Method to reduce the volatility of radioactive iodine waste.
Explore the source record for details and available documents.
SEARCH · PubMed Health
Explore indexed PubMed citations for clinical trials, systematic reviews and public health research. Read source abstracts and follow each citation to its original PubMed record.
Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.
Explore the source record for details and available documents.
Worker dose estimates have been made for various exposure scenarios resulting from the relocation of soil from the H Area Retention Basin to the Old Radioactive Waste Burial Ground at the Savannah River Site. Estimates were performed by hand calculations and using RESRAD and MAXDOSE-SR. Doses were estimated for the following pathways: (1) shine and inhalation as a result of standing on contaminated soil at the H Area Retention Basin and the Old Radioactive Waste Burial Ground; (2) exposure to off-unit receptors due to soil disturbances from excavation type activities at the H Area Retention Basin and the Old Radioactive Waste Burial Ground; (3) exposure to off-unit receptors due to soil disturbances from dumping of soil from bucket and from roll-off pan; and (4) exposure to off-unit receptors from wind driven dust from contaminated area. The highest dose estimates (0.25 mSv h(-1)) resulted from the receptor standing on the H Area Retention Basin.
Large quantities of radioactive wastes have been dumped in the Far Eastern Seas by the former Soviet Union and the Russian Federation, and small amounts of radioactive wastes have been dumped by Japan and the Republic of Korea. In order to investigate the concentrations of anthropogenic radionuclides in the nine dumping areas, a second expedition was conducted in 1995 by Japan, the Republic of Korea, the Russian Federation and IAEA, following the first expedition in 1994. The results show that 137Cs, 90Sr and 239 + 240Pu concentrations in surface and bottom waters at dumping areas do not significantly differ from the values observed in background areas, and from historical values. There is no clear effect of possible contamination due to radioactive waste dumping. The concentrations and water column inventories of 137Cs, 90Sr and 239 + 240Pu in the Far Eastern seas are controlled by physical oceanic processes such as horizontal transport and biogeochemical processes such as scavenging.
Explore the source record for details and available documents.
The properties of (79)Se make it of likely potential importance in safety studies for geological disposal of radioactive wastes. Despite a substantial literature on toxic and nutritional aspects of selenium in the environment little consideration has been given to the behaviour of radioactive selenium and its potential transfer from a radioactive waste repository to the biosphere. Column experiments (15 x 50 cm), using a sandy loam soil, indicated that the upwards migration of (75)Se (as a surrogate for (79)Se) from a contaminated water table was dependent upon the redox status of the soil. Low redox conditions within the water table strongly limited upwards (75)Se soil migration, presumably due to the immobilisation of reduced Se species. Under natural conditions, (79)Se from a radioactive waste repository is therefore likely to accumulate at considerable depth. As a consequence, its absence from the rooting zone is likely to limit its transfer into plants. Nevertheless, the column experiments indicated that when an overlap between roots and soil contamination occurs, uptake into the plant is observed. Quantification of (75)Se volatilisation from the column surfaces suggested that this is a significant pathway by which (79)Se may move either directly from soil to the atmosphere, or from soil to plants and then to the atmosphere.
A 3-yr study of radioactive materials transportation examined the magnitude of radioactive materials shipments in terms of numbers of packages and motor vehicle trips and types of materials; compliance with regulations for packaging, labelling, handling, external radiation exposure, and surface contamination; and dose to workers as measured with personnel dosimeters. Much of the information was obtained at the Atlanta airport and its vicinity, a package distribution center for the southeastern U.S., and at the Barnwell, S.C. radioactive waste burial site, the destination of most shipments of radioactive waste from or through Georgia. Approximately 12,000 packages in radioactive material categories I, II and III were handled in Georgia each year. Motor vehicles made approximately 3300 trips per year. Some instances of noncompliance were observed, but few of them had the potential for elevated radiation exposure of persons. Several incidents associated with radioactive material transport are reported, of which one may have resulted in slightly elevated exposures to persons. Among drivers and handlers who worked with radioactive material shipments, dosimeters showed that less than one-half of them received radiation doses above background levels. The highest doses were found for drivers who transported large numbers of 99Mo generators.
