Academic literature on the topic 'Non-radioactive in situ hybridisation'

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Journal articles on the topic "Non-radioactive in situ hybridisation"

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Osborne, Peter, and Peter K. Dearden. "Non-radioactive in-situ hybridisation to honeybee embryos and ovaries." Apidologie 36, no. 1 (January 2005): 113–18. http://dx.doi.org/10.1051/apido:2004075.

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Naher, H., D. Petzoldt, and K. K. Sethi. "Evaluation of non-radioactive in situ hybridisation method to detect Chlamydia trachomatis in cell culture." Sexually Transmitted Infections 64, no. 3 (June 1, 1988): 162–64. http://dx.doi.org/10.1136/sti.64.3.162.

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Brown, A., JA Hoyland, and EB Mawer. "P45. Demonstration of 1.25(OH)2D3 receptor mRNA by a novel non-radioactive in situ hybridisation method." Bone 15, no. 2 (March 1994): 241. http://dx.doi.org/10.1016/8756-3282(94)90778-1.

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Liem, R., N. Brouwer, and J. Copray. "Ultrastructural localisation of intramuscular expression of BDNF mRNA by silver-gold intensified non-radioactive in situ hybridisation." Histochemistry and Cell Biology 116, no. 6 (November 27, 2001): 545–51. http://dx.doi.org/10.1007/s00418-001-0349-z.

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Coates, P. J., W. P. Mak, G. Slavin, and A. J. d'Ardenne. "Detection of single copies of Epstein-Barr virus in paraffin wax sections by non-radioactive in situ hybridisation." Journal of Clinical Pathology 44, no. 6 (June 1, 1991): 487–91. http://dx.doi.org/10.1136/jcp.44.6.487.

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Veal, Duncan, Philip Bell, Hayley Brown, Hung-Yoon Choi, and Peter Karuso. "Fluorophores from fungi." Microbiology Australia 24, no. 3 (2003): 12. http://dx.doi.org/10.1071/ma03312.

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Fluorescence has many advantages over traditional colour and radioactive labels, and is playing an increasingly important role in the most powerful analytical techniques. For example, fluorescence is at the heart of many nucleic acid based diagnostics (e.g. DNA microarray, real time-PCR, fluorescence in situ hybridisation, etc), immunofluorescence assays, defined substrate technologies and differential display proteomics and is gradually replacing or complementing other techniques based on colour or radiolabels.
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Troncone, G., S. M. Anderson, C. S. Herrington, M. L. de Angelis, H. Noell, J. A. Chimera, and J. O'D McGee. "Comparative analysis of human papillomavirus detection by dot blot hybridisation and non-isotopic in situ hybridisation." Journal of Clinical Pathology 45, no. 10 (October 1, 1992): 866–70. http://dx.doi.org/10.1136/jcp.45.10.866.

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Keil, C., B. Husen, J. Giebel, G. Rune, and R. Walther. "Glycodelin mRNA is expressed in the genital tract of male and female rats (Rattus norvegicus)." Journal of Molecular Endocrinology 23, no. 1 (August 1, 1999): 57–66. http://dx.doi.org/10.1677/jme.0.0230057.

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In the present study we demonstrate for the first time the expression of glycodelin mRNA in the female and male genital tracts of rats using non-radioactive in situ hybridisation. Glycodelin fragment 1 (+41 to +141) shares 100% homology with the human gene sequence. In the ovary, glycodelin mRNA was restricted to granulosa cells. In the uterus, glycodelin mRNA was expressed in all epithelial cells of the endometrium. In the male reproductive tract, glycodelin mRNA was distributed in all epithelial cells of the epididymis, the prostate and the seminal vesicle. However, in the testis, glycodelin mRNA was predominantly found in spermatogonia and in spermatocytes of the seminiferous epithelium. The expression in several reproductive organs of rats offers an excellent tool to study further the physiological role of glycodelin, which is so far thought to act as an immunosuppressive factor.
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Cooper, K. "Physical state of human papillomavirus using non-isotopic in situ hybridisation." Journal of Clinical Pathology 48, no. 8 (August 1, 1995): 786. http://dx.doi.org/10.1136/jcp.48.8.786.

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Sinowatz, F., D. Schams, S. Kolle, A. Plath, D. Lincoln, and MJ Waters. "Cellular localisation of GH receptor in the bovine mammary gland during mammogenesis, lactation and involution." Journal of Endocrinology 166, no. 3 (September 1, 2000): 503–10. http://dx.doi.org/10.1677/joe.0.1660503.

