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Bio-monitoring the genotoxicity of populations of Scots pine in the vicinity of a radioactive waste storage facility.

Results of a long-term (1997-2002) study of the Scots pine populations growing in the vicinity of the radioactive waste storage facility ('Radon' LWPE) are presented. Cytogenetic disturbances in reproductive (seeds) and vegetative (needles) tissues sampled from Scots pine populations were studied to examine whether Scots pine trees have experienced environmental stress in areas with relatively low levels of pollution. The data clearly indicate the presence of mutagenic contaminants in the environment of the pine trees. An increased number of mitotic abnormalities, especially multipolar mitoses was found in the pine tree populations submitted to man-made exposure, which suggests that the cytogenetic damage is mainly caused by chemical contamination. A higher radioresistance of the Scots pine seeds from the impacted populations was shown by use of acute gamma-irradiation. During the observation period 1997-2002, pine trees exposed to anthropogenic pollution showed a steady increase of cytogenetic alterations in the root meristem cells.

Cytogenetics↗

Radioactive waste: the problem of plutonium.

Systems under development for the recovery of plutonium from spent fuel and its recycling in fresh fuel would not significantly reduce either the total alpha-activity or the amount of fissile plutonium in radioactive waste relative to what is possible with once-through fuel cycles.

Animals↗

Computer-assisted management of liquid radioactive waste at the University of California, San Diego.

Commercially available software has been obtained and internal software applications have been developed to implement a tracking system for liquid radioactive wastes. This system utilizes a number of data bases that maintain sampling, waste pickup and disposition information based on various parameters. Computerization has allowed access to summary information and inventory totals that are necessary for radioactive materials license compliance. Comparative reports, which are used to show trends and track historical information, can also be generated.

California↗

Historical relationship between performance assessment for radioactive waste disposal and other types of risk assessment.

This article describes the evolution of the process for assessing the hazards of a geologic disposal system for radioactive waste and, similarly, nuclear power reactors, and the relationship of this process with other assessments of risk, particularly assessments of hazards from manufactured carcinogenic chemicals during use and disposal. This perspective reviews the common history of scientific concepts for risk assessment developed until the 1950s. Computational tools and techniques developed in the late 1950s and early 1960s to analyze the reliability of nuclear weapon delivery systems were adopted in the early 1970s for probabilistic risk assessment of nuclear power reactors, a technology for which behavior was unknown. In turn, these analyses became an important foundation for performance assessment of nuclear waste disposal in the late 1970s. The evaluation of risk to human health and the environment from chemical hazards is built on methods for assessing the dose response of radionuclides in the 1950s. Despite a shared background, however, societal events, often in the form of legislation, have affected the development path for risk assessment for human health, producing dissimilarities between these risk assessments and those for nuclear facilities. An important difference is the regulator's interest in accounting for uncertainty.

Decision Theory↗

Sampling and analyses of colloids at the Drigg low level radioactive waste disposal site.

Water samples have been extracted from inside (from standpipes) and from outside (from boreholes) of the trenches at the low level radioactive waste disposal site at Drigg in Cumbria, UK. The samples were taken anaerobically from between 8.5 and 10.0 m below the surface using a submersible pump at low flow rates to ensure that the waters in the standpipes and boreholes were maintained at constant levels. To ensure representative samples, the Eh, pH. conductivity, temperature, iron and dissolved oxygen concentrations of the waters were taken during initial purging and during sampling. The gross tritium, gross non-tritium beta, gross alpha and gamma activities of each sample were determined using suitable sample preparation and counting techniques. Samples were then anaerobically, sequentially filtered through 12 microm, 1 microm, 30 kDa and 500 Da filter membranes. The filtrates were analysed for gross alpha, gross non-tritium beta and gamma activities. SEM and STEM analyses were used to determine the colloid population. An energy dispersive analyser on the SEM was used to determine the major elements present in the colloids. UV-visible spectrophotometry, fluorescence spectrophotometry and high performance size exclusion liquid chromatography were used to analyse the waters before and after treatment with ion exchange materials to determine whether natural organic matter was present in the waters. Results showed that two major types of colloids (iron containing colloids and silicon containing colloids) were present in the waters. There were also a small number of other colloids that contain, as major elements, aluminium, calcium and chromium. Organic colloids were also present. The majority of the radioactivity in the waters was due to tritium. Waters taken from outside the trenches contained low levels of non-tritium beta activities and alpha activities which were lower than the minimum detectable amount. Waters taken from the trenches contained non-tritium beta activities and low levels of alpha emitters. Filtration of the trench waters showed that some of the alpha activity was retained by the 30 kDa and 500 Da membranes suggesting that this activity was associated with small colloids. Radioactivity was not found to be associated with colloids present in the waters taken from outside the trenches. Possible reasons for this observation could be that radionuclide bearing colloids have not yet reached the far-field or that the radionuclide concentration is diluted to below the minimum detectable amount. After concentrating two of the samples by factors of x20 and x 16 respectively, 2.4+/-0.1 and 0.6+/-0.1 Bq dm(-3) of 137Cs were measured.

