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Electrets to measure ion concentration in air.

Positive and negative ions are produced in air, mainly due to radon and terrestrial/cosmic radiation sources. Measuring ion concentration in air indirectly provides a measure of these sources. Electrets (electrically charged pieces of Teflon), when exposed in the environment, collect ions of opposite sign leading to a measurable decrease in charge, depending upon the exposure time and ion concentration. This work describes a method of correlating electret discharge rate to the ion concentration as measured by a calibrated ion density meter. Once calibrated, electrets can then be used to measure ion concentration of either sign. The ion concentration in ambient air was measured to be about 200 ions mL(-1), measured over several hours. Both positive and negative ion concentrations were similar. In a typical room, negative ion concentration was about 3,500 ions mL(-1), and, surprisingly, there were no positive ions at all in that room. Being an integrating passive device, the method provides the unique possibility of measuring low or high concentrations of positive or negative ions over extended periods, which is difficult to do with other ion concentration measuring instruments.

Air Pollutants, Radioactive↗

Impacts of stable element intake on 14C and 129I dose estimates.

The purpose of this study was to evaluate and provide insights related to the influence of the intake of stable isotopes of carbon and iodine on the committed doses due to the ingestion of (14)C and (129)I. This was accomplished through the application of two different computational approaches. The first was based on the assumption that ground (drinking) water was the only source of intake of (14)C and (129)I, as well as stable carbon and stable iodine. In the second, the intake of (14)C and (129)I was still assumed to be restricted to that in the ground (drinking) water, but the intake of stable carbon and stable iodine was expanded to include that in other components of the diet. The doses were estimated using either a conversion formula or the applicable dose coefficients in Federal Guidance Reports No. 11 and No. 13. Serving as input for the analyses was the estimated maximum concentrations of (14)C or (129)I that would be present in the ground water due to potential releases from the proposed Yucca Mountain high-level radioactive waste repository during the first 10,000 y after closure. The estimated contributions of stable carbon and iodine through the consumption of ground water were based on analyses of samples collected in the Amargosa Valley, NV. The contributions through dietary intake were based on surveys conducted in the United States. Based on the accompanying analyses, it was noted that stable isotope intake has a significant effect on the estimated doses due to the intake of radioactive isotopes of the same element. While this is a well-known fact, this observation has international implications in terms of dose estimates for key radionuclides, such as (14)C and (129)I, a primary reason being the wide variations in the intakes of stable carbon and iodine in various countries. For this reason, analysts planning to apply the dose coefficients developed by the International Commission on Radiological Protection (ICRP) should either confirm that the average total intake in their country of stable isotope(s) of the radioactive isotope being evaluated is in reasonable agreement with the value assumed by the ICRP or suitably modify the ICRP dose coefficients to account for any differences. If such a procedure is to be implemented, there is a need for periodic updates of the dietary intakes of various stable elements in countries throughout the world. The importance of this is documented by recent surveys in Asia that revealed that their average total daily intake of stable iodine was less than half of the ICRP value for Reference Man. In this case, application of the ICRP dose coefficients, without modification, would underestimate the dose due to ingested (129)I by a factor of more than two. A related situation exists in the United States where the latest surveys indicate that the daily intake of stable iodine is 75% of the ICRP value.

Administration, Oral↗

Re-evaluation of the ultraviolet hazard action spectrum--the impact of spectral bandwidth.

The action spectra S(lambda) used for risk assessment of ultraviolet (UV) sources has been widely used since its development over three decades ago. This "UV hazard function" is cited in many safety standards, and UV survey instruments are designed to have a fitting spectral response. The UV hazard function was developed to preclude acute injury and minimize chronic effects but was based upon the best available experimental data of that time. With more experimental data and easier computer methods available today, the action spectrum can be re-examined. Therefore, the published experimental thresholds for damage to the cornea and skin were studied as a function of wavelength to revalidate this action spectrum. A key step relates to the proper consideration of the spectral bandwidth used to determine each threshold and the assignment of an effective wavelength for each narrow-band. We methodically analyzed the uncertainties introduced by employing 1-, 5-, and 10-nm spectral bandwidths by comparing published biological threshold data. The errors introduced by using broader bandwidths become enormous within the critical spectral region of 300-320 nm. By convoluting the threshold data and weighting them with trial, or reference, action spectra, it is possible to determine the wavelengths in each bandwidth that are contributing most of the effective dose and correct the experimental action spectrum. It is concluded that the current hazard function S(lambda) remains valid.