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We have used immunohistochemistry and non-radioactive in situ hybridisation to localise the GH receptor and its transcript in the bovine mammary gland during mammogenesis, lactation and involution. We found a characteristic pattern of immunoreactive GH (irGH) receptor distribution in the epithelial and stromal compartments during the different stages of mammary gland development: The ductular epithelium showed a distinct staining for irGH receptor during most stages, whereas the alveolar epithelium contained a modest amount of GH receptor during pregnancy which increased during lactation and galactopoiesis. In dry cows, the immunostaining for GH receptors in the alveolar epithelium was very weak or negative. Curiously, the amount of GH receptor mRNA appeared relatively constant during mammogenesis and lactation. The epithelial cells of the alveoli and ducts as well as the endothelial cells showed a distinct signal in our in situ hy! bridisation studies. The predominant localisation of GH receptors in the epithelium of ducts and alveoli is supportive of a role for GH in epithelial differentiation and maintenance. Furthermore, the increased intensity of immunostaining in bovine mammary tissue post partum suggests a direct role for GH receptor in mediating the effect of GH in milk production and secretion.
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Dissertations / Theses on the topic "Non-radioactive in situ hybridisation"

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Hammond, David William. "Analysis of non-Hodgkin's lymphoma by conventional cytogenetics and fluorescence in-situ hybridisation." Thesis, University of Sheffield, 1995. http://etheses.whiterose.ac.uk/3064/.

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Cytogenetic analysis was performed on 40 non-Hodgkin's lymphoma (NHQ node biopsies. Chromosomes X, 3 and 12 were the most frequently gained; of the much rarer monosomies, loss of chromosome 13 was most common. Structural abnormalities primarily involved chromosomes 14,1,18,6 and 17. A markedly greater number of chromosome gains were associated with low-grade disease when compared to high-grade. In order to obtain further information from the cytogenetic analysis of the NHL karyotypes, the fluorescence in-situ hybridisation (FISH) technique was applied to the series. The activation state of additional X-chromosomes was examined and evidence that more than one X-chromosome was present in the active state in 4/9 cases was obtained. Further, in an apparent case of monosomy X, a marker was identified as an abnormal X-chromosome by chromosome painting. Interphase FISH was applied to NHL cells and numerical chromosome changes were identified; this approach was also attempted on aged bone marrow smears from acute lymphocytic leukaemia patients, in order to test the utility of the technique on archival material. Dual chromosome painting was used to elucidate the origins of add(14) chromosomes in 8 of the cases. In the control and two other cases the translocated material was demonstrated to be from chromosome 18, in two cases it was from chromosome 3 and in one case them was an insertion of chromosome 11 material. it was not possible to identify the origins of the translocated material in one NHL and in the final case the apparent add(14) was demonstrated not to contain chromosome 14 material. Structural abnormalities of chromosome 6 were investigated both by chromosome painting and by hybridisation of the MYB gene. The latter, which was initially mapped to 6q23 before hybridisation to NHL cells revealed previously unsuspected rearrangements. One case contained extrachromosomal chromatin bodies that appeared to be double minute chromosomes (dmin), which FISH analysis demonstrated to be derived from the X-chromosome and contain centromere-associated DNA. The significance of these results is discussed with reference to previously published series of NHL karyotypes.
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Karlsson, Christina. "Biomarkers in non-small cell lung carcinoma : methodological aspects and influence of gender, histology and smoking habits on estrogen receptor and epidermal growth factor family receptor signalling." Doctoral thesis, Örebro universitet, Hälsoakademin, 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:oru:diva-19725.

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Non-small cell lung carcinoma is a leading cause of cancer mortality worldwide. There are gender and smoking associated differences both in tumour types and clinical outcome. Squamous cell carcinomas (SCC) are more frequent among smoking men while females develop adenocarcinomas (ADCA). NSCLC among never smokers are mainly ADCA, and occurs mostly in females. The present thesis elucidates the role of estrogen receptor (ER) and epidermal growth factor receptor family (EGFR/HER2-4) in NSCLC in the perspective of gender and histology as well as the influence of smoking on those biomarkers. A recently developed technique, tissue micro array (TMA), was employed.The question of how much of a tumour tissue that needed to be included in a TMA for biomarker analysis was analyzed by a statistical approach. Data indicates a sample size of three cylinders of tumour tissue with a diameter of 0.6 mm each as being appropriate and cost-effective. In order to optimally use the up to thousands of different tumour samples within a TMA, it would be optimal to serially cut and store slides before performing in situ detection of proteins and nucleic acids. Applying up to date methodology, and by evaluation with image analysis, data are presented that shows that such handling of TMA slides would be possible without any loss of biomarker information. ERα is more frequently observed in ADCA and in females and a local estradiol synthesis is supported by the presence of aromatase. ERβ is identified as a positive prognostic marker in ADCA. Smoking is associated to increased levels of ERβ mRNA. EGFR over expression is associated with a ligand. Independent phosporylation of ERα. HER-4 intracellular domain may also act as a co-activator to ERα in ADCA, especially among neversmokers. The question of ER and EGFR family signalling crosstalk as a potential target for combined targeted therapy is raised.
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Habeebu, Sahibu Sultan Murtaza. "The development of non-radioactive detection systems for molecular in situ hybridization." Thesis, University of Cambridge, 1990. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.359750.

