other pollutants. Plausible values are provided for the radon (radon progeny) lifetime lung cancer risk coefficients.
A Generalised Formulation of Microdosimetric Quantities
Authors: Kellerer (INVITED) A.M. 
Published: February 2017

Abstract
The microdosimetric quantities energy imparted, lineal energy, and specific energy are defined with reference to certain volumes but are quantified in terms of frequency distributions of possible values without regard to spatial interrelations. Computer simulations of the patterns of energy deposits seem, therefore, only loosely related to the microdosimetric distributions. In a more general formulation one treats the specific energy and the related microdosimetric quantities as point functions; one deals then with the spatial distribution of their random values and not merely with the frequency of different values. A further extension of the formalism admits reference regions of vanishing size; the inchoate distribution of energy deposits is then the limit case of specific energy. The definitions are related to Matheron's concept of the regularisation of a spatial variable; this is a convolution process that permits a flexible mathematical treatment. One resulting possibility is the definition of specific energy with reference not to the conventional geometry of a sphere or a cylinder but to a disperse region of support. This extension provides distributions of specific energy that are relevant to diffusion or transport processes and it can help to free biophysical models from a one-sided fixation on the concept of geometric targets. The formalism is applied also to the definition of the proximity functions and the related spatial autocorrelation functions.
Modelling of Alpha Particle Induced Soft Errors in Dynamic Random Access Memories (DRAM)
Authors: Haque A.K.M.M. , Stevens D.S. , Al-Affan I.A.M. 
Published: February 2017

Abstract
In order to model the alpha-particle-induced soft error phenomenon in Dynamic Random Access Memories (DRAM), analytical methods of Bradford, and Pickel and Blandford have been used to calculate the chord length distribution in rectangular sensitive volumes, which are then compared with those for cylindrical volumes given by Charlton et al (Monte Carlo). Soft error rates (SER) for an alpha flux density of 10-4 particles µm-2.s-1 incident on a 256K DRAM have been calculated for a set of funnelling lengths in the range of 1.5 - 4.5 µm, and compared. The experimental values are well within the range of the computed SERs, the methods for which need further development.
Simulation of Space and Time Evolution of Radiolytic Species Induced by Electrons in Water
Authors: Terrissol M. , Beaudré A. 
Published: February 2017

Abstract
We present results obtained with Monte Carlo type codes able to calculate the space and time distributions of the radicals and the molecular products resulting from the water radiolysis between 10-15 and 1 s: e-aq, OH, H, H3O+, H2O2, OH-, H2, HO2. These basic data may then be used to carry out radiophysical, radiotherapic, microdosimetric or radiobiological applications or investigations.
Comparison of Particle Tracks Calculated by Monte Carlo Computer Codes with Experimental Tracks Observed with the Harwell Low Pressure Cloud Chamber
Authors: Briden P.E. , Holt P.D. 
Published: February 2017

Abstract
Photographs of the droplets associated with the ionisations caused by charged particle tracks in the Harwell low pressure cloud chamber have been analysed. The radiation types these represent are alpha particles, protons and low energy X rays (carbon and aluminium) in either tissue-equivalent gas or water vapour. The tracks were used to test the validity of two Monte Carlo codes developed by Wilson and Paretzke, namely MOCA14 for the generation of proton and alpha particle tracks, and MOCA8 for the generation of electron tracks. The comparisons showed that the code MOCA14 would appear to be valid for protons with energies greater than about 390 keV, and for alpha particles with energies greater than 1.6 MeV. No disagreement was found between the low energy X ray tracks from the cloud chamber and the tracks calculated from MOCA8, although this comparison was severely limited by droplet diffusion.
Radiosensitivity Parameters for Cancer-like Biological Endpoints in Some Mammalian Cell Cultures
Authors: Waligorski M.P.R. 
Published: February 2017

