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At least 1,189 records · Page 66Linked to original sources
PubMed1984

Uptake of 244Cm, 238Pu and other radionuclides by trees inhabiting a contaminated flood plain.

The plant uptake of 244Cm, 137Cs, 238Pu and 90Sr was measured for trees in a flood plain forest whose soils were contaminated by aqueous discharges from a nuclear-fuel chemical separations facility. Uptake of the naturally occurring radionuclide 226Ra was also measured. The relative availability of the nuclides was 238Pu less than 244Cm less than 137Cs less than 226Ra less than or equal to 90Sr. The concentration ratios for 238Pu and 244Cm, 3 X 10(-4) and 3.6 X 10(-3), respectively, were similar to those reported for other plant-soil systems. The ratios for 137Cs and 90Sr, 0.11 and 3.9, were similar to those reported for other southeastern soils. However, the ratio for 226Ra, 2.1, was greater than that normally reported. These ratios, which were determined in the field, were generally similar to those reported for greenhouse studies on the same soil.

Cesium Radioisotopes↗
PubMed2006

Drip-feed bioreactor for the treatment of concentrated wastes with minimal dilution.

Avoiding substrate inhibition is a significant challenge in designing biological treatment systems for concentrated or toxic wastes. Substrate inhibition is commonly avoided by diluting the waste before treatment, however, dilution of a waste before treatment is not always feasible. In the case of radioactive mixed wastes and chemical warfare materiel (CWM), dilution presents regulatory and safety concerns. In this study, we investigated a "drip-feed" reactor configuration as an alternative approach for the biological treatment of concentrated waste streams with minimal dilution and complete containment. In the drip-feed reactor undiluted waste is slowly fed to biomass in a reactor at a rate sufficient to maintain activity, but at a low enough rate so that bacterial degradation maintains the reactor concentration below the toxic threshold. The reactor has no effluent, but rather fills as the undiluted waste is fed to the reactor, which has the advantage of preventing the release of hazardous material into the environment during treatment. Volatile releases are prevented with the use of condensers. The drip-feed bioreactor configuration was tested under aerobic conditions, at 25 degrees C, using a 10% acetonitrile feed solution. The treatment of acetonitrile to less than 0.1 mg l(-1) was achieved with a dilution factor of only 3.4. The acetonitrile degradation reaction was pH sensitive, where the optimal pH range for the biodegradation process was approximately between 6.5 and 7.1 and the biodegradation rate declined precipitously above pH 7.2. The applicability of the drip-feed reactor configuration to the treatment of mixed wastes and CWM is discussed.

Acetonitriles↗
PubMed2001

Technical procedures for the evaluation of different radiation detection systems at the entrance of a waste incinerator plant.

To protect a new waste incinerator plant and the population against the accidental introduction of radioactive material in the furnace, in 1998 the Municipal Service Corporation of the city of Brescia decided to acquire a radiation detection portal system. However, the performance of such instruments is not sufficiently specified in this type of application, so ASM asked the Nuclear Engineering Department of the Polytechnic of Milan to draw up a test protocol and to lead the following experimental campaign. A truck trailer and a source container were prepared ad hoc, and three different systems underwent a sensitivity and a false alarm test. On the basis of the final results, the performance characteristics of various monitoring systems in this particular application were established with the correct degree of accuracy.

Air Pollution, Radioactive↗
PubMed2003

[Radiation management for infectious waste from nuclear medicine studies].

An industrial waste management service has refused to collect medical waste from our hospital owing to radioactive contamination found in the waste in July 2000. An investigation revealed that the "three-way stopcock" and handling diapers used for radioisotope examination were the radioactive contaminants. We therefore reconsidered the system of medical waste maintenance especially for radioactive materials. Since February 2001, we have resumed radiation maintenance by following the manual for the handling diapers of patients administered radiopharmaceuticals issued by five organizations associated with JRS, JSRT, JSNM, JSNMT, and JARPM. A major change was to check the radioactive waste at the individual departments and at a centralized check system. This eliminated the problem of dumping radioactive material into medical waste as well as resolving the concerns of the industrial waste management service.

Containment of Biohazards↗
PubMed2003

Intercomparison of reactive transport models applied to UO2 oxidative dissolution and uranium migration.