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Fraser, Harris Andrew Peter. "Development of a new non-linear elastic hydro-mechanical model for the simulation of compacted MX-80 bentonite : application to laboratory and in situ sealing experiments for geo-repository engineered barriers." Thesis, University of Edinburgh, 2016. http://hdl.handle.net/1842/20419.

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The management of radioactive wastes is a significant environmental issue facing the international nuclear community today. The current international consensus is for disposal of higher activity waste from a variety of sources in deep geological disposal facilities (GDFs). Hydraulic seals, often planned to consist of compacted bentonite-sand blocks, are an important part of the closure phase of a GDF. As such, an understanding of the hydro-mechanical (HM) behaviour of these seals, and the ability to model and predict their behaviour is fundamental to support many planned safety cases and licence applications. Bentonite is well suited for use as a hydraulic seal due to its high swelling capacity that enables it to swell into voids while maintaining a low permeability sealed barrier to advective flow, and to provide structural support by generating a swelling pressure on the excavation walls. The hydro-mechanical process of bentonite hydration is a highly non-linear problem. As such, coupled process models that are able to account for the strong inter-dependence of the hydraulic and mechanical processes are employed to simulate the behaviour of bentonite under repository conditions. This thesis reports the development of an HM coupled model in the open source finite element code OpenGeoSys (OGS), and its application to the simulation of a range of hydraulic seal test conditions. The developed model couples Richards’ equation for unsaturated flow to a new strain dependent non-linear elastic mechanical model that incorporates a Lagrangian moving finite element mesh to inform the material non-linearity. Stress and volumetric dependent water retention behaviour are incorporated through the implementation of the Dueck suction concept extended to take into account non-recoverable strains during consolidation. A number of permeability functions are implemented and tested against experimental data. The mechanical model is extended to account for wetting-induced collapse behaviour by the definition of a failure curve derived from experimental results. Similar in definition to the Loading-Collapse curve in elasto-plastic models, this failure curve triggers the application of a source term to account for wetting-induced collapse. Coupling between the hydraulic and mechanical processes is achieved through the stress dependency of the water retention behaviour, the inclusion of a new coupling factor for the hydraulic contribution to the mechanical process, and the dependency of numerical convergence criteria on net mean stress. An explicit iterative calculation approach is employed. As a result, the hydraulic and mechanical moving meshes are decoupled to allow volumetric dependent parameters to be updated within process iterations. The model is calibrated and compared to experimental data from the SEALEX experiments conducted by the Institut de Radioprotection et de S ˆ uret´e Nucl´eaire (IRSN) at the Tournemire URL, France. The experimental programme comprises standardised laboratory tests, a 1/10th scale mock-up of a hydraulic seal with a uniform technological void, and a full scale in situ performance test with a non-uniform technological void due to its horizontal geometry. Using a model with 5 hydraulic parameters, 8 mechanical parameters with an experimentally defined failure curve, and one coupling parameter, the major trends of behaviour in all the SEALEX experiments can be recreated, including axial stress build up, water uptake, and final deformation. However, the elastic method employed leads to an over prediction of the rebound on loss of axial confinement in the 1/10th scale mock-up test. Simulations suggest that the non-symmetric technological void in the full scale performance test could have lasting effects on the development of heterogeneity in the hydraulic seal. The development of heterogeneity does not adversely affect the permeability with respect to the design criteria, but may have significant consequences for the development of a heterogeneous swelling pressure.
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Toulhoat, Pierre. "Hydrogeochimie de l'uranium, de ses descendants et d'elements associes (lanthanides) : application a la prospection miniere." Paris 6, 1987. http://www.theses.fr/1987PA066648.

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On etudie le comportement de l'uranium et de ses descendants dans les eaux naturelles et on quantifie les phenomenes de fixation en presence de complexants en solution. D'autre part, dans un but de prospection, on etudie les traceurs de mineralisations que sont **(234)u et **(206)pb, les phenomenes d'adsorption/desorption gouvernant en grande partie les modeles de prospection proposes, bases sur la mesure des rapports d'activite **(234)u/**(236)u et de la composition isotopique du plomb dans les eaux
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Gibson, Catherine Elizabeth. "The expression of hydrolytic enzymes in germinating barley grain." Thesis, 2017. http://hdl.handle.net/2440/114266.