Abstract
Radiosensitivity parameters of Katz's cellular track structure model have been evaluated for oncogenic transformations and survival in C3H 10T1/2 cells from the data of Hei et al (1988), and for chromatid exchanges, abnormal metaphases and survival in CH2B2 cells, from the data of Skarsgard et al (1967). Model predictions for transformations and survival in the C3H 10T1/2 mammalian cell line after neutron irradiations are compared with the experimental data of Miller et al (1988, 1989).
Measurements of Quality Factors and Dose Equivalents with CIRCE Inside the Soviet Space Station MIR
Authors: Nguyen V.D. , Bouisset P. , Akatov Y.A. , Petrov V.M. , Kozlova S.B. , Siegrist M. , Zwilling J.F. 
Published: February 2017

Abstract
During the French-Soviet space mission 'Aragatz', the experiment CIRCE (Computer Intégrateur de Rayonnement Complexe dans l'Espace) recorded the dose rate and quality factor values inside the MIR station. This paper presents results obtained with a new active dose equivalent meter based on microdosimetric techniques and using a low pressure tissue-equivalent proportional counter. In terms of lineal energy the CIRCE device works in the 0.2 - 1200 keV.µm-1 range in tissue. Preliminary studies were performed in photon, neutron and heavy ion beams, and in the real stratosphere cosmic radiation field. Long-term measurements on board the MIR station from December 1988 to April 1989 gave an average quality factor value equal to 1.9 ± 0.3. Through the South Atlantic Anomaly (SAA), the quality factor was equal to 1.4. The temporal orbital variations of the dose rates and quality factors have been established in space dosimetry for the first time.
Microdosimetry of Radon and Radon Daughters
Authors: Caswell R.S. , Coyne J.J. 
Published: February 2017

Abstract
We have developed an analytical method for calculations of slowing down spectra (fluence rate spectra) and lineal energy spectra for radon and its important alpha emitting daughters, 218Po and 214Po. We have also made calculations of microdosimetric parameters and quality factors for radon-related alpha particles. The y spectra show some increase in average values of y with cell depth.
Point Defects and the Pre-Dose Effect in Quartz
Authors: Yang X.H. , McKeever S.W.S. 
Published: February 2017

Abstract
The thermal annealing properties of (H3O4)0 centres in single crystal SiO2 were studies by means of electron spin resonance (ESR). The data indicate that these centres take part in the TL process at 110 oC in this material. The mechanism suggested for this TL signal is the thermal release of electrons from (GeO4)- centres and their recombination with holes trapped at (A104)0 and (H3O4)0 centres. We have also monitored the radiation-induced infra-red absorption bands in order to examine the thermal stability of A10H centres. Correlations between the A10H annealing curves and the pre-dose thermal activation curves indicate that hydrogen impurities are mobile in the quartz lattice during the pre-dose activation sequence.
Self Optical Attenuation Coefficient of TL Glow in BeO Detectors
Authors: Lembo L. , Pimpinella M. , Mukherjee B. 
Published: February 2017

Abstract
Thin ceramic pellets of BeO are now being used in many institutions as cheap, reliable, personnel monitoring dosemeters. Morphologically, in contrast to LiF TLDs, the BeO detectors have an opaque microporous, and hard ceramic constitution. It is evident that during the readout of BeO chips, exposed to gamma rays, where the TL emission centres are uniformly distributed throughout the bulk of the detector, a substantial amount of TL output is absorbed inside the chip. The present paper describes the experimental procedure for the determination of the self-absorption coefficient of TL light in the Be0 Thermalox 995 detectors. The results show that the self absorption effect should be considered when comparing the TL readouts measured with BeO detectors of different thickness.
MOS Structure for Emergency Gamma and Proton Dosimetry
Authors: Litovchenko P.G. , Barabash L.I. , Rosenfeld A.B. , Khivrich V.I. , Zinets O.S. , Kuts V.I. , Marusan I.A. , Petrov V.I. , Sluchenkov G.F. , Koval G.N. , Fominych V.I. , Belovodskiy L.F. , Dumik A.I. , Kiblik V.Ya. 
Published: February 2017

