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Radiation protection issues of treating hyperthyroidism with 131 I in patients on haemodialysis.

We report on the cases of two patients referred for 131I treatment of hyperthyroidism who were dependent on haemodialysis. Following 131I administration, all disposable lines and filters from dialysis were collected and measured for 131I radioactivity. The amount of 131I retained by the filters at the end of each successive dialysis session was found to decay with effective half-lives of 6.6+/-0.2 and 6.3+/-0.2 days. Dose rate measurements at 1m from the patients were recorded to find the effective half-life of the radioiodine clearance, which were found to be 6.9 and 7.1 days. From measured dose rates taken at 30 cm, the radiation hazard to ward staff involved in patient management was shown to be negligible.

Aged↗

Radiation alarm at an airport after radioiodine therapy.

BACKGROUND: Screening for radioactive material at borders may become more widely introduced in order to prevent illegal transport. All the alarms at Vienna airport so far have been due to recent applications of radionuclides for medical reasons. METHODS: We report a patient who unexpectedly experienced this problem after undergoing radioiodine therapy. RESULTS: We propose to inform patients routinely about this issue and to provide them with a certificate containing details of the administered radionuclide. CONCLUSION: This could reduce problems for authorities, patients and institutions. This problem may not have arisen if the authorities had informed the appropriate groups before starting the security procedure.

Aged↗

Contact lenses and acute exposure to ultraviolet radiation.

The eyes of twenty-three pigmented rabbits (weight approximately 2kg) were irradiated with a single dose of UVB (285 to 315 nm total bandpass at approximately 450 muW.cm-2 irradiance) for exposure times of 22s to 1680s. One group wore UV-transmitting soft contact lenses during exposure of one eye with the fellow eye serving as a control while another group wore a UV-absorbing lens on each eye with only one eye irradiated. UV-transmitting contact lenses did not affect the clinical response to UV exposure whereas the UV-absorbing contact lenses protected the corneas as could have been predicted by consideration of the absorption characteristics of the lenses at the experimental waveband. In no case was there any evidence of adhesion between the contact lens and the corneal epithelium.

Animals↗

Radiation hazards in scoliosis management.

Safe radiography in scoliosis management is based on a sound knowledge of 1) the radiographic imaging process, 2) the degree of risk to the patient from radiation exposure, and 3) the radiographic requirements to both evaluate and follow patients with spine deformity. This paper is a current review of the subject and work done at the authors' centers. It includes recommendations for reducing the radiation risk while maintaining necessary diagnostic information.

Child↗

Anomalously high levels of uranium and other naturally occurring radionuclides in private wells in the piedmont region of South Carolina.

Anomalously high levels of uranium and 210Pb have been detected in untreated domestic groundwater wells near Simpsonville/Fountain Inn, South Carolina. Nine wells were sampled from the affected area and analyzed for total uranium, 234, 235, 238U, 226, 228Ra, 222Rn, and 210Pb as well other water quality parameters. These data augment other uranium concentration measurements and limited 226, 228Ra and 222Rn concentration measurements collected on private and public wells by the South Carolina Department of Health and Environmental Control. The observed radionuclide data were compared to maximum levels published in several national surveys from the past 30 years. The total uranium concentration in the groundwater ranged from 44.3 to 5,570 microg L(-1), with one well having the second highest published concentration in the U.S. The U/U activity ratio ranged from 1.1 to 2.5. 226Ra concentrations ranged from less than the minimum detectable concentration (< MDC) to 1,154 mBq L(-1) while the 228Ra concentration ranged from < MDC to 532.8 mBq L(-1) and the 222Rn levels ranged from 62 to 1,510 Bq L(-1). The 210Pb concentrations ranged from < MDC to 844 mBq L(-1).

Background Radiation↗

Naturally occurring radionuclides in community water supplies of New York state.

During a 2-y study, drinking-water samples were analyzed for gross-alpha and gross-beta activity in 1,869 community water supplies in New York State. Among these, 87 and 14 samples were further analyzed for radium and uranium activity, respectively. The results showed that concentrations in drinking water samples met regulatory limits for gross-alpha, gross-beta, and combined radium in over 99% of the community water supplies tested. Gross-alpha activity in 97% of the supplies was below half of the maximum contaminant level. In the water samples that exceeded the maximum contaminant level, a significant part of the gross-alpha activity was contributed by dissolved uranium. In the 14 supplies that contained >556 mBq L(-1) (15 pCi L(-1)) of gross-alpha activity, the mean uranium concentrations were 548 mBq L(-1) and ranged from 36 to 2,135 mBq L(-1). In the 87 supplies that contained >185 mBq L(-1) of gross-alpha activity, the mean 226Ra and 228Ra concentrations were each 52 mBq L(-1). Based on the mean concentrations in the measured water supplies, the radioactive dose due to ingestion of 226Ra, 228Ra, and uranium is about 27 microSv y(-1), respectively, with 228Ra alone producing half of the dose.

