bluuebunny/crossref_metadata_2025_split huggingface dataset:
Patients’ and providers’ perceptions of the impact of health literacy on communication in pulmonary rehabilitation
Authors: Sadeghi Shiva , Brooks Dina , Goldstein Roger S 
Published: January 2013

Chronic obstructive pulmonary disease (COPD) is the most prevalent form of chronic respiratory diseases worldwide. Pulmonary rehabilitation, including self-management education, highlights the importance of good patient–provider communication in establishing optimal care. There is a growing awareness of the potential impact of health literacy (HL) on the patients’ access to and understanding of medical information. This study was designed to explore the patients’ and health care professionals’ (HCPs) perceptions of the role of HL in health communication. Semi-structured interviews and focus groups were conducted with 12 patients and 20 HCPs at a Pulmonary Rehabilitation Center in Metropolitan Toronto. Although the term health literacy was not familiar to many patients, the contribution of knowledge to patient well-being was consistently identified by patients and HCPs. Barriers to communication included provider time constraints and the use of medical jargon. For providers they also included patient characteristics, language, culture and awareness of health resources. Approaches that might improve communication incorporated family support, peer support, better print and visual teaching material and a trusting empathic patient–provider relationship. The findings provide an increased understanding of patients’ and providers’ perceptions of HL as a barrier to effective communication of medical information to patients with COPD as well as approaches that might improve this communication.
Durability of potential plutonium wasteforms under repository conditions
Authors: Deissmann G. , Neumeier S. , Modolo G. , Bosbach D. 
Published: January 2013

AbstractSeparated stocks of UK civil plutonium are currently held as a zero value asset in storage, as there is no final decision about whether they should be treated as a resource for future use as nuclear fuel or as waste. Irrespective of future UK government strategies regarding plutonium, at least a portion of the UK civil plutonium inventory will be designated for geological disposal. In this context, we performed a high-level review of the performance of potential wasteforms for the disposal of separated civil plutonium. The key issues considered were the durability and chemical reactivity of the wasteforms in aqueous environments and the long-term radionuclide release under conditions relevant to geological disposal. The major findings of the review, relevant not only to the situation in the UK but to plutonium disposal in general, are summarized in this paper. The review showed that, in the event of a decision being taken to declare plutonium as a waste for disposal, more systematic studies would be required to constrain the wasteform performance under repository conditions in order to derive realistic source terms for a safety case.
Development of nuclear criticality safety controls on intermediate-level waste packages
Authors: Hicks T. W. , Wood P. , Putley D. , Baldwin T. D. 
Published: January 2013

AbstractIntermediate-level wastes (ILW) include substantial quantities of fissile material and controls are required to ensure that its storage, transport and disposal does not present a nuclear criticality hazard. This paper describes the Radioactive Waste Management Directorate's research to develop package fissile material limits (in the form of screening levels) for four different categories of ILW, defined according to uranium or plutonium composition: (1) irradiated natural and slightly enriched uranium (uranium containing up to 1.9 wt.% 235U); (2) low-enriched uranium (uranium containing up to 4 wt.% 235U); (3) high-enriched uranium (uranium containing up to 100 wt.% 235U); and (4) separated plutonium (plutonium containing up to 100 wt.% 239Pu).The derivation of package screening levels was supported by neutron transport calculations that addressed conditions during waste package transport to a geological disposal facility (GDF), during the GDF operational phase and after GDF closure. The analysis included consideration of combinations of events and processes that could result in fissile material accumulation and concentration after GDF closure, when waste packages have deteriorated sufficiently for fissile material to be mobilized. The results of the calculations have provided input to Radioactive Waste Management Directorate's decision making on setting waste package screening levels.
Experimental study to evaluate the effect of polymeric encapsulants on the corrosion resistance of intermediate-level radioactive waste packages
Authors: Winsley R. J. , Smart N. R. , Padovani C. 
Published: January 2013