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Modification of the barley grain endosperm in germination is fundamental to successful plant growth but also has important ramifications for down-stream industrial uses of barley, particularly in the malting and brewing industries. There are a battery of enzymes that are involved in the modification process but the sites of synthesis and action of only of a few of these have been described in detail and most have only been studied in isolated tissues. The development of a sensitive and robust in situ mRNA hybridization (ISH) procedure, which allows the detection of specific transcripts representing proteins in grain sections is described here. This first required the optimization of grain fixation, embedding and sectioning procedures as well as the adaptation of a staining method using calcofluor white to accurately assess the modification state of each grain prior to processing. Once these technical parameters were established, the non-radioactive ISH protocol was developed to allow the detection of transcripts of (1,3;1,4)-β-glucanases, (1→4)-β-endo-xylanases, limit dextrinase and limit dextrinase inhibitor in grain sections of the two barley cultivars Sloop and Himalaya. The panel of enzymes selected for study covers several aspects of grain modification, such as (1,3;1,4)-β-glucan, xylan and starch breakdown, which are all important for successful grain germination. The successful ISH technique proved sensitive enough to discriminate between the (1,3;1,4)-β-glucanase and xylanase isoenzymes and clearly defined whether the transcipts for these enzymes were synthesized in both a tissue-specific manner and a fixed temporal sequence during grain germination. The use of monoclonal antibodies specific for the two (1,3;1,4)-β-glucanase isoforms in a related immunolabelling procedure, using the same fixed grains, also allowed the patterns of transcript and protein appearance to be correlated. As expected, use of the ISH method showed that the transcripts of the (1,3;1,4)-β-glucanase, xylanase and limit dextrinase inhibitor genes are variously found in the aleurone cells, the starchy endosperm tissue and the scutellum. However, there were also substantial amounts of transcript detected in the tissues of the growing embryo which suggests that these enzymes may also contribute substantially to early seedling development.
Thesis (Ph.D.) -- University of Adelaide, School of Agriculture, Food and Wine, 2018
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Books on the topic "Non-radioactive in situ hybridisation"

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United States. Dept. of Energy. Office of Science and Technology., ed. Overview of non-thermal mixed waste treatment technologies: Treatment of mixed waste (ex situ) : technologies and short descriptions. Germantown, Md: U.S. Dept. of Energy, Assistant Secretary for Environmental Management, Office of Science and Technology, 1995.

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Book chapters on the topic "Non-radioactive in situ hybridisation"

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Nakane, Paul K., Hidekatsu Matsumura, and Takehiko Koji. "In Situ Hybridization Using T-T Dimerized Non-Radioactive Probes." In Biological Aspects of Brain Tumors, 52–62. Tokyo: Springer Japan, 1991. http://dx.doi.org/10.1007/978-4-431-68150-2_5.

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Berger, R. "Non-radioactive in situ hybridization to metaphase and interphase nuclei of malignant cells." In Chromosomes Today, 171–80. Dordrecht: Springer Netherlands, 1993. http://dx.doi.org/10.1007/978-94-011-1510-0_13.

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Veuskens, J., S. Hinnisdaels, and A. Mouras. "In situ hybridization to plant metaphase chromosomes: radioactive and non-radioactive detection of repetitive and low copy number genes." In Plant Tissue Culture Manual, 723–37. Dordrecht: Springer Netherlands, 1993. http://dx.doi.org/10.1007/978-94-009-0103-2_41.

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Bustos-Sanmamed, Pilar, Carole Laffont, Florian Frugier, Christine Lelandais-Brière, and Martin Crespi. "Analyzing Small and Long RNAs in Plant Development Using Non-radioactive In Situ Hybridization." In Methods in Molecular Biology, 303–16. Totowa, NJ: Humana Press, 2012. http://dx.doi.org/10.1007/978-1-62703-221-6_20.

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Herrington, C. S., J. Burns, and J. O'D McGee. "Non-isotopic in situ hybridisation in human pathology." In In Situ Hybridisation, 241–70. Cambridge University Press, 1990. http://dx.doi.org/10.1017/cbo9780511629051.014.

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Coulton, Gary. "Non-radioisotopic labels for in situ hybridisation histochemistry: a histochemist's view." In In Situ Hybridisation, 1–32. Cambridge University Press, 1990. http://dx.doi.org/10.1017/cbo9780511629051.002.

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TANIMOTO, EUGENE Y., and THOMAS L. ROST. "Non-radioactive In Situ RNA Hybridisation Using Digoxigenin and an Application for Co-localisation Studies with Radioisotopes." In Methods in Plant Biochemistry, 141–58. Elsevier, 1993. http://dx.doi.org/10.1016/b978-0-12-461020-0.50013-5.

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Augood, S. J., E. M. McGowan, B. R. Finsen, B. Heppelmann, and P. C. Emson. "Non-radioactive in situ hybridization using alkaline phosphatase-labelled oligonucleotides." In International Review of Neurobiology, 173—IN5. Elsevier, 2002. http://dx.doi.org/10.1016/s0074-7742(02)47060-2.

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Wahle, P. "Combining non-radioactive in situ hybridization with immunohistological and anatomical techniques." In International Review of Neurobiology, 203–38. Elsevier, 2002. http://dx.doi.org/10.1016/s0074-7742(02)47061-4.