Background Radiation↗

The possible contribution of 129I in the drinking water and food supply to the nodular formation of thyroid tissue.

Nodular formation of the thyroid tissue can occur as a result of exposure to radiation. The nodular goiter is a common disease seen in the city of Elazig and its surroundings, in the eastern part of Turkey. A prospective study was conducted in an effort to identify the role of 129I in drinking water supply. Specimens obtained from nodular and normal thyroid tissue during surgery and also water specimens were counted by nuclear spectrometric system. 129I radioactivity in nodular tissue was noted to be higher compared to normal tissue and the difference was statistically significant (p <0.05). There was no statistically significant difference (p >0.05) between 129I radioactivity in the water supply and tissue obtained from the patients who have malignant or benign nodular lesions. These results support that the 129I radioactivity level in the water supply is one of the risk factors of the nodular formation of the thyroid tissue in the eastern part of Turkey.

Adult↗

Derived release limits for the greek research reactor site based on a diagnostic atmospheric modeling system for irregular terrain.

The upper limits for the rate of release of radionuclides into the atmosphere, i.e., the "derived release limits," are calculated for the Greek Research Reactor (GRR-1) in order to determine possible operational schemes compatible with the effective dose limits for the general population. GRR-1 is located at the northwestern foot of Hymettos Mountain and at the eastern border of the urbanized area of Athens basin. Due to the topographic complexity of the region, the meteorological and atmospheric dispersion calculations were based on a numerical modeling system that is especially designed to work over irregular terrains by using a prismatic unstructured grid. The calculation of derived release limits was made using guidelines and methods that conform to the system of dose limits prescribed by the European radiation protection regulations.

Air Pollutants, Radioactive↗

Radiation effectiveness factors for use in calculating probability of causation of radiogenic cancers.

This paper presents so-called radiation effectiveness factors that are intended to represent the biological effectiveness of different radiation types, relative to high-energy Co gamma rays, for the purpose of estimating cancer risks and probability of causation of radiogenic cancers in identified individuals. Radiation effectiveness factors are expressed as subjective probability distributions to represent uncertainty that arises from uncertainties in estimates of relative biological effectiveness obtained from radiobiological studies of stochastic endpoints, limited data on biological effectiveness obtained from human epidemiological studies, and other judgments involved in evaluating the applicability of available information to induction of cancers in humans. Primarily on the basis of reviews and evaluations of available data by experts, probability distributions of radiation effectiveness factors are developed for the following radiation types: neutrons of energy less than 10 keV, 10-100 keV, 0.1-2 MeV (including fission neutrons), 2-20 MeV, and greater than 20 MeV; alpha particles of any energy emitted by radionuclides; photons of energy 30-250 keV and less than 30 keV; and electrons of energy less than 15 keV. Photons of energy greater than 250 keV and electrons of energy greater than 15 keV are assumed to have the same biological effectiveness as reference Co gamma rays and are assigned a radiation effectiveness factor of unity, without uncertainty. For neutrons and alpha particles, separate probability distributions of radiation effectiveness factors are developed for solid tumors and leukemias, and small corrections to represent an inverse dose-rate effect are applied to those distributions in cases of chronic exposure. A radiation effectiveness factor different from unity for 15-60 keV electrons is discussed but is not adopted due to a lack of relevant radiobiological data. Radiation effectiveness factors presented in this paper are incorporated in the Interactive RadioEpidemiological Program and were developed for use by The National Institute for Occupational Safety and Health and U.S. Department of Labor in evaluating claims for compensation for radiogenic cancers by workers at U.S. Department of Energy facilities.

Algorithms↗

Deterministic vs. probabilistic analyses to identify sensitive parameters in dose assessment using RESRAD.

The dose assessments for sites containing residual radioactivity usually involve the use of computer models that employ input parameters describing the physical conditions of the contaminated and surrounding media and the living and consumption patterns of the receptors in analyzing potential doses to the receptors. The precision of the dose results depends on the precision of the input parameter values. The identification of sensitive parameters that have great influence on the dose results would help set priorities in research and information gathering for parameter values so that a more precise dose assessment can be conducted. Two methods of identifying site-specific sensitive parameters, deterministic and probabilistic, were compared by applying them to the RESRAD computer code for analyzing radiation exposure for a residential farmer scenario. The deterministic method has difficulty in evaluating the effect of simultaneous changes in a large number of input parameters on the model output results. The probabilistic method easily identified the most sensitive parameters, but the sensitivity measure of other parameters was obscured. The choice of sensitivity analysis method would depend on the availability of site-specific data. Generally speaking, the deterministic method would identify the same set of sensitive parameters as the probabilistic method when 1) the baseline values used in the deterministic method were selected near the mean or median value of each parameter and 2) the selected range of parameter values used in the deterministic method was wide enough to cover the 5th to 95th percentile values from the distribution of that parameter.

