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PubMed2003

Determination of tritium and 14C concentration in two hydrostratigraphic units below the University of California, Davis, waste burial holes at the Laboratory for Energy-Related Health Research/South Campus Disposal Site (LEHR/SCDS).

The Laboratory for Energy-Related Health Research site at the University of California at Davis was used as a disposal site for tritium and 14C waste generated by campus related research. This low-level radioactive waste was disposed of by shallow land burial from 1956 to 1974 in waste burial holes and resulted in extensive contamination of soils and groundwater at the LEHR/SCDS. In part, due to this contamination, the LEHR/SCDS was placed on the National Priority List in May of 1994. In 1999, soils in the vicinity of the waste burial holes were subject to a CERCLA Removal Action. To this day elevated tritium and 14C concentrations are found in two groundwater monitoring wells that are located down gradient from the waste burial holes. The Bioscreen, Natural Attenuation Decision Support System software program was used, along with site-specific hydrogeologic conditions, to estimate the maximum source zone concentrations in the water bearing intervals below the waste burial holes. The first order decay process, and assumptions of horizontal flow provided reasonably accurate estimates of contaminant concentrations in the unconfined portion of the water bearing interval, but results for the confined portion of the water bearing intervals were mixed. Dose estimates for the time period of maximum contaminant concentration in the aquifer below the waste burial holes, predicted by modeling, suggested that the 4 mrem drinking water standard had not been exceeded at this site.

Calibration↗
PubMed1988

Continuous monitoring for airborne alpha emitters in a dusty environment.

Disposal of radioactive wastes in underground facilities requires continuous monitoring for airborne radioactive materials, both on the surface and underground. In addition to a natural background of nonradioactive and radioactive aerosols, there may be a sizeable dust contribution from ongoing work such as mining and vehicular traffic. In the monitoring of alpha-emitting radionuclides, these aerosols may lead to self-absorption in the source and a deterioration of the energy spectrum of the detected alpha particles. In this paper, the influence of a realistic background aerosol on the performance of an alpha monitoring system is evaluated theoretically. It is shown that depositing alpha emitters and background aerosol on a surface for counting leads rapidly to a considerable loss of counts, a deterioration of the alpha spectra, an eventual saturation of the count rates, and interference from the natural background of Rn daughters.

Air Pollution, Radioactive↗
PubMed2004

External radiation exposure of residents living close to the Mayak facility: main sources, dose estimates, and comparison with earlier assessments.

In 1951 and 1952 specialists from the Mayak production association investigated the radiological situation in the area of the Metlinski reservoir that was located 5-7 km from the site of liquid radioactive waste (LRW) discharge. Based on their measurements of both the specific radioactivity in the water and the dose-rate above the water surface, the gamma-field above the water surface in 1951 was demonstrated to be mainly due to (95)Zr+(95)Nb. The dose-rate at the shore of the reservoir was calculated for the period 1949-1951. In November and December 1951, the gamma-field at the shore was mainly due to (140)Ba+(140)La. For the period 1949-1951, the external exposure of the Metlino population due to the decay of these radionuclides was about 200 R (2 Sv), most of the dose having been produced in 1951. The contribution of (137)Cs to external doses did at that time probably not exceed a fraction of several percent. This finding is in contradiction to the assumptions made in the most recent TRDS-2000 system that was developed to reconstruct the doses to the residents of the Techa river. The results presented here demonstrate that the reconstruction of external doses received by the Metlino population as well as by the Techa river residents can be improved for the most critical period between 1949 and 1954.

Body Fluids↗
PubMedDate not supplied

Ocean storage of nuclear wastes? Experiences from the Russian Arctic.

