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The role of performance assessment in the regulation of underground disposal of radioactive wastes: an international perspective.

Much has been written about the development and application of quantitative methods for estimating under uncertainty the long-term radiological performance of underground disposal of radioactive wastes. Until recently, interest has been focused almost entirely on the technical challenges regardless of the role of the organization responsible for these analyses. Now the dialogue between regulators, the repository developer or operator, and other interested parties in the decision-making process receives increasing attention, especially in view of some current difficulties in obtaining approvals to construct or operate deep facilities for intermediate or high-level wastes. Consequently, it is timely to consider the options for regulators' review and evaluation of safety submissions, at the various stages in the site selection to repository closure process, and to consider, especially, the role for performance assessment (PA) within the programs of a regulator both before and after delivery of such a submission. The origins and broad character of present regulations in the European Union (EU) and in the OECD countries are outlined and some regulatory PA reviewed. The issues raised are discussed, especially in regard to the interpretation of regulations, the dangers from the desire for simplicity in argument, the use of regulatory PA to review and challenge the PA in the safety case, and the effects of the relationship between proponent and regulator. Finally, a very limited analysis of the role of PA in public hearings is outlined and recommendations are made, together with proposals for improving the mechanisms for international collaboration on technical issues of regulatory concern.

Ethics↗

Test case of the long term preliminary performance assessment for the L&IL radioactive waste repository Baita Bihor, Romania.

The paper presents the assessment methodology developed in the framework of the long-term preliminary performance assessment of Baita Bihor Romanian national low-level and intermediate-level radioactive waste repository. Conservative assumptions, input parameters and tools used in this approach reflect limitations imposed by the current assessment capability, as well as limited knowledge and understanding of the disposal system. The resultant dose rates are presented and analysed. Conclusions are drawn relating to the safety of the repository.

Computer Simulation↗

Use of a simulation model in occupational dose assessment at a high-level radioactive waste repository.

Occupational radiation dose assessment at a nuclear facility can benefit from a systems approach that recognizes the complex dynamics of the facility. A simulation model can be a useful tool for accomplishing this goal. This technique can quantify the uncertainty in estimates of occupational dose equivalent and illustrate the effects of system interactions. A simulation model of operations at a high-level radioactive waste repository together with a radiological dose assessment model were used to illustrate this technique. Annual individual and collective occupational dose equivalents were estimated in the truck cask receiving and handling stations at a repository. The uncertainty of these estimates is shown through the use of complementary cumulative distribution functions. The effects of changing parameters in cask handling operations are examined.

Computer Simulation↗

Environmental monitoring for a low-level radioactive waste management facility: incinerator operations.

An environmental monitoring program has been developed for Harvard University, Southborough campus, to assess the local environmental concentrations of radionuclides released in incinerator effluents. The campus is host to the University's low-level radioactive waste management facility, which consists of 6,000 drum capacity decay-storage buildings; a 250 drum capacity decay-storage freezer; and a controlled-air incinerator. Developmental considerations were based on the characteristics and use of the incinerator, which has a capacity of 8 tons per day and is operated 5% of the time for the volume reduction of Type 0 and Type 4 wastes contaminated with a variety of radionuclides used in biomedical research-some in microsphere form. Monitoring was established for air, leafy vegetation, leaf-litter, and surface soil media. Field sampling was optimized regarding location and time based on the action of atmospheric, terrestrial, and biotic transport mechanisms. Preliminary results indicate transient concentrations of 3H and 125I in vegetation directly exposed to the dispersing plume. Measurable particulate depositions have not been observed.

Environmental Monitoring↗

Stirring system for radioactive waste water storage tank.

A stirring system for 100-m(3) radioactive liquid waste tanks was constructed to unify radioactive concentrations in the tank. The stirring system is effective in certifying that the radioactive concentrations in the tanks are less than the legal limits before they are drained away as waste liquid. This system is composed of discharge units, pipe lines, and a controller. The performance of the system was assessed by comparing the calculated red ink and 32P concentrations with those monitored at six locations in the tanks. The concentration reached equilibrium after stirring 60 to 120 min with discharge units equipped with six fixed openings configured in differing directions. Residual chlorine in city water used for dilution occasionally bleached the red ink and reduced its concentration. The adsorption of 32P by slime on the walls of the tanks storing actual waste water lowered the equilibrium concentration.

