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Microbially mediated redox processes in natural analogues for radioactive waste.

Natural analogues allow scientists to investigate biogeochemical processes relevant to radioactive waste disposal that occur on time scales longer than those that may be studied by time-limited laboratory experiments. The Palmottu U-Th deposit in Finland and the Bangombé natural nuclear reactor in Gabon involve the study of natural uranium, and are both considered natural analogues for subsurface radioactive waste disposal. The microbial population naturally present in groundwater may affect the redox conditions, and hence, the radionuclide solubility and migration. Therefore, groundwater samples from the two sites were investigated for microbial populations. The total numbers of cells ranged from 10(4) to 10(6) cells ml(-1). Iron-reducing bacteria (IRB) were the largest culturable microbial population in the Palmottu groundwater and were present at up to 1.3 x 10(5) cells ml(-1). Sulfate-reducing bacteria (SRB) and acetogens could also be cultured from the Palmottu groundwater. The numbers of IRB and SRB were largest in groundwater with the lowest uranium concentrations. Removal of dissolved U(VI) from solution was concomitant with the growth of IRB enrichment cultures and the reduction of iron. The redox buffer in the Palmottu groundwater consists of iron and uranium species, both of which are affected by IRB. IRB and aerobic heterotrophs were cultured from the Bangombé groundwater, where redox potentials are buffered by iron and organic carbon species. Microbial populations similar to those found at Palmottu and Bangombé are found throughout the Fennoscandian Shield, a potential host rock for subsurface radioactive waste disposal. These results confirm that microorganisms can be expected to play a role in stabilizing radioactive waste disposed of in the subsurface by lowering redox potential and immobilizing radionuclides.

Bacteria↗

[Experince accumulated by RADON Industrial Research Association in treating radioactive waste].

To reduce volume of radioactive waste for long storage, specialists in "RADON" Industrial Research Association according to qualitative contents of the waste use methods of filtration and selective sorption of radionuclides, electrolysis, monoselective purification, burning, plasmic burning and pressing. Overall volume of the waste processed by various plants exceeds 50 thousand cubic meters. The mentioned technologies could be widely used in radiochemical works and other nuclear energy plants.

Electrolysis↗

Radioactive waste management at a large university and medical research complex.

A radioactive waste management program was developed for a large university and medical research complex to contain costs and to reduce the impact of the Low-Level Radioactive Waste Policy Act. The program takes advantage of decay-in-storage, incineration, special packaging techniques, and increased training and awareness. A series of metrics are presented to evaluate the effectiveness of the radioactive waste management program. Through the use of this program the amount of waste disposed of at commercial burial sites decreased from 98% to 1.61% of the waste generated. At the same time the volume of waste generated per laboratory declined by almost 45%, from 0.35 m3 (12.31 ft3) to 0.19 m3 (6.80 ft3).

Academic Medical Centers↗

[Investigation of radioactivity measurement of medical radioactive waste].

To explore the possibility of which medical radioactive wastes could be disposed as general wastes after keeping them a certain period of time and confirming that their radioactivity reach a background level (BGL), we made a survey of these wastes in several nuclear medicine facilities. The radioactive wastes were collected for one week, packed in a box according to its half-life, and measured its radioactivity by scintillation survey meter with time. Some wastes could reach a BGL within 10 times of half-life, but 19% of the short half-life group (group 1) including 99mTc and 123I, and 8% of the middle half-life group (group 2) including 67Ga, (111)In, and 201Tl did not reach a BGL within 20 times of half-life. A reason for delaying the time of reaching a BGL might be partially attributed to high initial radiation dose rate or heavy package weight. However, mixing with the nuclides of longer half-life was estimated to be the biggest factor affecting this result. When disposing medical radioactive wastes as general wastes, it is necessary to avoid mixing with radionuclide of longer half-life and confirm that it reaches a BGL by actual measurement.

Half-Life↗

Review of the radioactive waste management system in Nigeria.

The management of radioactive waste in Nigeria from early 1960 to date is reviewed. As in many developing countries, waste management in Nigeria has been shown to be ineffective. The factors that are responsible for this ineffectiveness are identified and discussed. The steps being taken by and the opportunities available to the newly established Nigerian Nuclear Regulatory Authority towards addressing this problem of ineffectiveness are discussed. The efforts of this newly set up body towards managing the resultant radioactive wastes that will be generated during the use of a reactor and an accelerator that will soon be commissioned in Nigeria are also mentioned. Likely ways of further addressing the problems militating against waste management in developing countries are suggested.

Developing Countries↗

Recent trends and developments in dialogue on radioactive waste management: experience from the UK.