AbstractIntermediate-level radioactive waste is normally encapsulated in cementitious grout. However, for some wastes, grout may not be suitable and polymeric encapsulants are being considered as an alternative. One concern with such encapsulants is their long-term chemical stability and the possibility that release of aggressive degradation products could cause corrosion.This paper evaluates the potential for three polymeric encapsulants: two epoxy resins (the APS polymer system, (APS) and Alchemix 4760 (ALC)) and a vinyl-ester styrene (VES); to cause internal corrosion of stainless steel waste containers. The corrosion behaviour of stainless steel 316L in contact with each encapsulant was studied in saturated Ca(OH)2 solutions and deionized (DI) water, at 80°C, under non-irradiated and γ-irradiated conditions.In aerated, alkaline conditions, 316L was resistant to corrosion in all the conditions tested. However, in DI water, the pH fell to values as low as three due to release of acidic species from the polymers. The two epoxy materials (particularly APS) also released significant levels of chloride; VES did not. Chloride release appeared to be increased by γ-irradiation. As a result of the low pH chloride-containing environment created by the APS encapsulant, 316L experienced localized corrosion, whereas coupons in Alchemix 4760 and VES did not. Weight loss measurements correlated with visual observations. γ-irradiation appeared to increase the degree of corrosion.
Deep borehole disposal of higher burn up spent nuclear fuels
Authors: Gibb F. G. F. , Travis K. P. , Hesketh K. W. 
Published: January 2013

AbstractThe heat outputs of higher burn up spent fuels (SF) create problems for disposal in mined repositories, including needs for reduced container loadings and extended pre-disposal cooling. An alternative that is less temperature sensitive is deep borehole disposal (DBD) which offers safety, cost, security and other potential benefits and could be implemented relatively quickly using currently available deep-drilling technology. We have modified our previously proposed version of DBD to be more appropriate for higher burn-up fuels by using smaller (0.36 m diameter) stainless steel containers, a smaller (0.56 m diameter) borehole, and different support matrices. We present the results of new heat-flow modelling for DBD of UO2 and MOX SF with burn ups of 55 and 65 GWd/t showing how temperatures evolve, especially on the outer surface of the containers. Consequences for the performance of the support matrices and the disposal concept are discussed. The thermal modelling indicates DBD is a viable option for higher burn-up SF and could be a practical disposal route for many combinations of fuel types, burn ups, ages and container loadings. Further, the results suggest that DBD of complete fuel assemblies, a desirable option, would be feasible and require much shorter pre-disposal cooling than necessary for disposal in mined repositories.
The role of stress history on the flow of fluids through fractures
Authors: Sathar S. , Reeves H. J. , Cuss R. J. , Harrington J. F. 
Published: January 2013

AbstractUnderstanding flow along fractures and faults is of importance to the performance assessment (PA) of a geological disposal facility (GDF) for radioactive waste. Flow can occur along pre-existing fractures in the host-rock or along fractures created during the construction of the GDF within the excavation damage zone (EDZ). The complex fracture network will have a range of orientations and will exist within a complex stress regime. Critical stress theory suggests that fractures close to localized shear failure are critically stressed and therefore most conductive to fluid flow. Analysis of fault geometry and stress conditions at Sellafield has revealed that no features were found to be, or even close to being, classified as critically stressed, despite some being conductive. In order to understand the underlying reasons why non-critically stressed fractures were conductive a series of laboratory experiments were performed. A bespoke angled shear rig (ASR) was built in order to study the relationship between fluid flow (water and gas) through a fracture surface as a function of normal load. Fluid flow reduced with an increase in normal load, as expected. During unloading considerable hysteresis was seen in flow and shear stress. Fracture flow was only partially recovered for water injection, whereas gas flow increased remarkably during unloading. The ratio of shear stress to normal stress seems to control the fluid flow properties during the unloading stage of the experiment demonstrating its significance in fracture flow. The exhumation of the Sellafield area during the Palaeogene–Neogene resulted in considerable stress relaxation and in fractures becoming non-critically stressed. The hysteresis in shear stress during uplift has resulted in faults remaining, or becoming, conductive. The field and laboratory observations illustrate that understanding the stress-history of a fractured rock mass is essential, and a mere understanding of the current stress regime is insufficient to estimate the flow characteristics of present-day fractures.
Adsorption and diffusion of strontium in simulated rock fractures quantified via ion beam analysis
Authors: Ohe T. , Zou B. , Noshita K. , Gomez-Morilla I. , Jeynes C. , Morris P. M. , Wogelius R. A. 
Published: January 2013