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Ariza-McNaughton, L., and R. Krumlauf. "Non-radioactive in situ hybridization: Simplified procedures for use in whole-mounts of mouse and chick embryos." In International Review of Neurobiology, 239–50. Elsevier, 2002. http://dx.doi.org/10.1016/s0074-7742(02)47062-6.

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Conference papers on the topic "Non-radioactive in situ hybridisation"

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Brown, Steven H. "Radiological Aspects of In Situ Uranium Recovery." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7379.

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In the last few years, there has been a significant increase in the demand for Uranium as historical inventories have been consumed and new reactor orders are being placed. Numerous mineralized properties around the world are being evaluated for Uranium recovery and new mining / milling projects are being evaluated and developed. Ore bodies which are considered uneconomical to mine by conventional methods such as tunneling or open pits, can be candidates for non-conventional recovery techniques, involving considerably less capital expenditure. Technologies such as Uranium in situ leaching in situ recovery (ISL / ISR), have enabled commercial scale mining and milling of relatively small ore pockets of lower grade, and may make a significant contribution to overall world wide uranium supplies over the next ten years. Commercial size solution mining production facilities have operated in the US since 1975. Solution mining involves the pumping of groundwater, fortified with oxidizing and complexing agents into an ore body, solubilizing the uranium in situ, and then pumping the solutions to the surface where they are fed to a processing plant. Processing involves ion exchange and may also include precipitation, drying or calcining and packaging operations depending on facility specifics. This paper presents an overview of the ISR process and the health physics monitoring programs developed at a number of commercial scale ISL / ISR Uranium recovery and production facillities as a result of the radiological character of these processes. Although many radiological aspects of the process are similar to that of conventional mills, conventional-type tailings as such are not generated. However, liquid and solid by product materials may be generated and impounded. The quantity and radiological character of these by products are related to facility specifics. Some special monitoring considerations are presented which are required due to the manner in which Radon gas is evolved in the process and the unique aspects of controlling solution flow patterns underground. An overview of the major aspects of the health physics and radiation protection programs that were developed at these facilities are discussed and contrasted to circumstances of the current generation and state of the art of Uranium ISR technologies and facilities.
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Simpson, Alan, Stephanie Jones, Martin Clapham, and Randy Lucero. "Portable Non-Destructive Assay Methods for Screening and Segregation of Radioactive Waste." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40255.

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Significant cost-savings and operational efficiency may be realised by performing rapid non-destructive classification of radioactive waste at or near its point of retrieval or generation. There is often a need to quickly categorize and segregate bulk containers (drums, crates etc.) into waste streams defined at various boundary levels (based on its radioactive hazard) in order to meet disposal regulations and consignor waste acceptance criteria. Recent improvements in gamma spectroscopy technologies have provided the capability to perform rapid in-situ analysis using portable and hand-held devices such as battery-operated medium and high resolution detectors including lanthanum halide and high purity germanium (HPGe). Instruments and technologies that were previously the domain of complex lab systems are now widely available as touch-screen “off-the-shelf” units. Despite such advances, the task of waste stream screening and segregation remains a complex exercise requiring a detailed understanding of programmatic requirements and, in particular, the capability to ensure data quality when operating in the field. This is particularly so when surveying historical waste drums and crates containing heterogeneous debris of unknown composition. The most widely used portable assay method is based upon far-field High Resolution Gamma Spectroscopy (HRGS) assay using HPGe detectors together with a well engineered deployment cart (such as the PSC TechniCART™ technology). Hand-held Sodium Iodide (NaI) detectors are often also deployed and may also be used to supplement the HPGe measurements in locating hot spots. Portable neutron slab monitors may also be utilised in cases where gamma measurements alone are not suitable. Several case histories are discussed at various sites where this equipment has been used for in-situ characterization of debris waste, sludge, soil, high activity waste, depleted and enriched uranium, heat source and weapons grade plutonium, fission products, activation products, americium, curium and other more exotic nuclides. The process of acquiring and analyzing data together with integration of historical knowledge to resolve and delineate waste streams (for example between low-level waste and transuranic waste) is described.
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Beyke, Gregory, and Gregory J. Smith. "Advances in the Application of In Situ Electrical Resistance Heating." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7136.