Agriculture↗

Health physics challenges involved with opening a "seventeen-inch" concrete waste vault.

This paper describes the various activities involved with opening a sealed legacy "Seventeen-inch" concrete vault and the health physics challenges and solutions employed. As part of a legacy waste stream that was removed from the former Hazardous Waste Management Facility at Brookhaven National Laboratory, the "Seventeen-inch" concrete vault labeled 1-95 was moved to the new Waste Management Facility for ultimate disposal. Because the vault contained 239Pu foils with a total activity in excess of the transuranic waste limits, the foils needed to be removed and repackaged for disposal. Conventional diamond wire saws could not be used because of facility constraints, so this project relied mainly on manual techniques. The planning and engineering controls put in place enabled personnel to open the vault and remove the waste while keeping dose as low as reasonably achievable.

Decontamination↗

High level waste tank closure project: ALARA applications at the Idaho National Engineering and Environmental Laboratory.

Bechtel BWXT Idaho, Maintenance and Operating Contractor for the Department of Energy at the Idaho National Engineering and Environmental Laboratory, has emptied, cleaned, and sampled six of the eleven 1.135 x 10(6) L high level waste underground storage tanks at the Idaho Nuclear Technology and Engineering Center, well ahead of the State of Idaho Consent Order cleaning schedule. Cleaning of a seventh tank is expected to be complete by the end of calendar year 2004. The tanks, with associated vaults, valve boxes, and distribution systems, are being closed to meet Resource Conservation and Recovery Act regulations and Department of Energy orders. The use of remotely operated equipment placed in the tanks through existing tank riser access points, sampling methods and application of as-low-as-reasonably-achievable (ALARA) principles have proven effective in keeping personnel dose low during equipment removal, tank, vault, and valve box cleaning, and sampling activities, currently at 0.03 Sv.

Decontamination↗

Medical radiography at sea.

The medical use of x-rays on cruise ships presents some interesting challenges to those used to radiation protection on land. However, the same radiation protection principles apply in both situations. The protection of staff and public apply wherever x-ray machines are used. Whether medical staff, patients, other crew or passengers, all need to be considered with respect to restriction of exposure. An important part of patient dose restriction is dose assessment. A procedure for doing this is presented in this article. The physical assessment of an x-ray facility has two aspects: assessment of shielding afforded by the room structure and assessment of the x-ray equipment itself. Assessment of ancillary equipment is also appropriate; for example, the film processor can have a direct impact on doses to patients. Badly processed films might necessitate repeat exposures. Underdeveloped films might also mislead operators into suspecting that the film is underexposed--the apparent solution is an increase in output causing an unacceptable increase in patient dose. This article also discusses some aspects of the design and assessment of x-ray facilities and the adaptations necessary to achieve a reasonable level of protection in an unusual environment.

Equipment Failure Analysis↗

Sensitivity analyses of the standards for the proposed Yucca Mountain repository--a review, evaluation, and commentary.

The standards and regulations for the proposed Yucca Mountain high level radioactive waste repository, which were developed and promulgated by the U.S. Environmental Protection Agency and the U.S. Nuclear Regulatory Commission, respectively, are complex and challenging. A major reason is that they are divided into three parts, an Individual Protection Standard, a Human Intrusion Standard, and multiple Ground Water Protection Standards. Because the individual parts are not fully integrated, the one that controls under a specific set of circumstances depends on the radionuclide being evaluated, its mechanisms of transport, its avenues of intake, and differences in the specified limits. Although the coefficients in Federal Guidance Report (FGR) No. 11 are being used to estimate the doses, other sources (for example, Title 10, CFR, Part 20, and/or FGR No. 13) may deserve consideration. Since the regulations specify that the reasonably maximally exposed individual is an adult, this leaves unanswered the estimated doses to other age groups, such as infants and adolescents. Summarized in this paper are comparisons of the dose coefficients for different age groups, as well as evaluations of the sensitivity of effective and organ dose estimates for adults, depending on the source of the coefficients. All the latter analyses were based only on the consumption of ground water. While the dose estimates are different, depending on the sources of the coefficients, this was not unexpected. What these evaluations demonstrate is the caution that must be exercised to ensure that a full range of considerations is taken into account in interpreting the outcome of the dose assessments being made with respect to the proposed repository.

Body Burden↗

An analysis of differences in the low-frequency electric and magnetic field exposure standards of ices and ICNIRP.

Technical factors accounting for differences in low-frequency (0-3 kHz) standards of IEEE C95.6 and ICNIRP are identified. These factors are related to thresholds of adverse reactions, safety factors, probability factors, thresholds for different tissue types, magnetic induction models, and induced current and spark discharges with E-field exposure. This paper summarizes technical factors accounting for differences between the two standards and recommends resolution of those factors.

Electromagnetic Fields↗