An international demonstration (RD&D) project for ocean storage of radioactive wastes should be proposed, to study the feasibility of the concept of ocean storage of nuclear waste. This international project should utilize the scientific, engineering and technical capabilities of selected universities, oceanographic institutions, NGOs and industries. This project would need to be an independent (non-governmental) study, utilizing the capabilities of selected universities, oceanographic institutions, environmental NGOs (Non-Governmental Organizations) and industries. Scientists and engineers first need to conduct an engineering, environmental, and economic feasibility study of the concept. The goal of the project would be to determine if ocean-based storage reduced the risks to the environment and public health to a greater degree than land-based storage. This would require comparing the risks and factors involved and making the data and information available to anyone, anywhere, anytime on the internet. The mere presence of an investigation of the ocean storage option could facilitate scientific and engineering competition between the two options, could subsequently reduce environmental and public risks and provide better protection and cost benefits in the system utilized. One of the primary concerns of the scientific community would be related to the sensitivity and precision of the monitoring of individaul containers on the ocean bottom. An advantage of the land-based option is that if there is a release, its presence could be detected at very low levels and be contained in the storage facility. On the ocean bottom, a release from a container might not be easily detected due to dispersion. Therefore the containment system would have to be a system within a system with monitoring between the two providing greater protection. Ocean storage may have greater technical and political hurdles than land-based options, but it may provide greater protection over time, because it negates the threat of terrorism, it therefore merit further study. In the future if the use of nuclear energy and nuclear wastes increases, the global society could benefit from this international project, because it could reduce environmental and public health risks and promote energy independence.

Arctic Regions↗
PubMedDate not supplied

[The study of the multifactorial anthropogenic effect on the ecosystems of the industrial reservoirs of "Maiak" industrial complex].

The analysis of the ecological situation of the Southern Urals industrial water reservoirs of the nuclear fuel cycle enterprise, "Mayak" PA is represented. The study was held in the 80s - early 90s. The subjects of the study were: a cooling water reservoir--Kysyl-Tash Lake (R-2) as well as a radioactive waste storage reservoir (R-10). Irtyash Lake, which is a drinking water reservoir for the city of Ozyorsk and Alabuga and Kazhakul Lakes, located on the boundary of the Eastern Urals Radioactive Trace (EURT), were taken as control ones. Such water reservoirs as Irtyash, Kysyl-Tash and the waste storage reservoir (R-10) are incorporated into the Techa River basin; while Alabuga and Kazhakul Lakes are related to the interfluve between the Techa River and the Sinara River. The complex effect from such man--caused factors as radiation, chemical and thermal to water reservoirs' ecosystems was studied. Radionuclide specific activities of the major reservoir components (water, bottom sediments, and biological objects), cumulative stock and radiation doses to the biota were determined. Assessment of the condition of biological structures of individual reservoirs was performed. It was found that the long-term complex influence of radiation, thermal and chemical factors resulted in the formation of the unique technology-induced ecosystems being a part of "Mayak" PA process cycle. Radiation doses to the fish of the cooling water reservoir and the radioactive waste storage reservoir were experimentally estimated. These doses from the incorporated beta-emitters were not less then 2-3 Gy/year. The long-term complex influence of radiation and chemical factors didn't cause any irreversible changes either in the fish population or in the ecosystem. Water purity indicators like crayfish (Astacus leptodactilus Esch) and mollusk (Anodonta cygnea L.) were found in the cooling water reservoir. The comparative analysis of the ecological situation of the reservoirs carried out on the basis of several qualitative indicators and with the help of the formalized scoring system allowed determining that the optimum ecological conditions can be observed in Irtyash Lake. The quality of the environment of Alabuga Lake is slightly lower. The ecological conditions in Kysyl-Tash Lake are up to the standard, while in Kazhakul Lake they are lower than the standard. This is the result of the natural salinization of the ecosystem. The lowest indicator was obtained for the radioactive waste storage reservoir.

Animals↗
PubMed2000

Hybrid radioassay of multiple radionuclide mixtures in waste solutions by using liquid and NaI(Tl) scintillation monitors.

A new analytical technique for radioactive waste solutions has been developed by using a combination of a liquid and a NaI(Tl) scintillation monitor, which enables beta-emitter mixtures to be radioassayed using one calculation process with the method of least squares. This hybrid system can facilitate the analysis of beta-emitter mixtures with very similar liquid scintillation pulse height distributions, such as 3H, 51Cr, and 125I. All that is required for the technique are sets of quench standards of the nuclides to be analyzed and calibration standards for the gamma-emitters. Detection limits for seven nuclides were estimated to be about 0.005 Bq mL(-1), which are sufficiently low compared with the values of authorized safety guidelines.

Chromium Radioisotopes↗
PubMed1994

Radiological effect of a low level waste site on the environment.