Abstract
Effect of gamma and proton irradiation on threshold voltage shift ? VT for n-channel MOSFET has been studied. For MOSFET with zero gate bias during gamma irradiation the shift ? VT is linear with dose D? (up to doses of 10 Gy) and the sensitivity ? VT/D? is approximately 120 mV.Gy-1. The sensitivity of MOSFETs with positive gate bias Vg during irradiation varies as Vg 2/3 and no saturation is observed up to breakdown voltage. n-MOSFETs with bias of 100 V have the sensitivity of approximately 5 V.Gy-1. When n-MOSFETs are irradiated with 50 MeV protons the shift ? VT varies as Dp 0.67 (for proton doses Dp ranged from 0.2 to 900 Gy). The positive charge storage in oxide is shown to contribute mainly to the radiation sensitivity of n-MOSFETs investigated.
Lyoluminescence in a Non-Aqueous Medium
Authors: Dixon S.M. , Ettinger K.V. 
Published: February 2017

Abstract
Lyoluminescence of mannose in water has been compared with that in water-methanol mixtures and in pure methanol. The light yield is larger in methanol by a factor, dependent upon the dose, which can reach 20 times. The yield in methanol increases with the temperature of the solvent. The nature of the dose response curve and the onset of saturation are the same. The fading on storage is faster for readout in methanol.
Optimisation of LiF:Cu,Mg,P for Radiation Protection Dosimetry
Authors: Horowitz A. , Horowitz Y.S. 
Published: February 2017

Abstract
The results of our investigations of various parameters of the preparation procedure of thermoluminescent LiF:Cu,Mg,P are reported. The parameters under investigation are: (i) the relative concentration of the incorporated Mg, Cu and (PO4)-3 dopants; (ii) the influence of incorporation of oxygen; (iii) particle size distribution of the prepared powder samples; (iv) emission wavelength; (v) high temperature '300 oC, 10 min' pre-irradiation annealing. Incorporation of oxygen in the molten stage plays an essential role in the creation of thermoluminescence: 0.5 mol.% oxygen leads to a TL material with approximately twenty times the intensity of TLD-100. We also find that the relative intensity of the undesirable high-temperature TL (270 oC) shows no apparent correlation with oxygen or other dopant concentrations. The loss in TL sensitivity following 300 oC, 10 min annealing shows similar behaviour.
Relative Thermoluminescent Efficiency of LiF:Cu,Mg,P to Alpha Particles: Theory and Experiment
Authors: Horowitz Y.S. , Stern N. 
Published: February 2017

Abstract
The relative thermoluminescent response of LiF:Cu,Mg,P to 4 MeV alpha particles has been calculated theoretically using the convolution of the radial dose around the alpha particle track with the gamma generated TL dose response function, with the result ?a? = 0.04 ± 0.01. Experimentally, the alpha particle generated TL signal was measured with the irradiated side both facing and away from the photomultiplier in order to measure TL light self-absorption with the result µd = 1.32 ± 0.03 (1 SD), and ?a? = 0.065 ± 0.01 in reasonable agreement with theory and previous measurements of the fast neutron relative TL response. The very low sensitivity of LiF:Cu,Mg,P to high LET particles is a microdosimetric effect arising from the very rapid saturation of the TL signal at high ionisation density.
LiF(Mg,Cu.P) Thin Dosemeter for Skin Dose Measurement
Authors: Fang W. , Ziying Z. , Jian L. , Zhongmei Z. 
Published: February 2017