Colloids↗

Significance of 14C and 228Ra in terms of the proposed Yucca Mountain high-level radioactive waste repository.

C and Ra are two of the radionuclides that have either been identified as being potentially significant in terms of releases from the proposed Yucca Mountain high-level radioactive waste repository, or are specifically cited for consideration and evaluation in the regulations promulgated by the U.S. Nuclear Regulatory Commission. The purpose of this study was to estimate the concentrations and associated doses for these two radionuclides, if released under conditions of a scenario assumed to apply to a repository containing some of the features of the one proposed at Yucca Mountain, NV, and to compare these estimates to the regulatory limits for that facility. For C, the postulated condition was that an annual fractional release of 10 of its total remaining inventory occurs beginning at 10,000 y after repository closure. For Ra, the same fractional release rate was assumed, but in this case it was presumed to occur when the Ra inventory was projected to reach a maximum at more than 10 y after repository closure. The estimated concentrations and doses were, in turn, compared to the concentration limit, specified in the Ground Water Protection Standards (GWPSs) in the case of Ra, or derived, in the case of C, on the basis of the regulatory dose rate limit. Due to the small inventory of C in the waste, and its short half-life relative to the performance period evaluated, its estimated concentration in the ground water would be slightly more than 4% of the derived GWPS. Due to the relatively small initial inventory of Th, the precursor of Ra, and the correspondingly small quantities of higher atomic number actinides that could, through decay, produce additional quantities of Th, its estimated concentration in the ground water would be less than 3% of the GWPS, leaving the remaining portion of the limit for potential contributions from Ra. At the same time, however, it must be recognized that, in this case, the regulations require that any contributions of naturally occurring Ra and Ra already present in the ground water must be included in the determination of compliance. If this is done, the total concentration of Ra, combined with the naturally occurring concentration of Ra, would be about 10.5% of the limit. In a similar manner, the committed doses due to the annual consumption of each of these two radionuclides in ground water and food, produced in the local biosphere, were evaluated in terms of the Individual Protection Standard (IPS). Based on these analyses, the estimated effective dose for C, using the coefficients in Federal Guidance Report (FGR) No. 13, was 4.15 muSv y, less than 3% of the IPS. For Ra, the comparable estimate at the time of maximum inventory, excluding in this case the contributions from naturally occurring Ra and Ra, was 7.39 muSv y, representing about 5% of the IPS. Based on the value assumed for the fractional release rate (10 y), it was concluded that neither C nor Ra will be significant in terms of either the applicable GWPS or the IPS. While it was recognized that, due to the time spans involved, these analyses were primarily an academic exercise, it is believed that the perspectives and accompanying insights are useful.

Carbon Radioisotopes↗

Characterization of low-level radioactive waste generated by a large university/hospital complex.

Descriptions of the physical characteristics and radioactive contents of waste generated by a large university/hospital complex were recorded in a computerized data base for 1 y. The data were summarized to create a waste stream profile so that major waste sources could be identified and minimization efforts quantified. The resultant profile provides a comprehensive description of the low-level radioactive waste produced by a large biomedical research and patient care facility, and projects the methods that will be used to process and ultimately dispose of the material.

Hospitals↗

Geologic storage of radioactive waste: field studies in Sweden.