Explore the source record for details and available documents.
Explore the source record for details and available documents.
Explore the source record for details and available documents.
Explore the source record for details and available documents.
In their regulations, the U.S. Environmental Protection Agency and the U.S. Nuclear Regulatory Commission permit the omission of features, events, or processes with probabilities of <10(-4) in 10(4) yr (e.g., a constant frequency of <10(-8) per yr) in assessments of the performance of radioactive waste disposal systems. Igneous intrusion (or "volcanism") of a geologic repository at Yucca Mountain for radioactive waste is one disruptive event that has a probability with a range of uncertainty that straddles this regulatory criterion and is considered directly in performance assessment calculations. A self-sustained nuclear chain reaction (or "criticality") is another potentially disruptive event to consider, although it was never found to be important when evaluating the efficacy of radioactive waste disposal since the early 1970s. The thesis of this article is that the consideration of the joint event--volcanism and criticality--occurring in any 10,000-year period following closure can be eliminated from performance calculations at Yucca Mountain. The probability of the joint event must be less than the fairly well-accepted but low probability of volcanism. Furthermore, volcanism does not "remove" or "fail" existing hydrologic or geochemical constraints at Yucca Mountain that tend to prevent concentration of fissile material. Prior to general corrosion failure of waste packages, the mean release of fissile mass caused by a low-probability, igneous intrusive event is so small that the probability of a critical event is remote, even for highly enriched spent nuclear fuel owned by the U.S. Department of Energy. After widespread failure of packages occurs, the probability of the joint event is less than the probability of criticality because of the very small influence of volcanism on the mean fissile mass release. Hence, volcanism plays an insignificant role in inducing criticality over any 10(4)-yr period. We also argue that the Oklo reactors serve as a natural analogue and provide a rough bound on probability of criticality given favorable hydrologic or geochemical conditions on the scale of the repository that is less than 0.10. Because the product of this bound with the probability of volcanism represents the probability of the joint event and the product is less than 10(-4) in 10(4) yr, consideration of the joint event can be eliminated from performance calculations.
Many publications attest to the potential of the sentinel lymph node technique in advancing the clinical management of melanoma and, more recently, breast cancer. Whilst not yet universally regarded as the standard of care, the technique is gaining wide acceptance. Use of a radiolabelled colloidal tracer is central to optimising sensitivity, and this brings with it the need to address radiation safety issues relating to the use of radioactive materials in the operating theatre and pathology laboratory, and the generation of radioactive waste. The radiation dose to the patient should also be determined if the professional is to reassure the patient by placing this in its proper context. For the purpose of this investigation, biodistribution data were obtained from patient studies to quantify the migration of tracer beyond the injection site, thereby permitting a detailed assessment of the internal dosimetry of the tracer and the resulting radiation dose to the patient. Uptake of tracer in the sentinel nodes, reticulo-endothelial system and circulating blood was investigated. The radiation dose to surgical staff was recorded using whole-body monitors and extremity dosimeters worn at the fingers. Clinical waste in the operating theatre was monitored and the radioactive content of significantly contaminated items determined. The radiation dose to pathology staff was estimated from knowledge of the radioactive content of the specimens obtained and a study of work practices. Migration of tracer was found to be minimal, with greater than 95% retention at the injection site. The effective dose resulting to the patient was 2.1x10(-2) mSv/MBq, with a mean breast dose of 7.2x10(-1) mGy/MBq. A mean whole-body dose of 0.34 microSv was received by surgical staff per procedure, with a mean finger dose of 0.09 mSv (90 microSv). Radiation doses received by pathology staff will be predominantly below measurable levels and are likely to be negligible unless primary specimens from a large number of studies are analysed promptly upon their excision. At operation, surgical swabs can become significantly contaminated and have been found to contain up to 22% of the administered activity, dependent upon the surgical procedure performed. It is concluded that moderate activities of technetium-99m labelled tracer are administered to the patient, and the radiation risk to the patient is consequently low relative to that from many other medical exposures. The radiation doses to staff groups involved in all aspects of the technique are low, and under normal circumstances and levels of workload, routine radiation monitoring will not be required. Standard biohazard precautions prevent direct intake of radioactive contamination. Radioactive waste is created in the operating theatre, and may be generated in the pathology laboratory if specimens are not routinely stored until fully decayed. This will require special handling if the disposal of radioactive material is not permitted.
