bluuebunny/crossref_metadata_2025_split huggingface dataset:
Development of Evaluation Models of Manpower Needs for Dismantling the Dry Conversion Process-Related Equipment in Uranium Refining and Conversion Plant (URCP)
Authors: Izumo Sari , Usui Hideo , Tachibana Mitsuo , Morimoto Yasuyuki , Takahashi Nobuo , Tokuyasu Takashi , Tanaka Yoshio , Sugitsue Noritake 
Published: February 2014

Evaluation models for determining the manpower needs for dismantling various types of equipment in uranium refining and conversion plant (URCP) have been developed. The models are widely applicable to other uranium handling facilities. Additionally, a simplified model was developed for easily and accurately calculating the manpower needs for dismantling dry conversion process–related equipment (DP equipment).
It is important to evaluate beforehand project management data such as manpower needs to prepare an optimized decommissioning plan and implement effective dismantling activity. The Japan Atomic Energy Agency (JAEA) has developed the project management data evaluation system for dismantling activities (PRODIA code), which can generate project management data using evaluation models. For preparing an optimized decommissioning plan, these evaluation models should be established based on the type of nuclear facility and actual dismantling data.
In URCP, the dry conversion process of reprocessed uranium and others was operated until 1999, and the equipment related to the main process was dismantled from 2008 to 2011. Actual data such as manpower for dismantling were collected during the dismantling activities, and evaluation models were developed using the collected actual data on the basis of equipment classification considering the characteristics of uranium handling facility.
Radiological Issues Associated With the Recent Boom in Oil and Gas Hydraulic Fracturing
Authors: Lopez Alejandro 
Published: February 2014

As the worldwide hydraulic fracturing ‘fracking’ market continued to grow to an estimated $37 Billion in 2012, the need to understand and manage radiological issues associated with fracking is becoming imperative. Fracking is a technique that injects pressurized fluid into rock layer to propagate fractures that allows natural gas and other petroleum products to be more easily extracted. Radioactivity is associated with fracking in two ways. Radioactive tracers are frequently a component of the injection fluid used to determine the injection profile and locations of fractures. Second, because there are naturally-occurring radioactive materials (NORM) in the media surrounding and containing oil and gas deposits, the process of fracking can dislodge radioactive materials and transport them to the surface in the wastewater and gases.
Treatment of the wastewater to remove heavy metals and other contaminates can concentrate the NORM into technologically-enhanced NORM (TENORM). Regulations to classify, transport, and dispose of the TENORM and other radioactive waste can be complicated and cumbersome and vary widely in the international community and even between states/provinces. In many cases, regulations on NORM and TENORM do not even exist. Public scrutiny and regulator pressure will only continue to increase as the world demands on oil and gas continue to rise and greater quantities of TENORM materials are produced. Industry experts, health physicists, regulators, and public communities must work together to understand and manage radiological issues to ensure reasonable and effective regulations protective of the public, environment, and worker safety and health are implemented.
Westinghouse Modular Grinding Process: Improvement for Follow on Processes
Authors: Fehrmann Henning 
Published: February 2014

In nuclear power plants (NPP) ion exchange (IX) resins are used in several systems for water treatment. The resins can be in bead or powdered form.
For waste treatment of spent IX resins, two methods are basically used:
• Direct immobilization (e.g. with cement, bitumen, polymer or High Integrity Container (HIC))
• Thermal treatment (e.g. drying, oxidation or pyrolysis)
Bead resins have some properties (e.g. particle size and density) that can have negative impacts on following waste treatment processes. Negative impacts could be:
• Floatation of bead resins in cementation process
• Sedimentation in pipeline during transportation
• Poor compaction properties for Hot Resin Supercompaction (HRSC)
Reducing the particle size of the bead resins can have beneficial effects enhancing further treatment processes and overcoming prior mentioned effects.
Westinghouse Electric Company has developed a modular grinding process to crush/grind the bead resins. This modular process is designed for flexible use and enables a selective adjustment of particle size to tailor the grinding system to the customer needs.
The system can be equipped with a crusher integrated in the process tank and if necessary a colloid mill. The crusher reduces the bead resins particle size and converts the bead resins to a pump able suspension with lower sedimentation properties. With the colloid mill the resins can be ground to a powder.
Compared to existing grinding systems this equipment is designed to minimize radiation exposure of the worker during operation and maintenance.
Using the crushed and/or ground bead resins has several beneficial effects like facilitating cementation process and recipe development, enhancing oxidation of resins, improving the Hot Resin Supercompaction volume reduction performance.
Characterization of Radioactive Wastes With Respect to Harmful Materials
Authors: Kugel Karin , Brennecke Peter , Steyer Stefan , Gruendler Detlef , Boetsch Wilma , Haider Claudia 
Published: February 2014