Access to a granitic rock mass in an iron ore mine in Sweden provided a unique opportunity for underground experiments related to the geologic disposal of radioactive waste. These field tests demonstrated the importance of hydrogeology and the difficulties in predicting the thermomechanical behavior of fractured granitic rocks. To characterize a site fully, measurements made from the surface must be supplemented by extensive subsurface measurements and experiments. Much effort is needed at this stage to generate the technology required for the development of waste repositories.

Geological Phenomena↗

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↗

A Monte Carlo procedure for the construction of complementary cumulative distribution functions for comparison with the EPA release limits for radioactive waste disposal.

A Monte Carlo procedure for the construction of complementary cumulative distribution functions (CCDFs) for comparison with the U.S. Environmental Protection Agency (EPA) release limits for radioactive waste disposal (40 CFR 191, Subpart B) is described and illustrated with results from a recent performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP). The Monte Carlo procedure produces CCDF estimates similar to those obtained with importance sampling in several recent PAs for the WIPP. The advantages of the Monte Carlo procedure over importance sampling include increased resolution in the calculation of probabilities for complex scenarios involving drilling intrusions and better use of the necessarily limited number of mechanistic calculations that underlie CCDF construction.

Monte Carlo Method↗

Radiation streaming and skyshine evaluation for a proposed low-level radioactive waste assured isolation facility.

Texas is investigating the idea of building a long term waste storage facility, also known as an Assured Isolation Facility. This is an above-ground, retrievable low-level radioactive waste storage facility. A preliminary, scoping-level analysis has been extended to consider more complex scenarios of radiation streaming and skyshine by using MCNP to model the facility in greater detail. Using bounding source term assumptions, the radiation doses and dose rates are found to exceed applicable limits by an order of magnitude. By altering the facility design to fill in the hollow cores of the prefabricated concrete slabs used in the roof over the "high-gamma" rooms where the waste with greatest gamma radiation intensity is stored, dose rates outside the facility decrease by an order of magnitude. With the modified design, the annual dose at the site fenceline is less than the 1 mSv annual limit for exposure of the public. Within the site perimeter, modifying the roof results in an order of magnitude drop in the dose rate for personnel outside the facility and on the facility roof, as well as a significant drop inside the facility. Radiation streaming inside the facility can be lowered almost two orders of magnitude by placing operational restrictions to keep at least two rows of waste containers in front of the high-gamma room to cut down on the size of the path for streaming.

Environmental Monitoring↗

Limitations on upper bound dose to adults due to intake of 129I in drinking water and a total diet-implications relative to the proposed Yucca Mountain high level radioactive waste repository.

The purpose of this report is to comment on the potential annual doses due to the intake by adults of I, an important radionuclide in the proposed high-level radioactive waste repository at Yucca Mountain. An often overlooked, but significant, factor is that, in this case, the ground water, which would be the primary transport vehicle for any releases, contains relatively high concentrations of stable iodine (127I); in fact, the median concentration in the ground water in the vicinity of the proposed repository is 5.0 microg L-1. In comparison, the maximum concentration of 129I in the ground water, due to potential releases of 129I during the first 10,000 y following closure of the repository, is estimated to be approximately 3.7 x 10(-7) Bq L-1 (approximately 10(-5) pCi L-1). This would result in a 127I to 129I ratio in the water of almost 90 million to one. Assuming no other sources of these two isotopes were being consumed, this would place an upper bound on the annual committed thyroid dose of 1.2 x 10(-1) mSv (1.2 x 10(-1) mrem), less than one thousandth of the Ground Water Protection Standard of 4 mrem y-1. When the additional intake of stable and radioactive iodine in other components of the diet is considered, the overall ratio of 127I to 129I would be more than 2 billion to one. The would place an upper bound on the annual committed effective dose of approximately 2.5 x 10(-8) mSv (approximately 2.5 x 10(-6) mrem), less than one millionth of the Individual Protection Standard of 0.15 mSv (15 mrem).

Adult↗

Bioremediation of radioactive waste: radionuclide-microbe interactions in laboratory and field-scale studies.