Like radioactive waste, municipal solid waste (MSW) requires consideration of a complex mix of intergenerational and intragenerational risks surrounded by uncertain science. Unlike radioactive waste, MSW is a common problem and hence one often perceived to be controllable, at least until a required facility is proposed in a particular community. The intragenerational risks focused on local communities rouse intense public pressures for management. Although some of the risks can be quantified, the risk assessment process cannot deal with all questions. This article examines the multiple dimensions of the decisions required to be made and the weaknesses of a number of decision tools traditionally used. A case is made for the need to integrate decision tools appropriate to the risks into reflexive and iterative decision processes open to public involvement. It is argued that this presents the best hope of both optimizing decisions about the intragenerational risks as well as raising public debate about the importance of sustainable waste management in transgenerational terms.
Explore the source record for details and available documents.
The primary objective of a low-level radioactive waste disposal facility is to isolate low-level radioactive waste from the public and the environment until the radionuclides in the waste have decayed to levels at which the hazard is negligible. Two fundamental concerns must be addressed when attempting to isolate low-level waste in a disposal facility on land. The first concern is isolating the waste from water, or hydrologic isolation. The second is preventing movement of the radionuclides out of the disposal facility, or radionuclide migration. Particularly, we have investigated here the latter scenario. Empirical curves describing the progression of the altered zone are obtained and they are used to define the correspondent altered thickness in the numerical calculations for a cement sample. Subsequent numerical analyses of diffusion of activated sources in waste disposals are considered for cemented containers. The adopted DAMAGE code takes into account a mass conservation equation and the linear momentum balance equation for the multiphase material. The mathematical model is based on the theory developed by Bazant for concretes and geomaterials; the fluid phases are considered as a unique mixture interacting with a solid phase. Short- and long-term diffusion analyses are performed for different characteristics of the grout and the results are presented in terms of radionuclides concentration. Indications on the minimum grout thicknesses able to resist to radioactive fluxes up to 1000 years are given.
Explore the source record for details and available documents.
Explore the source record for details and available documents.
This article discusses the most important information on health effects in the Urals region (Russia) of residents exposed to radiation from activities of a weapon plutonium separation plant. The population residing on the contaminated territory was exposed to chronic combined irradiation (external gamma-irradiation and internal irradiation due to Sr-90 and Cs-137). The red bone marrow (RBM) was the critical organ affected as a result of radiation events in the Urals. In the early period, after the discharges of radioactive wastes into the river Techa (about 3 M Ci) started, cases of chronic radiation sickness (CRS; 940 cases, in total), postirradiation reactions manifested by changes in blood parameters (e.g., leukopenia, thrombocytopenia, granulocytopenia), nervous system disorders, immunity changes and ostealgic syndrome were registered in a portion of those riverside village residents who had received the highest doses. Increased leukemia and cancer mortality and morbidity rates were noted among this population in later periods. No late effects were observed in residents exposed to an explosion in a radioactive waste depot in September, 1957 when radioactive wastes with about 20 M Ci of activity were released into the environment. Similarly, the offspring of the residents exposed on the Techa also did not display any late effects. The data about the possibilities of long-term (43-45 years after the start of exposure) biological indication of chronic internal exposure are presented. The methods used in the study include in situ fluorescent hybridization, analysis of mutations in the TCR gene of peripheral blood lymphocytes and erythrocyte mutations in the glycophorine A system. No dependence of genomic translocations and mutations in glycophorine A on cumulative exposure dose to RBM was traced.