Environmental surveillance at the fence line of a low-level radioactive waste disposal site on the Nevada Test Site includes sampling for air particulates, radioiodines, tritium in atmospheric moisture, and airborne transuranics, plus an array of thermoluminescent dosimeters for measurement of external gamma exposures. The results obtained from this surveillance are displayed and discussed. The calculated effluents and the resultant effective dose equivalents to workers and the general public are discussed. It is concluded that, in the 15 years since its establishment, this waste disposal site has led to no significant radiological exposure to workers, the general public, or the environment.

Nevada↗
PubMed1998

Disposal of therapeutic 131I waste using a multiple holding tank system.

Therapeutic application of 131I for the treatment of thyroid cancer generates a significant amount of liquid radioactive waste. Discharge of this waste into the public sewage system is governed by local regulations. In Canada, the permissible concentration is such that only a few patients can be treated in modern water-efficient buildings if this waste is discharged directly through the toilet to the public sewage system. If the toilet discharge is first collected into a holding tank for physical decay before it is released, a large patient load can be handled without exceeding the permissible concentration. In this paper, the principles of operation and the design parameters are discussed, and a multiple holding tank system installed in the Princess Margaret Hospital/Ontario Cancer Institute is described.

Equipment Design↗
PubMed1984

Immobilization and geological disposal of nuclear fuel waste.

The Canadian Nuclear Fuel Waste Management Program is developing methods for the safe disposal of both used nuclear fuel and fuel recycle waste. The disposal strategy is based on interim storage of the used fuel, immobilization of either used fuel or recycle waste, and disposal, deep in a stable geological formation in the Canadian Shield. The disposal concept proposes a multibarrier system to inhibit the release of the radioactive waste from the disposal vault. The principal components of the multibarrier system are (i) the waste form in which the radionuclides are immobilized, (ii) engineered barriers including high integrity containers, buffers and backfills designed to retard the movement of groundwaters in the disposal vault, and (iii) the natural barrier provided by the massive geological formation itself. The research programs to investigate this concept are discussed briefly. Several different waste forms are being developed for the immobilization of high-level fuel recycle waste, including glass, glass-ceramics and crystalline materials. Dissolution of these materials in groundwater is the only likely scenario that could lead to radionuclide release. The factors that influence the aqueous dissolution behaviour of these materials are reviewed.

Ceramics↗
PubMed1995

[The role of the operator of nuclear power plants in disposal of nuclear waste].

Public opinion polls show that the French have largely understood the importance of our nuclear programme in maintaining French independence with regard to power supply and its security and that they have confidence in the technicians for the proper construction and operation of these power plants, but that they retain many questions concerning the disposal of nuclear waste. They have the impression that solutions remain to be found, and especially that the Electricité de France (EDF) devised the nuclear power programme without concern for the disposal of waste. This lack of information is fortunately far from reality. EDF, under the supervision of the security authorities, manages the waste produced in the nuclear power plants. Final stocking of waste is handled by a body that is independent of the waste producer, the "Agence nationale pour la gestion des déchets radioadctifs" (Andra) (National Agency for the Management of Radioactive Waste).

France↗
PubMed2004

Uranium mill tailings: nuclear waste and natural laboratory for geochemical and radioecological investigations.

Uranium mill tailings (UMT) are a high volume, low specific activity radioactive waste typically disposed in surface impoundments. This review focuses on research on UMT and related earth materials during the past decade relevant to the assessment of: (1) mineral hosts of radionuclides; (2) the use of soil analogs in predicting long-term fate of radionuclides; (3) microbial and diagenetic processes that may alter radionuclide mobility in the surficial environment; (4) waste-management technologies to limit radionuclide migration; and (5) the impact of UMT on biota.

Animals↗
PubMed2003

Comparison of the efficacy of biodegradable and non-biodegradable scintillation liquids on the counting of tritium- and [14C]-labeled compounds.