Given the scale of the contamination associated with 60 years of global nuclear activity, and the inherent high financial and environmental costs associated with invasive physical and chemical clean-up strategies, there is an unparalleled interest in new passive in situ bioremediation processes for sites contaminated with nuclear waste. Many of these processes rely on successfully harnessing newly discovered natural biogeochemical cycles for key radionuclides and fission products. Recent advances have been made in understanding the microbial colonization of radioactive environments and the biological basis of microbial transformations of radioactive waste in these settings.

Bacteria↗

[Radioactive waste monitored around the city hospitals in Brescia. Results of a radiometric survey and model of the radiologic impact on the environment].

The release into environment of liquid radioactive wastes coming from the metabolic therapy department of the Spedali Civili in Brescia was monitored during six months, with a rate of release of about 20 divided by 50 mCi of 131I every 30 divided by 40 days. Samples of 10 liters of liquid, taken from sewers downstream from the release point during a release operation, was percolated on 50 cm3 of ionic exchange resin in order to achieve a suitable counting rate with a Ge(Li) crystal spectrometer, connected to a 2048 channel analyzer. From these measurements a dilution curve along the sewers course was obtained, allowing one to know, for a given radioiodine concentration at the release point, concentration at every point downstream. In this way, by means of a simple linear compartmental model, it is possible to calculate the average individual dose taken by individuals who are living in the region (250.000 inhabitants) in one year of release operations. In our case we considered, as critical pathways to man, cow milk, meat, cereals and fruits: we obtained for thyroid, which in the case of radioiodine is the critical organ, an individual annual dose of 5,41 x 10(-4) mrem, while for total body we obtained 9,49 x 10(-7) mrem.

Environmental Pollution↗

Implementation of the MARSSIM philosophy to evaluate the remedial status of a radioactive waste disposal site at the Idaho National Engineering and Environmental Laboratory. Multi-Agency Radiation Survey and Site Investigation Manual.

Implementation of the MARSSIM remedial-verification protocol at a radioactive waste disposal site is described in some detail to provide a record of the utility of this process. The selected site was the Stationary Low-Power Reactor No. 1 burial ground at the Idaho National Engineering and Environmental Laboratory. Evaluation was restricted to 137Cs in the uppermost 10 cm of potentially contaminated soils. According to the MARSSIM, this site warranted a "Class 1" designation based on previous remedial activities within the burial ground, its status as a radioactive disposal facility, and the anticipated presence of discrete radioactive particles. Nine survey units within the confines of the burial ground were selected, based primarily on the presence of physical boundaries and disparate histories. Surface scans with 100% coverage were performed using a hand-held plastic scintillator and rate meter with audible output. In situ gamma-ray spectrometry was not used for the individual stationary measurements due to the limited area and proximity of engineered barriers. Instead, individual soil samples were obtained using a standard hand-held coring device. The number of soil samples taken from the background reference area and each survey unit were determined with the MARSSIM protocol, which resulted in a total of 160 (including quality-control samples). Two of the nine regions exhibited elevated radiation levels and the null hypothesis could not be rejected in one survey unit, thereby indicating the need for additional remediation. The MARSSIM process proved to be flexible, scientifically rigorous, and cost effective in this field application. Several modifications to the procedure are discussed and offered as recommendations for enhancement of the MARSSIM.

Humans↗

[DNA-protein cross-links in leukocytes of the field mouse (Apodemus agrarius) and the bank vole (Clethrionomys glareolus) dwelling in the territory of a radioactive waste storage station].

DNA-protein cross-links in white blood cells of Apodemus agrarius and Clethrionomys glareolus dwelling in the territory of the guarded zone of the radioactive waste storage in Sergievo Posad (area with gamma-background 50-400 microR/h) have been determined. As a control the animals from sanitary protected area of Sergievo Posadsky department (gamma-background on the soil surface is 8-10 microR/h) was used. It was found that the doses received by Apodemus agrarius and Clethrionomys glareolus, resulted in increasing of the DNA-protein cross-link level in the Apodemus agrarius white blood cells by a factor of 1.8, and in Clethrionomys glareolus by a factor of 1.4, in comparison with control. The increase of DNA-protein cross-link number reliably correlates with the beta-emitting nuclide content in animal bodies. The changes in the number white of cells and in the white blood composition were not observed.

Animals↗