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Electrical Resistance Heating (ERH) is an aggressive in situ thermal remediation technology that was developed by the U.S. Department of Energy from the original oil production technology to enhance vapor extraction remediation technologies in low permeability soils. Soil and groundwater are heated by the passage of electrical current through saturated and unsaturated soil between electrodes, not by the electrodes themselves. It is the resistance to the flow of electrical current that results in increased subsurface temperatures, and this is typically applied to the boiling point of water. It is estimated that more than 75 ERH applications have been performed. Capacity to perform these projects has increased over the years, and as many as 15 to 20 of these applications now being performed at any given time, mainly in North America, with some European applications. While the main focus has been to vaporize volatile organic compounds, as one would expect other semi-volatile and non-volatile organic compounds have also been encountered, resulting in observations of chemical and physical reactions that have not been normally incorporated into environmental restoration projects. One such reaction is hydrolysis, which is slow under normal groundwater temperatures, becomes very rapid under temperatures that can easily be achieved using ERH. As a result, these chemical and physical reactions are increasing the applicability of ERH in environmental restoration projects, treating a wider variety of compounds and utilizing biotic and abiotic mechanisms to reduce energy costs. For the treatment of oil and coal tar residues from manufactured gas plants, a process TRS has called steam bubble floatation is used to physically remove the coal and oil tar from the soils for collection using conventional multi-phase collection methods. Heat-enhanced hydrolysis has been used to remediate dichloromethane from soils and groundwater at a site in Illinois, while heat-enhanced biotic and abiotic dehalogenation has been observed at the vast majority of the sites where ERH has been applied. With disposal options becoming more limited around the world, alternate in situ treatment methods for soil and groundwater restoration are becoming more important. Over the 10 years of commercialization of the ERH technology, soil and groundwater remediation mechanisms and processes that were not envisioned by the technology’s developers expand the range of chemicals that have successfully been treated. This paper will discuss these processes and how these processes have been used to effect remediation of soil and groundwater where ERH has been employed.
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Brown, S. H. "Design Improvements and ALARA at U.S. Uranium In Situ Recovery Facilities." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16415.

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In the last few years, there has been a significant increase in the demand for Uranium as historical inventories have been consumed and new reactor orders are being placed. Numerous mineralized properties around the world are being evaluated for Uranium recovery and new mining / milling projects are being evaluated and developed. Ore bodies which are considered uneconomical to mine by conventional methods such as tunneling or open pits, can be candidates for non-conventional recovery techniques, involving considerably less capital expenditure. Technologies such as Uranium In Situ Leaching / In Situ Recovery (ISL / ISR - also refered to as “solution mining”), have enabled commercial scale mining and milling of relatively small ore pockets of lower grade, and are expected to make a significant contribution to overall world wide uranium supplies over the next ten years. Commercial size solution mining production facilities have operated in the US since the mid 1970’s. However, current designs are expected to result in less radiological wastes and emissions relative to these “first” generation plants (which were designed, constructed and operated through the 1980s). These early designs typically used alkaline leach chemistries in situ including use of ammonium carbonate which resulted in groundwater restoration challenges, open to air recovery vessels and high temperature calcining systems for final product drying vs the “zero emmisions” vaccum dryers as typically used today. Improved containment, automation and instrumentation control and use of vacuum dryers in the design of current generation plants are expected to reduce production of secondary waste byproduct material, reduce Radon emisions and reduce potential for employee exposure to uranium concentrate aerosols at the back end of the milling process. In Situ Recovery in the U.S. typically involves the circulation of groundwater, fortified with oxidizing (gaseous oxygen e.g) and complexing agents (carbon dioxide, e.g) into an ore body, solubilizing the uranium in situ, and then pumping the solutions to the surface where they are fed to a processing plant (mill). Processing involves ion exchange and may also include precipitation, drying or calcining and packaging operations depending on facility specifics. This paper presents an overview of the ISR process and the health physics monitoring programs developed at a number of commercial scale ISL / ISR Uranium recovery and production facillities as a result of the radiological character of these processes. Although many radiological aspects of the process are similar to that of conventional mills, conventional-type tailings as such are not generated. However, liquid and solid byproduct materials may be generated and impounded. The quantity and radiological character of these by products are related to facility specifics. Some special monitoring considerations are presented which are required due to the manner in which radon gas is evolved in the process and the unique aspects of controlling solution flow patterns underground. The radiological character of these procesess are described using empirical data collected from many operating facilities. Additionally, the major aspects of the health physics and radiation protection programs that were developed at these first generation facilities are discussed and contrasted to circumstances of the current generation and state of the art of uranium ISR technologies and facilities.
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5

Bamberger, Judith A., and Margaret S. Greenwood. "Evolution of a Non-Invasive Sensor for Fluid Density and Solids Concentration Measurement Using Ultrasound." In ASME/JSME 2003 4th Joint Fluids Summer Engineering Conference. ASMEDC, 2003. http://dx.doi.org/10.1115/fedsm2003-45590.