Animals↗

First responders and nuclear terrorist attacks.

Avoidance of downwind radioactive fallout exposure within the first few hours after a nuclear or radiological dispersal device detonation can save lives and minimize radiation exposure. First responders with awareness training can help to avoid prompt fatalities and excessive contamination or exposure following such a detonation. This paper outlines some of the critical components of the situational awareness and actions necessary to save lives and minimize radiation contamination and exposure.

Disaster Planning↗

Radiation doses in the surroundings of patients undergoing nuclear medicine diagnostic studies.

Dose rate measurements were performed at 0, 0.5, and 1 m from the external surface of 79 patients corresponding to the most frequent studies: 99mTc-cardiac with reinjection, 99mTc-cardiac single injection, 99mTc-bone scan, 99mTc-lung studies, and cardiac studies using 201Tl. Doses to staff, nearby patients, and the collective effective doses were estimated for the different working shifts and hospital areas. The estimated dose for nurses for 1 y was 518 microSv in the cardiology section and 338 microSv in the short stay section. For patients, the mean dose per stay was calculated to be 8.5 microSv in the cardiology section. The maximum dose that a patient could receive from a radioactive patient is 499 microSv for a double injection cardiac patient study. The maximum collective effective dose for the whole hospital was calculated to be 0.063 person-Sv. The probability of staff receiving doses higher than the limits for a working day is negligible. Maximum doses for staff and patients are far below dose limits for the public and therefore no additional radiological protection is needed.

Hospital Bed Capacity, 500 and over↗

Effective dose scaling factors for use with cascade impactor sampling data in tenorm inhalation exposures.

When assessing the effective dose to workers following radio-aerosol inhalation exposures, significant reductions in dose uncertainty can be achieved through direct measurement of the particle-size distribution. The University of Washington Mark III cascade impactor is one such air sampling device that permits the user to determine aerosol mass and radioactivity concentrations as a function of particle size within eight different size intervals (each corresponding to a different impactor stage or end filter). Traditionally, dose assessments made using the LUDEP code or other internal dosimetry software utilize this air sampling information by assigning the radioactivity measured at each stage as concentrated at a single representative size central to the size interval. In this study, we explore more realistic assumptions that the measured radioactivity distributes uniformly, linearly increases, or linearly decreases across the particle size interval for each impactor stage. The concept of an effective dose scaling factor, SF(E), is thus introduced whereby (1) the former approach can be used (which requires less computational effort using the LUDEP code), and (2) the resulting values of effective dose per stage can then be rescaled to values appropriate to a linear radioactivity distribution per stage. For a majority of (238)U-series radionuclides, particle size ranges, and absorption classes, differences in these two approaches are less than 10%, and thus no corrections in effective dose per particle stage are needed. Significant corrections, however, were noted in select cases. For uniform or linearly decreasing radioactivity distributions, end-filter particles (0.03 to 0.35 microm) of type F, M, or S radionuclides were assigned values of SF(E) ranging from 1.15 to 1.44, while 3(rd) stage particles (4.5 to 12 microm) of type M and S radionuclides were assigned values of SF(E) ranging from 1.11 to 1.53. When the cascade impactor measurements indicate a linear increase of activity across a given impactor-stage size range, values of SF(E) range from a high of 1.11 (6(th) stage particles of type F radionuclides) to lows of 0.85 to 0.91 (4(th) stage and end-filter particles of type M and S radionuclides). In these cases, the inhalation dose coefficient varies non-linearly across the particle size range, and the assumption of a mono-size distribution per impactor stage either underestimates (SF(E) > 1) or overestimates (SF(E) < 1) that stage's contribution to the worker effective dose.

Aerosols↗

Understanding the toxicity of buried radioactive waste and its impacts.

