Agricultural research program : quarterly research progress report for the two quarters ending...

"Contract No. AT-40-1-GEN-242."

Agricultural research program : semi-annual progress report for...

"Contract No. AT-40-1-GEN-242."

Naturally occurring radioactive material (NORM) from a former phosphoric acid processing plant

In recent years there has been an increasing awareness of the radiological impact of non-nuclear industries that extract and/or process ores and minerals containing naturally occurring radioactive material (NORM). These industrial activities may result in significant radioactive contamination of (by-) products, wastes and plant installations. In this study, scale samples were collected from a decommissioned phosphoric acid processing plant. To determine the nature and concentration of NORM retained in pipe-work and associated process plant, four main areas of the site were investigated: (1) the 'Green Acid Plant', where crude acid was concentrated; (2) the green acid storage tanks; (3) the Purified White Acid (PWA) plant, where inorganic impurities were removed; and (4) the solid waste, disposed of on-site as landfill. The scale samples predominantly comprise the following: fluorides (e.g. ralstonite); calcium sulphate (e.g. gypsum); and an assemblage of mixed fluorides and phosphates (e.g. iron fluoride hydrate, calcium phosphate), respectively. The radioactive inventory is dominated by U-238 and its decay chain products, and significant fractionation along the series occurs. Compared to the feedstock ore, elevated concentrations (<= 8.8 Bq/g) of U-238 Were found to be retained in installations where the process stream was rich in fluorides and phosphates. In addition, enriched levels (<= 11 Bq/g) of Ra-226 were found in association with precipitates of calcium sulphate. Water extraction tests indicate that many of the scales and waste contain significantly soluble materials and readily release radioactivity into solution. (c) 2005 Elsevier Ltd. All rights reserved.

Estudo da eficiência de deteção de um monitor portátil de contaminação de superfícies em função da distância e do débito de emissão da fonte

Introdução – No caso de uma eventual contaminação radioativa esta deve ser quantificada, pelo que é necessário garantir que as condições de funcionamento de um monitor de contaminação de superfícies se encontrem adequadamente caracterizadas, através da determinação da sua eficiência de deteção. Este estudo tem como objetivo determinar a eficiência de deteção de um monitor de contaminação e analisar a influência da distância e da atividade. Metodologia – O monitor de contaminação Thermo Mini 900E e as fontes radioativas planas de referência de Carbono – 14 (C-14), Césio – 137 (Cs-137), Estrôncio – 90 (Sr-90), Cloro – 36 (Cl-36) e Amerício – 241 (Am-241) com débito de emissão superficial rastreável ao Physikalish Technischen Bundesanstalt (PTB) foram utilizadas. Fontes de Sr-90 e C-14 com dois débitos de emissão distintos para cada e distâncias de 1 a 20mm foram usados para estudar a sua influência na eficiência de deteção. Resultados – Verificou-se que as fontes radioativas emissoras de partículas de maior energia apresentam uma maior eficiência de deteção e que esta diminui com o aumento da distância do detetor à fonte, sendo que os radioisótopos de maior energia apresentam um decréscimo na eficiência de 15% ao longo de 20mm, enquanto os radioisótopos de menor energia apresentam um decréscimo de 10%. Não se verificou uma influência expressiva do débito de emissão na eficiência de deteção deste monitor de contaminação. Conclusão – A eficiência de deteção de um monitor de contaminação portátil é dependente da distância deste à contaminação bem como do tipo de radiação emitida e energia dos radioisótopos presentes na contaminação. - ABSTRACT - Introduction – A radioactive contamination needs to be quantified in case it eventually occurs. Therefore it is necessary to ensure that the operating conditions of a surface contamination monitor are characterized by determining its detection efficiency. This experimental study aims to determine the detection efficiency of a contamination monitor and evaluate the distance and surface emission rate influence on the detection efficiency. Methodology – A contamination monitor Thermo Mini 900E was tested with reference radiation sources of Carbon – 14 (C-14), Cesium – 137 (Cs-137), Strontium – 90 (Sr-90), Chlorine – 36 (Cl-36) and Americium – 241 (Am-241) with its emission rate traced to the Physikalish Technischen Bundesanstalt (PTB). Sources of Sr-90 and C-14 with two different emission rates for each one and distances of 1 to 20mm were used to study its influence in the detection efficiency. Results – With the increasing of distance, the detection efficiency decreases. The most energetic radiation sources have higher detection efficiency, boasting a 15% decrease over 20mm whereas the sources bearing a smaller efficiency decrease 10%. No influence of the surface emission rate in the detection efficiency was verified. Conclusion – Thus, it is concluded that the detection efficiency of a contamination monitor is dependent of the distance between it and the contamination as well as the type and energy of the radioisotopes present in the contamination.