AbstractAn experimental technique has been developed and applied to the problem of determining effective diffusion coefficients and partition coefficients of Sr in low permeability geological materials. This technique, the micro-reactor simulated channel method (MRSC), allows rapid determination of contaminant transport parameters with resulting values comparable to those determined by more traditional methods and also creates product surfaces that are amenable for direct chemical analysis. An attempt to further constrain mass flux was completed by detailed ion beam analysis of polished tuff surfaces (tuff is a polycrystalline polyminerallic aggregate dominated by silicate phases) that had been reacted with Sr solutions at concentrations of 10−5, 10−3 and 10−1 mol l−1. Ion beam analysis was carried out using beams of both protons (using particle induced X-ray emission and elastic backscattering spectrometry or EBS) and alpha-particles (using Rutherford backscattering spectrometry). The ion beam analyses showed that increased solution concentrations resulted in increased surface concentrations and that in the highest concentration experiment, Sr penetrated to at least 4 μm below the primary interface. The Sr surface concentrations determined by EBS were 0.06 (±0.05), 0.87 (±0.30) and 2.40 (±1.0) atomic weight % in the experiments with starting solution concentrations of 10−5, 10−3, and 10−1 mol l−1, respectively.
Biosphere studies supporting the disposal system safety case in the UK
Authors: Walke R. C. , Thorne M. C. , Norris S. 
Published: January 2013

AbstractHigher activity radioactive wastes remain hazardous for extremely long timescales, of up to hundreds of thousands of years. Disposing of such wastes deep underground presents the internationally accepted best solution for isolating them from the surface environment on associated timescales. Geological disposal programmes need to assess potential releases from such facilities on long timescales to inform siting and design decisions and to help build confidence that they will provide an adequate degree of safety. Assessments of geological disposal include consideration of the wastes, the engineered facility, the host geology and the surface and near-surface environment including the biosphere. This paper presents an overview of recent post-closure biosphere assessment studies undertaken in support of the Nuclear Decommissioning Authority Radioactive Waste Management Directorate disposal system safety case for geological disposal of the United Kingdom's higher activity radioactive wastes. Recent biosphere studies have included: (1) ensuring that the United Kingdom's approach to consideration of the biosphere in safety case studies continues to be fit for purpose, irrespective of which site or sites are considered in the United Kingdom's geological disposal programme; (2) updating projections of global climate and sea level, together with consideration of the potential importance of transitions between climate states; (3) considering geosphere–biosphere interface issues and their representation, including redox modelling and catchment-scale hydrological modelling; and (4) identifying key radionuclides and developing a series of reports describing their behaviour in the biosphere together with an evaluation of associated implications for post-closure assessment calculations.
Evidence for gas-induced pathways in clay using a nanoparticle injection technique
Authors: Harrington J. F. , Milodowski A. E. , Graham C. C. , Rushton J. C. , Cuss R. J. 
Published: January 2013

AbstractCorrosion, water radiolysis and microbial degradation will result in the generation of gas within repositories designed for the geological disposal of high-level radioactive waste. It is therefore crucial in the design of such facilities that the relevant mechanisms allowing gas migration through repository materials, both engineered barriers and clay-based candidate host rocks, are correctly identified. In Belgium, the Boom Clay represents a candidate host material for which the advective gas breakthrough characteristics and transport properties have been extensively tested and are well defined by numerous studies. The Boom Clay displays a significant capacity for self-sealing and both laboratory and field tests indicate that advective gas transport occurs not by visco-capillary flow, but instead through the formation of pressure-induced dilatant pathways. In this study, we present results from a gas injection test designed to demonstrate the presence of these features by injecting nanoparticulate tracers with helium gas into a sample of Boom Clay. The results provide conclusive evidence for the formation of transient, dilatant gas pathways within a candidate clay-based host rock. This technique provides a novel diagnostic tool for the identification of processes governing multi-phase flow, supporting robust long-term assessments of repository performance.
Multicomponent gas flow through compacted clay buffer in a higher activity radioactive waste geological disposal facility
Authors: Masum S. A. , Vardon P. J. , Thomas H. R. , Chen Q. , Nicholson D. 
Published: January 2013