The oral ingestion toxicities of buried high level radioactive waste from nuclear power plants and of the natural radioactivity in the ground are calculated and expressed as cancer doses, the number of fatal cancers predicted by the linear no-threshold theory if all of the material were fed to people. Unless the size of the U.S. nuclear power industry is greatly expanded, there will probably never be more than 2 trillion cancer doses (CD) in U.S. repositories, as compared with 31 trillion CD in the ground above them. Measurements of the uranium, thorium, and radium in human bodies indicate that the latter cause 500 deaths per year in U.S. The great majority of this material is derived from the top few meters of soil that are penetrated by plant roots. It is concluded that the annual number of U.S. deaths from buried nuclear wastes will be about 1.0 (or less), orders of magnitude less than the number from coal burning electricity generation, the principal competitor of nuclear power.

Algorithms↗

Final results of the Austrian Radon Project.

The Austrian Radon Project started in 1992 and ended in 2001. The Austrian Radon Project had two aims: firstly, finding areas of enhanced indoor radon concentration for future radon mitigations, and, secondly, defining areas with elevated radon risk where radon safe construction is necessary for new houses. The project was based on systematic indoor measurements in randomly selected houses using different types of detectors. Successful intercomparison tests were made in a radon chamber, but simultaneous measurements by different detectors normally used in homes deviated sometimes up to a factor of two. We have to assume that this results from manipulations of the detectors by the inhabitants. The mean radon concentration in Austrian homes was found to be 99 Bq m(-3). A radon potential was derived from the results of the measurements and the information received from questionnaires. This radon potential was defined as an expected radon concentration in a standard situation and characterizes the radon risk from ground sources with all the influences of different living situations eliminated. A mean radon potential was computed for every municipality and the information is displayed as a map. The uncertainty and the reliability of the classification of municipalities according to the radon potential are discussed in more detail and compared with results from Switzerland.

Air Pollutants, Radioactive↗

Warren K. Sinclair Keynote Address: Current challenges in countering radiological terrorism.

Terrorism, although perhaps known by other names, is not a new phenomenon. It dates back to Roman times and perhaps even further in world history. Caleb Carr says terrorism "is simply the contemporary name given to, and the modern permutation of, warfare deliberately waged against civilians with the purpose of destroying their will to support either their leaders or policies... " In modern times, in the United States, there have been isolated violent acts of citizens against each other, although these acts often were directed toward symbols of the federal government. In the Middle East and other parts of the world, acts of violence against U.S. citizens and military personnel date back into the early 1960's. Some of these acts seem to be almost random in nature. But these events occurred in distant lands of sometimes uncertain locations to the American public, who soon forgot them and their important message. Even though there had been at least one other attempt on the World Trade Center, it was not until 11 September 2001 that successful, large-scale acts of terrorism came to our shores. In 1998, the National Council on Radiation Protection and Measurements (NCRP) formed a Scientific Committee and charged the committee with the task of providing a report on the state of preparation and the potential use by terrorists of radiation and radioactivity. The draft report of the Committee was produced a year in advance of the events of 11 September 2001 and was published in its final form about a month after these terrible events. The report brought together, in one place, information that existed in a number of areas, not all of which were easily accessible. However, there were a number of gaps in the information and in the planning and preparation for such events. These were reflected in a series of recommendations for organization, planning, and training, as well as for research and development in a number of areas. This brief presentation will address a few selected areas that remain a challenge for those preparing for terrorist events involving radioactive materials. More detailed discussions will be provided by the presentations at this NCRP Annual Meeting.

Disaster Planning↗

Hospital management of mass radiological casualties: reassessing exposures from contaminated victims of an exploded radiological dispersal device.

One of the key issues in the aftermath of an exploded radiological dispersal device from a terrorist event is that of the contaminated victim and the concern among healthcare providers for the harmful exposures they may receive in treating patients, especially if the patient has not been thoroughly decontaminated. This is critically important in the event of mass casualties from a nuclear or radiological incident because of the essential rapidity of acute medical decisions and that those who have life- or limb-threatening injuries may have treatment unduly delayed by a decontamination process that may be unnecessary for protecting the health and safety of the patient or the healthcare provider. To estimate potential contamination of those exposed in a radiological dispersal device event, results were used from explosive aerosolization tests of surrogate radionuclides detonated with high explosives at the Sandia National Laboratories. Computer modeling was also used to assess radiation dose rates to surgical personnel treating patients with blast injuries who are contaminated with any of a variety of common radionuclides. It is demonstrated that exceptional but plausible cases may require special precautions by the healthcare provider, even while managing life-threatening injuries of a contaminated victim from a radiological dispersal device event.