The widespread use of H and 14C in research has generated a large volume of waste mixed with scintillation liquid, requiring an effective control and appropriate storage of liquid radioactive waste. In the present study, we compared the efficacy of three commercially available scintillation liquids, Optiphase HiSafe 3, Ultima-Gold AB (biodegradable) and Insta-Gel-XF (non-biodegradable), in terms of [14C]-glucose and [ H]-thymidine counting efficiency. We also analyzed the effect of the relative amount of water (1.6 to 50%), radioisotope concentration (0.1 to 100 nCi/ml), pH (2 to 10) and color of the solutions (samples containing 0.1 to 1.0 mg/ml of Trypan blue) on the counting efficiency in the presence of these scintillation liquids. There were few significant differences in the efficiency of 14C and H counting obtained with biodegradable or non-biodegradable scintillation liquids. However, there was an 83 and 94% reduction in the efficiency of 14C and H counting, respectively, in samples colored with 1 mg/ml Trypan blue, but not with 0.1 mg/ml, independent of the scintillation liquid used. Considering the low cost of biodegradable scintillation cocktails and their efficacy, these results show that traditional hazardous scintillation fluids may be replaced with the new safe biodegradable fluids without impairment of H and 14C counting efficiency. The use of biodegradable scintillation cocktails minimizes both human and environmental exposure to hazardous solvents. In addition, some biodegradable scintillation liquids can be 40% less expensive than the traditional hazardous cocktails.

Analysis of Variance↗
PubMedDate not supplied

Three-dimensional spatial variability of chemical properties around a monitored waste emplacement tunnel.

Regulatory requirements and scientific needs require that the response of the geological system to emplacement of high level radioactive waste be monitored for long time periods. This monitoring activity is intended to establish the extent to which predicted behavior matches the actual response of the geological system to waste emplacement. To accomplish this goal, field measurements must be made at a spatial resolution that will determine whether the changes in parameters that are monitored conform to predicted evolutionary patterns. From the perspective of thermohydrological and geochemical parameters, key measurements will consider pore water compositional evolution and changes in matrix and fracture saturation in the near vicinity of waste emplacement tunnels. A massively parallel high performance computational platform (a 1200 processor IBM SP-2) was used to conduct three-dimensional, high resolution simulations to ascertain the spatial variability to be expected during a monitoring period. The results show that spatial variability in certain chemical parameters below waste emplacement tunnels provides robust targets for monitoring, but will require sampling on the scale of 10 s of centimeters in some locations, in order to rigorously test models. Chemical variability induced by relatively small changes in waste package heat output suggests that designing a monitoring program that will rigorously test model predictions will likely require high resolution, three-dimensional simulations of the "as-built" monitoring tunnels.

Environmental Monitoring↗
PubMed2004

pH neutralization and zonation in alkaline-saline tank waste plumes.

At the Hanford Site in Washington State, the pH values of contaminant plumes resulting from leaking of initially highly alkaline-saline radioactive waste solutions into the subsurface are now found to be substantially neutralized. However, the nature of plume pH neutralization has not previously been understood. As a master geochemical variable, pH needs to be understood in order to predict the fate and transport of contaminants carried by the waste plumes. Through this laboratory study, we found that the plume pH values spanned a broad range from 14 (within the near-source region) down to the value of 7 (lower than the pH value of the initial soil solution) while the plume was still connected to an actively leaking source. We defined two zones within a plume: the silicate dissolution zone (SDZ, pH 14-10) and the neutralized zone (NZ, pH 10-7). Quartz dissolution at elevated temperature and precipitation of secondary silicates (including sodium metasilicate, cancrinite, and zeolites) are the key reactions responsible for the pH neutralization within the SDZ. The rapid and thorough cation exchange of Na+ replacing Ca2+/Mg2+, combined with transport, resulted in a dynamic Ca2+/Mg2+-enriched plume front. Subsequent precipitation of calcite, sodium silicate, and possibly talc led to dramatically reduced pH within the plume front and the neutralized zone. During aging (after the plume source became inactive), continued quartz dissolution and the secondary silicate precipitation drove the pH value lower, toward pH 11 at equilibrium within the SDZ, whereas the pH values in the NZ remained relatively unchanged with time. A pH profile of 11 from the plume source to pH 7 at the plume front is expected for a historical plume. This laboratory-based study provided realistic plume pH profiles (consistent with that measured from borehole samples) and identified underlying mechanisms responsible for pH evolution.

Environmental Monitoring↗
PubMed2004

Groundwater chemistry of the Okélobondo uraninite deposit area (Oklo, Gabon): two-dimensional reactive transport modelling.