AbstractAt the post-closure stage of a geological disposal facility for higher activity radioactive waste several species of gas are likely to be generated in the near-field environment. These could alter the sealing and chemical properties of the bentonite buffer and the local geochemical environment significantly. The authors' attempt to simulate multicomponent gas flow through variably saturated porous media is presented. Governing equations have been developed for a reactive gas-flow model to simulate the thermo-hydro-gas-chemical-mechanical behaviour, with specific reference to the performance of highly compacted bentonite buffer subjected to repository gas generation and migration. The developed equations have been included in the bespoke numerical model COMPASS and some generic simulations are also presented. The model presented extends current capability to assess buffer performance.
Towards an 'implementing geological disposal technology platform' in Europe
Authors: Palmu M. , Eng T. , Beattie T. M. 
Published: January 2013

AbstractSeveral European waste management organizations have started work on creating a technology platform to accelerate the implementation of deep geological disposal of radioactive waste in Europe. There is an increasing consensus in the international community about geological disposal as the preferred option for solving the long-term management of spent fuel, high-level waste and other longlived radioactive wastes. At the same time, European citizens have a widespread desire for a permanent solution for high-level radioactive waste disposal. A majority of European countries with nuclear power have active waste-management programmes, but the current status and the main challenges of those programmes vary. The most advanced waste management programmes in Europe (i.e. those in Sweden, Finland and France) are prepared to start the licensing process of deep geological disposal facilities within the next decade. Despite the differences between the timing and the challenges of the different programmes, there is a joint awareness that cooperation on the scientific, technical and social challenges related to geological disposal is needed, and that it is beneficial for the timely and safe implementation of the first geological disposal facilities. Such a demonstration of a viable solution for the management of high-level radioactive waste will enhance stakeholder confidence in Europe. It is envisaged that a technology platform would enhance European cooperation in this area. The platform will provide a tool for reducing overlapping work, to produce savings in total costs of research and implementation, and to make better use of existing competence and research infrastructures. From 2008, SKB (Sweden) and Posiva (Finland) led the preparation work to set up the implementing geological disposal of radioactive waste technology platform (IGD-TP). Since then other implementers from France, Germany, Switzerland, United Kingdom, Spain and Belgium have joined the project. To date a strategic research agenda for the platform has been prepared and consulted upon, which is now the basis for taking the platform into a deployment phase.
Geological disposal programme design and prioritization in the face of uncertainty: use of structured evidence support logic techniques
Authors: Paulley A. , Metcalfe R. , Egan M. 
Published: January 2013

AbstractProgrammes for the geological disposal of radioactive wastes are by nature extremely complex. A structured approach for making and documenting varied kinds of decisions is required to support programme design and implementation. At each programme stage, the decision-making process must be able to identify and justify key priorities for work, to reduce uncertainties.To support structured decision-making evidence support logic (ESL) has been developed and applied to varied complex projects, nationally and internationally, in several industries. Evidence support logic involves breaking down a hypothesis that informs a decision into a hierarchical 'decision tree'. Examples of hypotheses are 'the geology associated with site x will provide sufficient disposal capacity', 'container x will contain waste form y for z years' and 'the engineered barrier system will provide the required safety functions'. Independent evaluations of confidence 'for' and 'against' bottom-level hypotheses allow the level of remaining uncertainty (or conflict) to be recognized explicitly, and the overall confidence (and uncertainty) relevant to the overall decision, and key sensitivities, to be represented clearly and succinctly.Thus ESL can help (1) break down decisions into a manageable and logical structure, assisting clear presentation; (2) identify key uncertainties and sensitivities to inform prioritization; and (3) test whether the outcomes of specific studies have improved confidence.
Cooperating gene mutations in childhood acute myeloid leukemia with special reference on mutations of ASXL1, TET2, IDH1, IDH2, and DNMT3A
Authors: Liang Der-Cherng , Liu Hsi-Che , Yang Chao-Ping , Jaing Tang-Her , Hung Iou-Jih , Yeh Ting-Chi , Chen Shih-Hsiang , Hou Jen-Yin , Huang Ying-Jung , Shih Yu-Shu , Huang Yu-Hui , Lin Tung-Huei , Shih Lee-Yung 
Published: January 2013