Decontamination↗

Advances in radiation detection technologies for responders.

The Department of Homeland Security is supporting the development of a large number of standards for first responders. In the area of detection of radioactive and nuclear materials, four new standards (ANSI N42.32, N42.33, N42.34, and N42.35) and their corresponding test and evaluation protocols were developed to meet Department of Homeland Security needs. Testing of the standards and protocols was carried out at the National Institute of Standards and Technology, Oak Ridge National Laboratory, Pacific Northwest National Laboratory, Los Alamos National Laboratory, and Lawrence Livermore National Laboratory.

Humans↗

Radiation protection aspects of shallow land disposal of low and intermediate level liquid and solid radioactive waste at PINSTECH.

Operation of Pakistan Research Reactors 1 and 2, radioisotope production plants, and allied laboratories at the Pakistan Institute of Nuclear Science & Technology (PINSTECH) generates radioactive waste effluents of low and intermediate level. These waste materials are managed in a way to keep the human health and the environment free of radiation associated hazards. The prime practice has been of shallow ground or near-surface disposal type. Different measures and operational procedures at the institute, in step with the international norms for the management of low and intermediate level waste, have been adopted. To ensure the safe disposal practices and radiation safety of the workers and of the general public, radiological safety related routines are practiced with due concern. Some safety aspects of the prevailing practices are discussed in this presentation.

Humans↗

Radiological threat assessment and the Federal Response Plan--a gap analysis.

The ability of the federal government to effectively and efficiently respond to nuclear or radiological terrorist attacks has been the subject of intense discussion and analysis for many years. Because of recent terrorist activities and intelligence information, there is strong sentiment that it is not a question of if, but when, a radiological or nuclear terrorist attack will occur. As a result, there is considerable concern that the federal government may not be adequately prepared to respond to an attack involving a radiological dispersal device or improvised nuclear device. In response to these concerns, federal departments and agencies have initiated actions to develop a better understanding of the magnitude of the radiological/nuclear terrorist threat, assess the ability of the federal government to support state and local responses to such attacks, and improve the Nation's ability to prepare for, respond to, and recover from these types of attacks. In an era of limited fiscal growth and competing priorities, the federal government will have to enhance its collaboration with state and local governments, the private sector, and academia to ensure that the Nation is capable of responding to a terrorist attack involving radioactive or nuclear material.

Disaster Planning↗

Extended conversion coefficients for use in radiation protection of the embryo and fetus against external neutrons from 10 MeV to 100 GeV.

External neutron exposure is of concern in the environment and in some workplaces. Dose assessments for neutrons frequently rely on fluence-to-absorbed dose conversion coefficients. A problem of concern in radiation protection is exposure of pregnant women to ionizing radiation because of the high radiosensitivity of the embryo and fetus. While neutron fluence-to-dose conversion coefficients for adults are recommended in ICRP publications and ICRU reports, conversion coefficients for embryos and fetuses are not given in the publications. This study uses the Monte Carlo code MCNPX to determine mean absorbed doses to the embryo and fetus when the mother is exposed to neutron fields. A previous study has dealt with neutrons from 1 eV to 10 MeV. In this study, monoenergetic neutrons ranging from 10 MeV to 100 GeV are considered. The irradiation geometries include antero-posterior, postero-anterior, lateral, rotational, and isotropic. At each of these standard irradiation geometries, absorbed doses to the fetal brain and body are calculated for the embryo of 8 wk and the fetus of 3, 6, or 9 mo. Neutron fluence-to-absorbed dose conversion coefficients are derived for the four prenatal ages. The results showed that the fetus at about 3 mo of prenatal age should receive more radiation protection to prevent long-term brain damage. During prenatal life, the fetus generally receives the highest absorbed dose per unit neutron fluence for antero-posterior irradiation. In cases where the irradiation geometry is not specified or not adequately known, conversion coefficients of AP-irradiation can therefore be used in a conservative dose assessment of fetus exposure to external neutrons.