Radioactive Waste↗

Applications of ICRP 30, ICRP 23, and radioactive waste risk assessment techniques to chemical carcinogens.

Linear, no threshold dose-response relationships at low doses are now accepted by U.S. Government agencies for risk assessment of chemical carcinogens. By application of ICRP30 metabolic models, ICRP23 data on ingestion intake of elements, and radioactive waste risk assessment techniques, it is shown that this predicts large numbers of eventual fatalities because of the high probability for material in the ground to eventually be ingested by humans. For example, a detailed for material in the ground to eventually be ingested by humans. For example, a detailed calculation shows that the cadmium released in U.S. coal burning in one year will eventually cause 20,000 fatal cancers (1000/GWe-yr of electricity production), the imports of cadmium into the U.S. will eventually cause 130,000 fatalities for each year of importing at the current rate, and CdS photovoltaic cells will cause 400 fatalities/GWe-yr.

Cadmium↗

Experimental and modeling study of adsorption-desorption processes with application to a deep-well injection radioactive waste disposal site.

Radionuclide (Sr-90 and Cs-137) behavior in the subsurface environment was evaluated with respect to natural attenuation, sorption and desorption kinetics, and equilibrium. Batch experiments were conducted with synthesized groundwater or acid (NaNO3; pH approximately 3) solutions under different temperature (T=20 and 70 degrees C) and pressure (P=Patm and P=3 MPa) conditions. Samples of sedimentary rock were selected as the solid phase from a radioactively contaminated site associated with deep-well injection of the radioactive waste. Groundwater and a NaNO3 waste-brine solution were used as the liquid phase. All experiments revealed hysteresis in radionuclide adsorption. Moreover, some of the experiments indicated that the adsorption process may be irreversible. A simultaneous temperature and pressure increase leads to anomalous behavior of the adsorption kinetics: a period of a rapid concentration drop of the radionuclides in solution, which is caused by their sorption uptake, is changed by a stage of a gradual increase in the corresponding concentrations. To explain the observed phenomena, several hypotheses were examined. Thus, an analytical model describing the mutual interference of adsorption kinetics and dissolution of carbonate minerals was developed resulting in a nonmonotonic behavior of the concentration curves obtained at the adsorption stage. For the description of the batch experiments with radionuclides at room temperature and atmospheric pressure, a dual-site adsorption model has been used.

Adsorption↗

Cost-benefit of final radiological survey versus radioactive waste disposal.

A significant portion of the cost for D&D is related to low-level waste disposal, decontamination, and final radiological survey. For that reason, a careful cost-benefit analysis must be performed weighing the cost of decontaminating and radiologically surveying the building media for release against the cost of disposing of the material as radioactive waste. This cost-benefit analysis visibly came into play at the Rocky Flats Environmental Technology Site during the recent D&D of two facilities.

Cost-Benefit Analysis↗

Validation of a physically based catchment model for application in post-closure radiological safety assessments of deep geological repositories for solid radioactive wastes.

The physically based river catchment modelling system SHETRAN incorporates components representing water flow, sediment transport and radionuclide transport both in solution and bound to sediments. The system has been applied to simulate hypothetical future catchments in the context of post-closure radiological safety assessments of a potential site for a deep geological disposal facility for intermediate and certain low-level radioactive wastes at Sellafield, west Cumbria. In order to have confidence in the application of SHETRAN for this purpose, various blind validation studies have been undertaken. In earlier studies, the validation was undertaken against uncertainty bounds in model output predictions set by the modelling team on the basis of how well they expected the model to perform. However, validation can also be carried out with bounds set on the basis of how well the model is required to perform in order to constitute a useful assessment tool. Herein, such an assessment-based validation exercise is reported. This exercise related to a field plot experiment conducted at Calder Hollow, west Cumbria, in which the migration of strontium and lanthanum in subsurface Quaternary deposits was studied on a length scale of a few metres. Blind predictions of tracer migration were compared with experimental results using bounds set by a small group of assessment experts independent of the modelling team. Overall, the SHETRAN system performed well, failing only two out of seven of the imposed tests. Furthermore, of the five tests that were not failed, three were positively passed even when a pessimistic view was taken as to how measurement errors should be taken into account. It is concluded that the SHETRAN system, which is still being developed further, is a powerful tool for application in post-closure radiological safety assessments.

Fresh Water↗