Key Points
A comprehensive study of 19 gene mutations and their cooperation, including the first report of ASXL1 and TET2 mutations in pediatric AML. The development of pediatric AML requires fewer gene mutations than adult AML.
Differential control of Helios+/− Treg development by monocyte subsets through disparate inflammatory cytokines
Authors: Zhong Hui , Yazdanbakhsh Karina 
Published: January 2013

Key PointsControl of Helios+/− Treg subset development is mediated through distinct cytokines and monocyte subpopulations. CD16+ monocytes inhibit Helios+ Treg proliferation through IL-12, whereas CD16− monocytes suppress Helios− Treg development through TNF-α.
Robo4 is an effective tumor endothelial marker for antibody-drug conjugates based on the rapid isolation of the anti-Robo4 cell-internalizing antibody
Authors: Yoshikawa Mai , Mukai Yohei , Okada Yoshiaki , Tsumori Yuki , Tsunoda Shin-ichi , Tsutsumi Yasuo , Aird William C. , Yoshioka Yasuo , Okada Naoki , Doi Takefumi , Nakagawa Shinsaku 
Published: January 2013

Key PointsFirst therapeutic application that targets Robo4 on the tumor blood vasculature High-throughput screening system to isolate cell-internalizing monoclonal antibodies useful to develop effective antibody-drug conjugates
Genome-wide identification, characterization, and expression analysis of lineage-specific genes within zebrafish
Authors: Yang Liandong , Zou Ming , Fu Beide , He Shunping 
Published: January 2013

Abstract

Background
The genomic basis of teleost phenotypic complexity remains obscure, despite increasing availability of genome and transcriptome sequence data. Fish-specific genome duplication cannot provide sufficient explanation for the morphological complexity of teleosts, considering the relatively large number of extinct basal ray-finned fishes.

Results
In this study, we performed comparative genomic analysis to discover the Conserved Teleost-Specific Genes (CTSGs) and orphan genes within zebrafish and found that these two sets of lineage-specific genes may have played important roles during zebrafish embryogenesis. Lineage-specific genes within zebrafish share many of the characteristics of their counterparts in other species: shorter length, fewer exon numbers, higher GC content, and fewer of them have transcript support. Chromosomal location analysis indicated that neither the CTSGs nor the orphan genes were distributed evenly in the chromosomes of zebrafish. The significant enrichment of immunity proteins in CTSGs annotated by gene ontology (GO) or predicted ab initio may imply that defense against pathogens may be an important reason for the diversification of teleosts. The evolutionary origin of the lineage-specific genes was determined and a very high percentage of lineage-specific genes were generated via gene duplications. The temporal and spatial expression profile of lineage-specific genes obtained by expressed sequence tags (EST) and RNA-seq data revealed two novel properties: in addition to being highly tissue-preferred expression, lineage-specific genes are also highly temporally restricted, namely they are expressed in narrower time windows than evolutionarily conserved genes and are specifically enriched in later-stage embryos and early larval stages.

Conclusions
Our study provides the first systematic identification of two different sets of lineage-specific genes within zebrafish and provides valuable information leading towards a better understanding of the molecular mechanisms of the genomic basis of teleost phenotypic complexity for future studies.