This paper highlights some recent trends and developments in dialogue on radioactive waste management in the UK. In particular, it focuses on the use of dialogue around options for the management of risk, and describes techniques for stakeholder dialogue in the field of radioactive waste management. The paper summarises past and on-going experience in the UK, and provides an overview of some practical examples from decommissioning of the former reprocessing facility at Dounreay in Scotland. In common with developments and trend in other countries, the UK has moved to a position where there is now widespread recognition that radioactive waste management requires not only sound technical assessment of risk, but also public participation, consultation and stakeholder dialogue on proposed solutions and the associated risks. In fact, the shift of position has arguably been quite pronounced, with formal procedures to identify, clarify and integrate stakeholders' issues and concerns within the decision-making processes. Experience suggests that citizens are capable of engaging with complex technical issues such as radioactive waste. Indeed, the earlier in the decision-making process that public and stakeholder engagement (PSE) occurs--for example, on the consideration of options and alternatives--the greater the chance of reaching a successful outcome that properly reflects the values and opinions of stakeholders. In the UK, the assessment of alternative waste management options is increasingly being addressed through Best Practical Environmental Option (BPEO) studies. Responses to stakeholder engagement processes and experience of conducting BPEO studies emphasise that consultation must be open, transparent, deliberative and inclusive. However, while early consideration of generic approaches and option choices is necessary to generate a climate of openness and understanding, it remains essential to fully engage with local stakeholder and community groups to consider issues associated with proposed developments at a site-specific level. An interesting area where further attention may be warranted is the use in final decision-making of the results from participatory processes such as BPEO studies. Demonstrating clearly that participants' views have influenced decisions appears to be essential for retaining legitimacy and trust, confidence and goodwill.

Community Participation↗

Collective dose estimates by the marine food pathway from liquid radioactive wastes dumped in the Sea of Japan.

IAEA-MEL has been engaged in an assessment programme related to radioactive waste dumping by the former USSR and other countries in the western North Pacific Ocean and its marginal seas. This paper focuses on the Sea of Japan and on estimation of collective doses from liquid radioactive wastes. The results from the Japanese-Korean-Russian joint expeditions are summarized, and collective doses for the Japanese population by the marine food pathway are estimated from liquid radioactive wastes dumped in the Sea of Japan and compared with those from global fallout and natural radionuclides. The collective effective dose equivalents by the annual intake of marine products caught in each year show a maximum a few years after the disposals. The total dose from all radionuclides reaches a maximum of 0.8 man Sv in 1990. Approximately 90% of the dose derives from 137Cs, most of which is due to consumption of fish. The total dose from liquid radioactive wastes is approximately 5% of that from global fallout, the contribution of which is below 0.1% of that of natural 210Po.

Animals↗

Geochemical evaluation of different groundwater-host rock systems for radioactive waste disposal.

The geochemical suitability of a deep bedrock repository for radioactive waste disposal is determined by the composition of geomatrix and groundwater. Both influence radionuclide solubility, chemical buffer capacity and radionuclide retention. They also determine the chemical compatibility of waste forms, containers and backfill materials. Evaluation of different groundwater-host rock systems is performed by modeling the geochemical environments and the resulting radionuclide concentrations. In order to demonstrate the evaluation method, model calculations are applied to data sets available for various geological formations such as granite, clay and rocksalt. The saturation state of the groundwater-geomatrix system is found to be fundamental for the evaluation process. Hence, calculations are performed to determine if groundwater is in equilibrium with mineral phases of the geological formation. In addition, corrosion of waste forms in different groundwater is examined by means of reaction path modeling. The corrosion reactions change the solution compositions and pH, resulting in significant changes of radionuclide solubilities. The results demonstrate that geochemical modeling of saturation state and compatibility of the host formation environment with the radioactive waste proves to be a feasible tool for evaluation of various sites considered as deep underground repositories.

Corrosion↗

Advances in cement solidification technology for waste radioactive ion exchange resins: a review.

Treatment and disposal of waste radioactive ion exchange resins is one of the most urgent problems for nuclear industries in China. Cement solidification technology has many advantages, such as requiring simple equipment, easy scaling-up, low working temperature, no trouble of gas cleaning and low cost. It is a suitable technology for treatment of waste radioactive resins, and has been widely used. The new developments and theoretical basis of cement solidification of radioactive resins were introduced in this paper. The cement solidification technology suitable for China and the questions needed to solve were also discussed.

Hot Temperature↗

[Modyfying complex additives in technologies for cementing radioactive waste].

The article presents results obtained in studies concerning properties of cement compounds with radioactive waste, if made with modifying complex additive. Modifying complex additive was proved to influence positively on technologic parameters of cementing liquid and solid radioactive waste, on possible lower volume of cemented waste vs. the volumes obtained through traditional cementing methods without the modifying complex additive, on regulated qualities of end cement compounds with radioactive waste and prevention of biologic corrosion in presence of the modifying complex additive.