BME-based uncertainty assessment of the Chernobyl fallout

The vast territories that have been radioactively contaminated during the 1986 Chernobyl accident provide a substantial data set of radioactive monitoring data, which can be used for the verification and testing of the different spatial estimation (prediction) methods involved in risk assessment studies. Using the Chernobyl data set for such a purpose is motivated by its heterogeneous spatial structure (the data are characterized by large-scale correlations, short-scale variability, spotty features, etc.). The present work is concerned with the application of the Bayesian Maximum Entropy (BME) method to estimate the extent and the magnitude of the radioactive soil contamination by 137Cs due to the Chernobyl fallout. The powerful BME method allows rigorous incorporation of a wide variety of knowledge bases into the spatial estimation procedure leading to informative contamination maps. Exact measurements (?hard? data) are combined with secondary information on local uncertainties (treated as ?soft? data) to generate science-based uncertainty assessment of soil contamination estimates at unsampled locations. BME describes uncertainty in terms of the posterior probability distributions generated across space, whereas no assumption about the underlying distribution is made and non-linear estimators are automatically incorporated. Traditional estimation variances based on the assumption of an underlying Gaussian distribution (analogous, e.g., to the kriging variance) can be derived as a special case of the BME uncertainty analysis. The BME estimates obtained using hard and soft data are compared with the BME estimates obtained using only hard data. The comparison involves both the accuracy of the estimation maps using the exact data and the assessment of the associated uncertainty using repeated measurements. Furthermore, a comparison of the spatial estimation accuracy obtained by the two methods was carried out using a validation data set of hard data. Finally, a separate uncertainty analysis was conducted that evaluated the ability of the posterior probabilities to reproduce the distribution of the raw repeated measurements available in certain populated sites. The analysis provides an illustration of the improvement in mapping accuracy obtained by adding soft data to the existing hard data and, in general, demonstrates that the BME method performs well both in terms of estimation accuracy as well as in terms estimation error assessment, which are both useful features for the Chernobyl fallout study.

Kontaminaatiomittaukset Loviisan voimalaitoksella

Kandidaatintyössä esitellään Loviisan ydinvoimalaitoksella käytössä olevia menetelmiä ja mittalaitteita radioaktiivisen kontaminaation havaitsemiseen ja mittaamiseen.

Contaminação radioativa: aspectos fundamentais associados à poluição nuclear

Since its discovery, radioactivity has brought numerous benefits to human societies. It has many applications in medicine, serving as a tool for non-invasive methods for diagnosis and therapies against diseases such as cancer. It also applies to technologies for energy in nuclear power plants with relatively low impacts on terms of perfect security. All applications, however, have risks, requiring maximum caution to drive processes and operations involving radioactive elements because, once released into the environment, they have extremely harmful effects on organisms affected. This paper presents fundamental concepts and principles of nuclear physics in order to understand the effects of radioactive elements released into the environment, culminating on the issue of radioactive contamination. Literature review allowed us to understand the radioactive contamination problem on living beings. Three major nuclear accidents have happened in the last thirty years, two of them in consecutive years. The nuclear accident at Chernobyl, Ukraine, in 1986, polluted large areas, condemning hundreds of thousands of people to live with consequences of the accident and effects of radiation, killing thousands of people throughout the years. In 1987, a major radiological accident occurred in Goiania (GO) when a source of radioactive cesium was violated, leading to the death of those who had direct or indirect contact with cesium. The most recent accident, in March, 2011, was located at the nuclear power plant in Fukushima Prefecture, Japan, after an earthquake and tsunami hit the region. There is no extensive and accurate knowledge about the consequences of the contamination entailed in that accident, although it is possible to verify signals on a global scale. An analysis of reports of contamination of large areas generated by nuclear plants with release of hazardous wastes suggests it is necessary to rethink the energy matrix of the various countries...