Body Burden↗

Measurement of 129 I and 137 Cs in soils from Belarus and reconstruction of 131I deposition from the Chernobyl accident.

I and Cs have been measured in a large number of soil samples collected throughout the country of Belarus to support efforts for thyroid-dose reconstruction following the Chernobyl accident. Samples of soil consisting of multiple 30-cm-deep cores per site were sampled following a selection process to ensure sites were undisturbed and representative. Samples were measured by accelerator mass spectrometry (AMS) for I, gamma spectrometry for Cs, and gas chromatography (GC) for total iodine. Results show that both I and Cs are retained firmly in the top approximately 15 to 20 cm of the soil. Our results also suggest that the correlation between I and Cs deposition across the country of Belarus is poor; hence, I is a better surrogate for I than is Cs. It was also noted that total iodine concentrations in topsoil from Belarus are low compared with other regions of the world where radiogenic thyroid cancer has been studied.

Cesium Radioisotopes↗

A commentary on some inconsistencies in the icrp 2005 recommendations: exclusion levels.

The International Commission on Radiological Protection (ICRP) 2005 Recommendations, which were released at the International Radiation Protection Association's congress held in Madrid (May 2004), have been available for public comment via the ICRP's Web site. The comment period has now closed and the Recommendations are presumably being re-worked. There are several inconsistencies in the Recommendations and they are exemplified by looking at the exclusion levels in more detail. The relevant text of the Recommendations is included in this paper as an . It is suggested that the International Atomic Energy Agency's approach is more balanced where each nuclide receives its own exclusion level instead of the incomplete and arbitrary categories proposed by the ICRP.

Health Physics↗

A novel technique for the rapid identification of alpha emitters released during a radiological incident.

Before the May 2003 TOPOFF II exercise in Seattle, the U.S. EPA's Laboratory in Las Vegas prepared five spiked samples to be analyzed by the Washington State Department of Health's (WSDOH) Radiation Laboratory. Two of these were simulated deposition samples prepared on packaging tape. Laboratories throughout the world are investigating rapid methods for analyzing plume-borne radioactive materials. While measuring gamma emitters in environmental samples is fairly straightforward, the potential presence of alpha emitters adds complexity. The short range of alpha particles and the high degree of energy interference between nuclides usually require chemical separations and very thin mounts for alpha spectrometry. Work published on Frisch-Grid alpha counting of transuranics in soil and the commercial development of radon-rejection for air filters indicate that alpha spectrometry can be used directly on some media with success. This suggests that plume-borne material sampled from air or freshly deposited surface layers may be counted directly by alpha spectrometry, making it possible to identify both alpha and gamma emitters and determine their relative concentrations. The long-range objective is to propose a sampling method that can be used for rapid qualitative and semi-quantitative analyses using conventional radioanalytical instruments, with minimal preparation. This paper describes experimentation with this approach during a real-time exercise. All samples were prepared by spiking with (137)Cs, (241)Am, (238)Pu, and (239)Pu and presented to the WSDOH's Radiation Laboratory for analysis during TOPOFF II. The laboratory quickly identified and determined the ratios of all four contaminants on the tape samples using sequential alpha spectrometry and gamma-ray spectroscopy without chemical separations.

Air Pollutants, Radioactive↗

A laboratory intercomparison of radon in water measurements in Maine.

Naturally occurring radon exists in ground water and drinking water supplies. Many water testing laboratories provide measurements of radon in water for the public. No known national intercomparison program exists to verify the accuracy of the laboratories measuring radon in water in Maine or the Northeast. In recognition of this situation, the State of Maine Radiation Control Program sanctioned an intercomparison study for laboratories registered in Maine to measure radon in water. The University of Maine supplied each laboratory with water samples of various radon concentrations, served as the reference laboratory, and analyzed the results. Of the nine participating laboratories, eight use the liquid scintillation method while the ninth uses the E-PERM method to measure radon in water. Presented here are the results of this intercomparison study with a tabulation of the materials and methods used by the laboratories. The results from five of the nine testing laboratories showed significant discrepancies with those of the reference laboratory, typically due to low measurements.

Laboratories↗