Abstract
The thin dosemeter is composed of 5 mg.cm-2 of LiF(Mg,Cu,P) powder bonded to a base tape of polyimide with organosilicon adhesive and covered by a 5-7 mg.cm-2 black film of polyethylene. The elements can be annealed at 240 oC and re-used more than 10 times with an uncertainty of 3-4%(1 SD). Its detection threshold is 30 µGy which remains unchanged after irradiation by a large dose of up to several Gy. The TL material utilised has good gamma energy response, whilst experiments indicate a relative response to beta rays from 147Pm, 204Tl and 90Sr-90Y of 0.38, 1.01 and 1.00 respectively. The background signal from the elements is equivalent to less than 150 µGy. The variation of the TL signal of the detector for exposure to 60Co ? rays at different angles of incidence of the radiation is within 4%. The dosemeters show satisfactory environmental stability and the elements can be used with general TL readers without need of any special design and operated manually.
Use of Solid State Nuclear Track Detectors in National Radiation Protection Monitoring Programmes
Authors: Guhr A. , Kraus W. , Rimpler A. , Sarenio O. , Lehmann R. 
Published: February 2017

Abstract
In the National Board of Nuclear Safety and Radiation Protection of the GDR solid state nuclear track detectors (SSNTD) have been used routinely both for individual neutron dosimetry and for long-term measurements of radon and radon daughter products in flats and in the environment. For neutron monitoring a fission track dosemeter is used for the simultaneous response to fast and intermediate neutrons, using Makrofol KG as a detector. The long-term dosemeter for registering radon and radon daughter products is based on the diffusion chamber principle. Makrofol DE 1-4 of 300 µm thickness is used as the detector. Detector evaluation and calibration methods are described in detail and detection limits are stated. In addition, a screening measuring method based on CR-39 is presented, allowing the rational performance of long-term measurements by radon diffusion chambers.
Relationship of Anomalous Fading to Feldspar Inclusions in Quartz
Authors: Fragoulis D. , Stoebe T.G. 
Published: February 2017

Abstract
The potential relationship between feldspar inclusions and anomalous fading in quartz is examined. Using scanning electron microscopy and electron microprobe observations, feldspar inclusions are observed to occur in natural quartz grains taken from a variety of locations. Anomalous fading in these samples is compared with the fraction of feldspar inclusions. The results indicate that the feldspar inclusions probably account only for a portion of the observed fading. The results also indicate than an HF etch is not necessarily reliable for the removal of feldspars from quartz samples.
The IAEA Intercomparison for Individual Monitoring
Authors: Griffith R.V. , Böhm J. , Herrman D. , Strachotinsky C. , Thompson I.M.G. 
Published: February 2017

Abstract
In 1985 the International Commission on Radiation Units and Measurements introduced a new set of operational quantities for radiation protection purposes through Report 39. A significant amount of additional information about these quantities was presented at the end of 1988 in ICRU Report 43. The International Atomic Energy Agency has been concerned with the impact of possible adoption of these quantities by its 113 Member States. In an effort to assess the potential degree of impact, and to begin defining recommendations for calibration procedures using the new quantities, the Agency implemented a Coordinated Research Programme on Intercomparison for Individual Monitoring in 1987. The first phase completed with a Research Coordination meeting of the participants in April, 1989. Photon exposures were provided at 11 energies over a range from 18 KeV to 1.25 MeV at three standards laboratories in Austria, the GDR and the UK. Technical coordination was provided by the PTB, Braunschweig. Twenty one laboratories from 19 countries participated with film, TLD of various types, and combination dosemeters. Irradiations were performed on the IAEA 30 cm cubic, water-filled phantom that is in use throughout its network of 61 Secondary Standard Dosimetry Laboratories. Conversion coefficients for the IAEA phantom were calculated by the PTB and confirmed through measurements at ASMW in the GDR. Preliminary results indicated that the type of dosemeter (film or TLD) had little effect on the quality of results. The most important factor appears to be the specific techniques used for data interpretation.
Analysis of Beta Radiation Fields in the Fuel Cycle
Authors: Burgkhardt B. , Piesch E. , Vilgis M. 
Published: February 2017