Oxidative dissolution of uranium dioxide (UO(2)) and the subsequent migration of uranium in a subsurface environment and an underground waste disposal have been simulated with reactive transport models. In these systems, hydrogeological and chemical processes are closely entangled and their interdependency has been analyzed in detail, notably with respect to redox reactions, kinetics of mineralogical evolution and hydrodynamic migration of species of interest. Different codes, where among CASTEM, CHEMTRAP and HYTEC, have been used as an intercomparison and verification exercise. Although the agreement between codes is satisfactory, it is shown that the discretization method of the transport equation (i.e. finite elements (FE) versus mixed-hybrid FE and finite differences) and the sequential coupling scheme may lead to systematic discrepancies.

Kinetics↗
PubMed2001

On the disposal of contaminated milk in coastal waters.

Estimates have been made of the reduction in dissolved oxygen levels in coastal waters that would result from the disposal of contaminated milk following a radiological accident. Two contrasting sites were chosen: the Bristol Channel near Hinkley Point and the coast of Cumbria near Sellafield. The results suggest that the dilution would be sufficiently strong near Hinkley Point, due to vigorous tidal mixing, that the impact on the DO levels of the coastal waters would be negligible. However, at both Sellafield and Heysham the disposal of milk could result in a reduction of the DO by 1-2 mg l(-1). In contrast to shallow estuarine waters, the recovery of oxygen levels due to the effects of re-aeration through surface gas exchange is unlikely to be significant due to the depth of the coastal waters. However, the recovery of the dissolved oxygen levels to ambient conditions following the completion of the discharge would occur on a time scale of about 17 days due to mixing of the DO deficit plume into the surrounding waters.

Animals↗
PubMed2001

Behaviour and transport of radionuclides in soil and vegetation of a sand dune ecosystem.

A sand dune ecosystem in the vicinity of the British Nuclear Fuels reprocessing plant at Sellafield, Cumbria, UK was used to examine the spatial, temporal and depth distributions of 134Cs, 137Cs, 238Pu, 239 + 240Pu and 241Am in soil and in two species of vegetation (Festuca rubra, Ammophila arenaria). Core samples showed evidence of the accumulation of radionuclides derived mainly from sea-to-land transfer. Accumulated deposits of radioactivity (0-0.1 m) lie within the range: 1.1-3.4 Bq kg-1 (134Cs), 260-440 Bq kg-1 (137Cs), 31-40 Bq kg-1 (238Pu), 150-215 Bq kg-1 (239 + 240Pu) and 190-240 Bq kg-1 (241Am). Soil profiles showed greater activity concentrations in their deeper regions and this is attributed to leaching of radionuclides in percolating drainage water accentuated by the coarse texture, low organic matter and clay mineral content of coastal sands. Radionuclide activity concentrations in F. rubra and A. arenaria were similar, in the ranges 20-70 Bq kg-1 (137Cs), 1-5 Bq kg-1 (238Pu), 10-30 Bq kg-1 (239 + 240Pu) and 10-65 Bq kg-1 (241Am). Clear temporal and spatial variations were observed in both species of vegetation, reflecting the weather conditions antecedent to the sampling period and the influence of sea-to-land transfer. Concentration ratios (vegetation:soil) for activity concentrations in the two species were similar, in the ranges: 0.05-0.14 (137Cs), 0.025-0.097 (238Pu), 0.022-0.057 (239 + 240Pu) and 0.025-0.212 (241Am).

Americium↗
PubMed2003

Estimates of (239+240)Pu inventories in Gdańsk Bay and Gdańsk basin.

This paper presents and discusses the results of (239+240)Pu determinations in different components of Gdańsk bay and Gdańsk basin ecosystem, as well as estimated sources and inventories of plutonium in these basins. The total plutonium (239+240)Pu activities deposited in Gdańsk bay and Gdańsk basin sediments are 1.18 TBq and 3.77 TBq, respectively. Two rivers, the Vistula and Neman rivers, and atmospheric fallout were distinguished as the main sources of plutonium in these basins. In seawater (with suspended matter included) there is about 2.33 GBq (239+240)Pu (0.2% of total activity) in Gdańsk bay and 9.92 GBq (239+240)Pu (0.3% of total activity) in Gdańsk basin. In both cases, 56% of (239+240)Pu is associated with suspended matter. Organisms contain 3.81 MBq in Gdańsk bay and 7.45 MBq (239+240)Pu in Gdańsk basin. From this value in Gdańsk bay 82.1% of plutonium is associated with zoobenthos, 13.6% with phytobenthos, 1.6% with phytoplankton, 1.5% with zooplankton and 1.2% with fish. In Gdańsk basin, 83.2% is associated with zoobenthos, 7.5% with phytobenthos, 3.6% with phytoplankton, 3.2% with zooplankton and 2.5% with fish.

Animals↗