The stability of uranium-bearing minerals in natural environments is of interest to evaluate the feasibility of radioactive waste repositories. The uraninite bodies, UO2(s), in the Oklo district (Gabon) are the result of a natural fission process, which took place 1970 Ma ago. These deposits can be regarded as natural analogues for spent fuel. One of the uraninite bodies, the Okélobondo deposit, is located at a depth of 300 m. Groundwater samples from boreholes located at shallow depths (100-200 m) show neutral to basic pH, anoxic conditions (Eh = 0.10 to -0.05 V) and are saturated with respect to uraninite. In contrast, deeper samples collected in the vicinity of the ore body are oxidising (Eh = 0.32-0.47 V), slightly basic (pH = 7.0-8.5) and undersaturated with respect to uraninite. These oxidising conditions at depth, if present under repository conditions, may affect the stability of uranium oxide. In order to improve our understanding of the observed site geochemistry, the available information on the lithology and groundwater flow was integrated in a reactive transport model. The chemical composition and the pH-Eh values of the water sampled above and in the western side of the Okélobondo deposit can be explained by the interaction of meteoric recharge with pelites, dolomites and sandstones. The dissolution of Fe(II)-silicates and the oxidation of the Fe(II)-aqueous species maintained the pH-Eh distribution along the Fe(2+)-Fe(OH)3(am) equilibrium, with the result that uraninite does not dissolve. This may explain the lower uranium content in the water samples from pelites and dolomites above the Okélobondo deposit. The high Mn/Fe ratio and the high pH-Eh values of the water sampled at depth, close to the Okélobondo deposit, suggest a control by the Mn(2+)-MnOOH(s) equilibrium. This control is attributed to the dissolution of a large rhodochrosite, MnCO3(s), and manganite, MnOOH(s) deposit in the recharge area on the eastern side.

Geological Phenomena↗
PubMed2004

Identifying the sources of subsurface contamination at the Hanford Site in Washington using high-precision uranium isotopic measurements.

In the mid-1990s, a groundwater plume of uranium (U) was detected in monitoring wells in the B-BX-BY Waste Management Area at the Hanford Site in Washington. This area has been used since the late 1940s to store high-level radioactive waste and other products of U fuel-rod processing. Using multiple-collector ICP source magnetic sector mass spectrometry, high-precision uranium isotopic analyses were conducted of samples of vadose zone contamination and of groundwater. The isotope ratios 236U/238U, 234U/238U, and 238U/235U are used to distinguish contaminant sources. On the basis of the isotopic data, the source of the groundwater contamination appears to be related to a 1951 overflow event at tank BX-102 that spilled high-level U waste into the vadose zone. The U isotopic variation of the groundwater plume is a result of mixing between contaminant U from this spill and natural background U. Vadose zone U contamination at tank B-110 likely predates the recorded tank leak and can be ruled out as a significant source of groundwater contamination, based on the U isotopic composition. The locus of vadose zone contamination is displaced from the initial locus of groundwater contamination, indicating that lateral migration in the vadose zone was at least 8 times greater than vertical migration. The time evolution of the groundwater plume suggests an average U migration rate of approximately 0.7-0.8 m/day showing slight retardation relative to a groundwater flow of approximately 1 m/day.

Environmental Monitoring↗
PubMed2001

The effect of coupled transport phenomena in the Opalinus Clay and implications for radionuclide transport.

In this study, the potential effects of coupled transport phenomena on radionuclide transport in the vicinity of a repository for vitrified high-level radioactive waste (HLW) and spent nuclear fuel (SF) hosted by the Opalinus Clay in Switzerland, at times equal to or greater than the expected lifetime of the waste canisters (about 1000 years), are addressed. The solute fluxes associated with advection, chemical diffusion, thermal and chemical osmosis, hyperfiltration and thermal diffusion have been incorporated into a simple one-dimensional transport equation. The analytical solution of this equation, with appropriate parameters. shows that thermal osmosis is the only coupled transport mechanism that could, on its own, have a strong effect on repository performance. Based on the results from the analytical model, two-dimensional finite-difference models incorporating advection and thermal osmosis, and taking conservation of fluid mass into account, have been formulated. The results show that, under the conditions in the vicinity of the repository at the time scales of interest, and due to the constraints imposed by conservation of fluid mass, the advective component of flow will oppose and cancel the thermal-osmotic component. The overall conclusion is that coupled phenomena will only have a very minor impact on radionuclide transport in the Opalinus Clay, in terms of fluid and solute fluxes, at least under the conditions prevailing at times equal to or greater than the expected lifetime of the waste canisters (about 1000 years).

Aluminum Silicates↗