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This paper describes the evolution of an ultrasonic sensor to non-invasively measure slurry density and solids concentration. Three generations of probe are discussed: 1) density sensor, 2) densimeter, and 3) fluid and solids monitor. The initial application was to measure slurry density during radioactive waste transport. The probe uses ultrasonic signal reflection at the fluid-pipe wall interface to quantify density in situ in real time and signal attenuation to evaluate solid concentration. In the latest configuration, the transducers are mounted on the wall of the pipe spool piece. This instrument was selected for monitoring radioactive waste transport based on several characteristic features: the sensing surface is non-intrusive and does not disrupt the slurry flow, instrument performance is not affected by slight amounts of entrained air that could be present during waste retrieval and transfer; nor is it affected by electromagnetic noise from nearby pumps and other equipment; and the instrument is compact. The densimeter has been deployed at Hanford tank SY-101 in the prefabricated pump pit process manifold to monitor slurry properties during radioactive waste transfers. To qualify densimeter performance prior to manifold installation in the radioactive pipeline, the probe was installed in the process manifold and performance was evaluated during tests using non-radioactive waste simulants over the density range from 1000 to 1500 kg/m3. The probe predicted density within ± 2%. The sensor is installed in a nominal 5-cm-diameter (2-in.) pipe spool piece; the design pressure is 2.8 MPa (400 psi). To ensure operability during prolonged contact with radioactive waste, the probe wedge in contact with the slurry was selected to operate up to pH 14, and the probe components were radiation tested at exposures of 1×106 R.
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6

Cross, Paul E., and Del Baird. "Phased Implementation of In Situ Chemical Oxidation for a Large TCE DNAPL Source Area at the Portsmouth Gaseous Diffusion Plant, USA." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7200.

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This paper describes the In Situ Chemical Oxidation (ISCO) remediation being implemented for the X-701B groundwater plume at the Department of Energy (DOE) Portsmouth Gaseous Diffusion Plant (PORTS). Modified Fenton’s reagent is the principal oxidant for the remedy, and Direct Push Technology (DPT) is being used for delivery of the oxidant. Trichloroethene (TCE) is the primary contaminant of concern and is present within the unit as a dense non-aqueous phase liquid (DNAPL). A phased approach is being implemented to optimize the type, location, and mass of the oxidant injections. During Phase I, a unique near-real time monitoring approach was utilized to observe the transient effects of the oxidant injections on the formation. As a result of the positive results from Phase I, Ohio EPA has approved the final work plan for the remedy, and the approach is now being applied to the source area of the plume. The results from Phase I and the layout for the first series of Phase II injections are presented in this paper. Previous testing at the site has shown that the shallow, water-bearing formation is primarily composed of silty gravel and clay, and is both heterogeneous and anisotropic. These factors have significantly compromised earlier attempts to remediate the unit. A patented ISCO process from In-Situ Oxidative Technologies, Inc. (ISOTEC) was selected for the remediation of the plume. Phase I results indicate that oxidant delivery via DPT is feasible for the unit. Contaminant reduction to date has been minimal due to the small quantity of oxidant injected during Phase I. Contaminant rebound in the aqueous phase remains a concern and will be monitored closely during the remedy.
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7

Boden, Sven, and Eric Cantrel. "Pre-Decommissioning Radiological Characterization of Concrete." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7044.

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The decommissioning of the BR3 (Belgian Reactor 3) approaches its final phase, in which the building structures are being decontaminated and either denuclearized for possible reuse or demolished. Apart from the presence of naturally occurring radionuclides in building materials, other radionuclides might be present due to contamination or activation. The overall process of the BR3 building structure D&D (Decontamination & Decommissioning) consists of the following steps: • make a complete inventory and preliminary categorize all elements based on historical data; • characterize and determine the contamination or activation depth; • determine the decontamination method; • perform the decontamination and clean up; • a possible intermediate characterization followed by an additional decontamination step; and • characterize for clearance. A good knowledge of the contamination and activation depth (second step) is fundamental in view of cost minimization. Currently, the method commonly used for the determination of the depth is based on core drilling and destructive analysis. Recently, we have introduced a complementary non destructive assay based on in-situ gamma spectroscopy. Field tests at BR3, both for contamination and activation, showed promising results.
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8

Barre´, Yves, and Vincent Pacary. "Study of the Radioactive Liquid Waste Treatment by Coprecipitation: From Modeling to New Process Designs." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16018.

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The ever increasing pressure to reduce the release of radioactive and other toxic substances into environment requires constant improvement/upgrading of processes and technologies for treatment and conditioning of liquid radioactive wastes. To decontaminate liquid nuclear wastes, the coprecipitation process is the most commonly used in nuclear field because it can be applied to any type of aqueous effluents whatever their composition may be. This process deals with the in situ precipitation of solid particles to selectively remove one or more radioelements. In the nuclear research center of CEA (Commissariat a` l’Energie Atomique), the coprecipitation of 90Sr with barium sulphate is the technique used to treat selectively this radionuclide. In a previous study (1), an elaborated model is presented which predicts the radioactive strontium decontamination factor of nuclear waste solutions which can be achieved by using a coprecipitation process with barium sulphate. The originality of this new approach lies in the possibility to simulate the decontamination process in non equilibrium conditions and at the reactor scale. This modelling combined with the resolution of the population balance, enables to identify the influence of process parameters (flow rates, stirring speed…) on crystal size and ultimately on decontamination. Simulations of the strontium coprecipitation with barium sulphate have been performed in continuous and semi batch reactors. Thanks to these simulations, laws of the treatment efficiency variation as a function of several process parameters (mean residence time, stirring speed, BaSO4 concentration) have been determined and experimentally verified. This study leads to the determination of optimal treatment conditions. Three apparatus (recycling apparatus, fluidised bed and reactor/settling tank) providing these optimal conditions have been successfully tested and offered significant outlooks for the reduction of the residual sludge volume.
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9