Lowering the radioactivity of the photomultiplier tubes for the XENON1T dark matter experiment

The low-background, VUV-sensitive 3-inch diameter photomultiplier tube R11410 has been developed by Hamamatsu for dark matter direct detection experiments using liquid xenon as the target material. We present the results from the joint effort between the XENON collaboration and the Hamamatsu company to produce a highly radio-pure photosensor (version R11410-21) for the XENON1T dark matter experiment. After introducing the photosensor and its components, we show the methods and results of the radioactive contamination measurements of the individual materials employed in the photomultiplier production. We then discuss the adopted strategies to reduce the radioactivity of the various PMT versions. Finally, we detail the results from screening 286 tubes with ultra-low background germanium detectors, as well as their implications for the expected electronic and nuclear recoil background of the XENON1T experiment.

(Table 1) Activity of strontium-90 in waters of the Northeast Atlantic at the end of 1965 and the beginning of 1966

In 1965-1966 R/V Mikhail Lomonosov conducted studies on concentrations of artificial radioactive products in the Northeast Atlantic. Concentration of strontium-90 at the end of 1965 and the beginning of 1966 was higher than the average level for the ocean and reached about 53 dpm/100 l in the surface layer. The most intense transport of artificial radioactive products out of the Irish Sea was detected in the northern and northeastern directions along the Hebrides and the Orkneys. In addition to radioactive fission products from nuclear weapons tests, radioactive wastes of atomic industrial facilities discharged into the ocean are an important source of radioactive contamination of some regions of the world ocean.

137Cs in waters and bottom sediments of the Sea of Japan in 2002 and 1994

During an expedition aboard R/V Pavel Gordienko (September, 2002) investigations in the Sea of Japan areas, where radioactive wastes were disposed by the former Soviet Union, were carried out in order to assess present level of radioactive contamination of marine environment. Concentration of I37Cs, radioecologically one of the most important radionuclides, in near-bottom sea water and bottom sediments were measured to be low, 2.8-17.2 Bq/m**3 and 3.2-27.2 Bq/kg dry weight, respectively, that did not differ significantly from levels elsewhere in the northwest Pacific Ocean arising from global fallout. Results of measurements were compared with results of the Joint Japanese- Korean -Russian expedition to the Sea of Japan in 1994.

The framework for post-accident preparedness in Europe. The IRPA guiding principles for stakeholder engagement

To provide public and private actors at local, regional, national and European levels with methodologies to: – Create the conditions for them to gradually appropriate the problematic of long term rehabilitation following a situation of long‐lasting radioactive contamination; – Develop in their context appropriate means and tools for rehabilitation strategies; – Foster innovation and experimentation at territorial and national levels.

An Investigation of the destruction of ion exchange resins

Ion exchange resins are used for many purposes in various areas of science and commerce. One example is the use of cation exchange resins in the nuclear industry for the clean up of radioactively contaminated water (for example the removal of 137Cs). However, during removal of radionuclides, the resin itself becomes radioactively contaminated, and must be treated as Intermediate Level Waste. This radioactive contamination of the resin creates a disposal problem. Conventionally, there are two main avenues of disposal for industrial wastes, landfill burial or incineration. However, these are regarded as inappropriate for the disposal of the cation exchange resin involved in this project. Thus, a method involving the use of Fenton's Reagent (Hydrogen Peroxide/soluble Iron catalyst) to destroy the resin by wet oxidation has been developed. This process converts 95% of the solid resin to gaseous CO2, thus greatly reducing the volume of radioactive waste that has to be disposed of. However, hydrogen peroxide is an expensive reagent, and is a major component of the cost of any potential plant for the destruction of ion exchange resin. The aim of my project has been to discover a way of improving the efficiency of the destruction of the resin thus reducing the cost involved in the use of hydrogen peroxide. The work on this problem has been concentrated in two main areas:-1) Use of analytical techniques such as NMR and IR to follow the process of the hydrogen peroxide destruction of both resin beads and model systems such as water soluble calixarenes. 2) Use of various physical and chemical techniques in an attempt to improve the overall efficiency of hydrogen peroxide utilization. Examples of these techniques include UV irradiation, both with and without a photocatalyst, oxygen carrying molecules and various stirring regimes.

Report to the director, National Center for Radiological Health, Public Health Service, on environmental contamination by radioactive substances, December 1, 1967.

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