Abstract
Depth-dose distributions have been measured in typical beta-photon radiation fields of the fuel element cycle using TL detectors and shielding layers of varying thickness in source-to-detector distances between 5 cm and 80 cm. Five representative beta contaminants namely 58CO, 60Co, 124Sb, 106Ru/106Rh, 234Th/234Pa have been found. An analytical approach takes into account the absorption of low beta radiation within the detector thickness and in the air in order to assess the dose equivalent distribution as a function of tissue depth for any source-to-detector distance. Typical data are presented for the dose quantities (H'(0.07), H'(10) and for the relevant dose equivalents in the gonads and the lens of the eye.
Some Characteristics of the AEOI Neutriran Albedo Neutron Personnel Dosemeter
Authors: Sohrabi M. , Katouzi M. 
Published: February 2017

Abstract
The Neutriran Albedo Personnel Neutron Dosemeter (NAPND) is based on the combination of a sensitive polymer such as polycarbonate (PC) in contact with 6LiF or 10B pellets in a cadmium cover. By adding a 10B pellet in front, the design of the dosemeter can be such that when worn on the body, direct thermal neutron induced alpha tracks (TNIAT), albedo neutron induced alpha tracks (ANIAT) and fast neutron induced recoil tracks (FNIRT) can be simultaneously detected in a single electrochemically etched PC foil. To establish a national personnel neutron dosimetry service in Iran, different parameters such as the effect of 10B(n,a)7Li convertor thickness. Cd thickness and its diameter, dosemeter distance from the phantom, dosemeter angle with phantom and directional response were studied using different phantoms. Under optimised conditions, a sensitivity of 1500 tracks.cm-2.mSv-1 for 252Cf neutrons with a lowest value of 0.05 mSv was measured. The results of these studies are reported and discussed.
The Active Personnel Dosemeter - Apfel Enterprises Superheated Drop Detector
Authors: Ipe N.E. , Donahue R.J. , Busick D.D. 
Published: February 2017

Abstract
The Active Personnel Dosemeter (APD) provides a digital readout of events caused by neutrons interacting with superheated liquid droplets. The droplets are suspended in a gel held in a replaceable cartridge. Upon neutron interaction, the superheated droplet vaporises, forming a bubble. The sound produced in this process is recorded by transducers that sense the accompanying pressure pulse. The APD electronically discrimates against spurious noise and vibration. Studies with the production prototype APDs indicate that the detector response is linear up to about 0.40 mSv, with large variations sometimes from predicted values and between cartridges at higher dose equivalents. The response to standard neutron sources (bare 252Cf, Pu-Be, Pu-B, Pu-F, Pu-Li) is reported and compared with the expected response. Unirradiated cartridges self-nucleate when heated to temperatures of 46 oC. The APD is insensitive to low energy photons but responds to high energy photons and electrons.
Environmental Alpha and Gamma Survey
Authors: Segovia N. , Gaso M.I. , Chavez A. , Tejera A. , Gutierrez A. , Azorin J. , Balcazar M. , Lopez A. , Tamez E. , Cervantes L. , Monnin M. 
Published: February 2017

Abstract
Radon data in soil and gamma and radon levels in air have been obtained for several years at the site of a Nuclear Research Centre and at a Radioactive Waste Storage Facility. Radon detection was carried out with SSNTD while for gamma levels TLD was used. Cross checking of gamma levels in air using gamma scintillation counting was also performed. The results obtained at the site of the Nuclear Research Centre showed a stability over time in the local average radioactive environment except for seasonal fluctuations essentially due to meteorological parameters which were continuously recorded. Results obtained at the Radioactive Waste Storage Facility indicate average gamma levels in air of 0.2 µGy.h-1 for most of the monitoring stations. One station with a higher radioactivity level was systematically observed. Measurements of radon in air up to 150 cm indicate a rapid dilution in the atmosphere.