Venara, J., M. Ben Mosbah, C. Mahé, M. Masson, and J. L. Paul. "Radiological Characterization Methods Specifically Applied to the Preparation of the Dismantling of PHENIX Fast Reactor." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96061.

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Knowledge of the radiological state of processes and equipment of a nuclear facility is essential to supervise a wide variety of sensitive tasks: building of intervention scenarios in order to optimize maintenance or dismantling operations, optimization of waste categorization, monitoring the effectiveness of decontamination processes, monitoring of nuclear facility decommissioning, etc. In order to meet the diversity of the issues involved, the CEA has developed in situ radiological characterization methods and techniques to acquire reliable radiological data. The data gathered is necessary to build robust radiological models which can be used as input data for dismantling studies. Over the last 30 years, the main nuclear measurement techniques, such as gamma imaging and gamma spectrometry, have been widely deployed by the CEA on many facilities under dismantling and more recently, on the Phénix nuclear power plant. Phénix was a small-scale prototype of a sodium-cooled fast breeder reactor, located at the Marcoule nuclear site. These techniques have been implemented on this reactor in order to meet the increased need for radiological knowledge to prepare for future dismantling operations following its final shutdown in 2009. This paper will focus on the description of three radiological characterization methods which take advantage of advanced nuclear measurement techniques. For each method, an example of a specific application on the Phénix reactor will be presented. Firstly, the so-called “gamma scanning” method will be explained. The objective of this method is to determine the activity profile of equipment based on collimated gamma spectrometry measurements with compact probes like CdZnTe. This method was applied to a neutron shielding of the reactor core to estimate the 60Co activity profile. Then the measured activities helped to validate the theoretical activities resulting from neutron activation calculations. Secondly, this paper will focus on the interest of combining different measurement techniques such as gamma imaging, gamma spectrometry and collimated/uncollimated dose rate mapping to characterize complex equipment or processes. In this case, a specific methodology was developed to define the radiological state of a shielded cell used for the processing of irradiated nuclear fuels. Finally, an isotopic characterization technique using a high purity germanium detector will be discussed. This technique was applied to a non-irradiated fertile fuel sub-assembly in order to determine the level of uranium enrichment. The processing was carried out by three types of analysis: two automated, with the MGA-U and IGA software, and one manual.
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10

Bel, Johan, and Fréderic Bernier. "Temperature Criterion Related to Clay Based Backfill Materials in the Framework of a Geological Repository of Heat Producing Radioactive Waste (HLW)." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1239.

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Abstract The objective of this paper is to define a criterion for the maximum temperature allowed within clay based backfill materials, used as engineered barriers, in the framework of a geological repository of heat emitting radioactive waste. This criterion applies to all candidate geological formations in Belgium (non-indurated clay). According to the current Belgian reference repository for vitrified High Level Waste (HLW), waste packages will be disposed in deep geological clay formations after a cooling period of about 50 years in surface storage facilities. The heat release of this waste has a important impact on the design of the different components of the disposal system. The temperature increase and the possible effects of this increase will have to be considered on different locations (e.g. disposal galleries, backfill, lining, host rock, aquifer, and biosphere). In this paper, we will focus mainly on the temperature increase in the backfill material of the galleries. In the past the temperature in the host rock (Boom Clay) was limited to 100°C. Consequently, higher temperatures (above 100°C) were allowed in the components between the waste and the host rock. During the preparation of the in situ demonstration project PRACLAY, a new more stringent criterion for the limitation of the temperature in the backfill has been proposed, namely the limitation of the temperature in the backfill to 100°C. The different scientific and technical reasons for the use of this lower temperature design criterion are described in this paper. Phenomena like steam generation, mineral transformations and thermally induced, coupled effects can be reduced or avoided at lower temperatures. Another important advantage is the reduction of the corrosion rate of metal components (e.g. overpack). Finally, problems of a more technical nature (difficulty of characterization of materials, uncertainty in modeling and problems with instrumentations) can also be avoided by the use of this new criterion. Thermal calculations point out that this new criterion can be met by respecting a cooling time, for the present repository design of vitrified HLW, of 60 years instead of 50 years. We can conclude that the application of this lower temperature criterion provides better predictability of coupled effects and increases the performance, lifetime and robustness of the different barriers of the repository and of the disposal system as a whole.
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