Construction Materials↗

A security vulnerabilities assessment tool for interim storage facilities of low-level radioactive wastes.

Limited permanent low-level radioactive waste (LLRW) disposal capacity and correspondingly high disposal costs have resulted in the creation of numerous interim storage facilities for either decay-in-storage operations or longer term accumulation efforts. These facilities, which may be near the site of waste generation or in distal locations, often were not originally designed for the purpose of LLRW storage, particularly with regard to security. Facility security has become particularly important in light of the domestic terrorist acts of 2001, wherein LLRW, along with many other sources of radioactivity, became recognized commodities to those wishing to create disruption through the purposeful dissemination of radioactive materials. Since some LLRW materials may be in facilities that may exhibit varying degrees of security control sophistication, a security vulnerabilities assessment tool grounded in accepted criminal justice theory and security practice has been developed. The tool, which includes dedicated sections on general security, target hardening, criminalization benefits, and the presence of guardians, can be used by those not formally schooled in the security profession to assess the level of protection afforded to their respective facilities. The tool equips radiation safety practitioners with the ability to methodically and systematically assess the presence or relative status of various facility security aspects, many of which may not be considered by individuals from outside the security profession. For example, radiation safety professionals might not ordinarily consider facility lighting aspects, which is a staple for the security profession since it is widely known that crime disproportionately occurs more frequently at night or in poorly lit circumstances. Likewise, the means and associated time dimensions for detecting inventory discrepancies may not be commonly considered. The tool provides a simple means for radiation safety professionals to assess, and perhaps enhance in a reasonable fashion, the security of their interim storage operations. Aspects of the assessment tool can also be applied to other activities involving the protection of sources of radiation as well.

Criminal Law↗

Model for inactivation and disposal of infectious human immunodeficiency virus and radioactive waste in a BL3 facility.

A method is described for autoclaving low levels of solid infectious, radioactive waste. The method permits steam penetration to inactivate biologic waste, while any volatile radioactive compounds generated during the autoclave process are absorbed. Inactivation of radiolabeled infectious waste has been problematic because the usual sterilization techniques result in unacceptable radiation handling practices. If autoclaved under the usual conditions, there exists a high probability of volatilization or release of radioisotopes from the waste. This results in the radioactive contamination of the autoclave and the laboratory area where steam is released from the autoclave. Our results provide a practical method to inactivate and dispose of infectious radioactive waste. For our research, Bacillus pumilus spore strips and vaccinia virus were used as more heat-resistant surrogates of the human immunodeficiency virus (HIV). These surrogates were used because HIV is difficult to grow under most conditions and is less heat tolerant than the surrogates. In addition, B. pumilus has defined cell death values, whereas such values have not been established for HIV. Both B. pumilus and vaccinia virus are less hazardous to work with. The autoclave method is time efficient and can be performed by laboratory personnel with minimal handling of the waste. Furthermore, waste site handlers are able to visually inspect the solid waste containers and ascertain that inactivation procedures have been implemented.

Disinfection↗

Accelerated biodegradation of cement by sulfur-oxidizing bacteria as a bioassay for evaluating immobilization of low-level radioactive waste.

Disposal of low-level radioactive waste by immobilization in cement is being evaluated worldwide. The stability of cement in the environment may be impaired by sulfur-oxidizing bacteria that corrode the cement by producing sulfuric acid. Since this process is so slow that it is not possible to perform studies of the degradation kinetics and to test cement mixtures with increased durability, procedures that accelerate the biodegradation are required. Semicontinuous cultures of Halothiobacillus neapolitanus and Thiomonas intermedia containing thiosulfate as the sole energy source were employed to accelerate the biodegradation of cement samples. This resulted in a weight loss of up to 16% after 39 days, compared with a weight loss of 0.8% in noninoculated controls. Scanning electron microscopy of the degraded cement samples revealed deep cracks, which could be associated with the formation of low-density corrosion products in the interior of the cement. Accelerated biodegradation was also evident from the leaching rates of Ca(2+) and Si(2+), the major constituents of the cement matrix, and Ca exhibited the highest rate (up to 20 times greater than the control rate) due to the reaction between free lime and the biogenic sulfuric acid. Leaching of Sr(2+) and Cs(+), which were added to the cement to simulate immobilization of the corresponding radioisotopes, was also monitored. In contrast to the linear leaching kinetics of calcium, silicon, and strontium, the leaching pattern of cesium produced a saturation curve similar to the control curve. Presumably, the leaching of cesium is governed by the diffusion process, whereas the leaching kinetics of the other three ions seems to governed by dissolution of the cement.

Betaproteobacteria↗