In addendum 4 to the license of the German KONRAD repository, which considers mainly radiological aspects, a water law permit was issued in order to prevent the pollution of the near-surface groundwater. The water law permit stipulates limitations for 10 radionuclides and 2 groups of radionuclides as well as mass limitations for 94 substances and materials relevant for water protection issues. Two collateral clauses, i.e. additional requirements imposed by the licensing authority, include demands on the monitoring, registering and balancing of non-radioactive harmful substances and materials /1/.
In order to fulfill the requirements of the water law permit the German Federal Office for Radiation Protection (BfS) being the operator of the KONRAD repository has developed a concept, which ensures the compliance with all requirements of the water law permit and which provides standardized easy manageable guidance for the waste producers to describe their wastes.
On 15 March 2011 the competent water authority, the “Niedersaechsischer Landesbetrieb fuer Wasserwirtschaft, Kuesten- und Naturschutz” (NLWKN) issued the approval for this concept. Being the most essential part of this concept the procedural method and the developed description of non-radioactive waste package constituents by use of standardized lists of materials and containers is addressed and presented in this paper.
The waste producer has to describe his waste package in a standardized way on the base of the lists of materials and containers. For each material in the list a comprehensive description is given comprising the composition, scope of application, quality control measures, thresholds and other data. Each entry in the list has to be approved by NLWKN. The scope of the lists is defined by the waste producers’ needs. Using some particular materials as examples, the approval procedure for including materials in the list is described.
The procedure of describing the material composition has to be considered in the KONRAD waste acceptance requirements. The respective part of these requirements will be introduced.
In order to clarify the procedure of describing waste packages by use of the standardized lists of materials and containers some examples of typical waste package descriptions will be presented.
The Analysis of Metal Melting Application in the Management of Metallic Radioactive Materials Arising From Decommissioning of Nuclear Installations
Authors: Slimak Andrej , Necas Vladimir 
Published: February 2014

Basic characterization of the waste management process during decommissioning of nuclear installations is described in the presented paper. A brief description is given of conditional and unconditional release of materials into the environment. The paper deals also with metal melting as prospective decontamination technique which can significantly reduce metallic radioactive waste.
The material and radioactivity flow in the decommissioning process should be followed using the integrated material flow tool that is implemented into the standardized analytical decommissioning parameters calculation code OMEGA. Applying the integrated material flow tool, it is possible to monitor radiological and physical properties of individual material items listed in the nuclear installation input database, from dismantling up to their release into the environment or disposal in repository.
Using the OMEGA code and two model databases, several scenarios related to metal melting are evaluated. The impact of applying different input decommissioning parameters on the metal distribution is the main result discussed in the paper.
The Perspective Awareness Model: Eliciting Multiple Perspectives to Formulate High Quality Decisions
Authors: Boucher Laurel 
Published: February 2014

A great deal of attention is given to the importance of communication in environmental remediation and radioactive waste management. However, very little attention is given to eliciting multiple perspectives so as to formulate high quality decisions. Plans that are based on a limited number of perspectives tend to be narrowly focused whereas those that are based on a wide variety of perspectives tend to be comprehensive, higher quality, and more apt to be put into application. In addition, existing methods of dialogue have built-in limitations in that they typically draw from the predominant thinking patterns which focus in some areas but ignore others. This can result in clarity but a lack of comprehensiveness.
This paper presents a Perspective Awareness Model which helps groups such as partnering teams, interagency teams, steering committees, and working groups elicit a wide net of perspectives and viewpoints. The paper begins by describing five factors that makes cooperation among such groups challenging. Next, a Perspective Awareness Model that makes it possible to manage these five factors is presented. The two primary components of this model — the eight “Thinking Directions” and the “Shared Documentation” — are described in detail. Several examples are given to illustrate how the Perspective Awareness Model can be used to elicit multiple perspectives to formulate high quality decisions in the area of environmental remediation and radioactive waste management.
The Large Scale In-Situ PRACLAY Heater and Seal Tests in URL HADES, Mol, Belgium
Authors: Li Xiangling , Chen Guangjing , Verstricht Jan , Van Marcke Philippe , Troullinos Ioannis 
Published: February 2014

In Belgium, the URL HADES was constructed in the Boom Clay formation at the Mol site to investigate the feasibility of geological disposal in a clay formation. Since 1995, the URL R&D programme has focused on large scale demonstration tests like the PRACLAY Heater and Seal tests.
The main objective of the Heater Test is to demonstrate that the thermal load generated by the heat-emitting waste will not jeopardise the safety functions of the host rock.
The primary objective of the Seal Test is to provide suitable hydraulic boundary conditions for the Heater Test. The Seal Test also provides an opportunity to investigate the in-situ behaviour of a bentonite-based EBS.
The PRACLAY gallery was constructed in 2007 and the hydraulic seal was installed in 2010. The bentonite is hydrated both naturally and artificially. The swelling, total pressure and pore pressure of the bentonite are continuously measured and analysed by numerical simulations to get a better understanding of this hydration processes.
The timing of switching on the heater depends on the progress of the bentonite hydration, as a sufficient seal swelling is needed to fulfill its role. A set of conditions to be met for the heater switch-on and its schedule will be given.
Development and Testing of Techniques for In-Ground Stabilization, Size Reduction, and Safe Removal of Radioactive Wastes Stored in Containments Buried in Ground
Authors: Halliwell Stephen , Christodoulou Apostolos 
Published: February 2014

Since the 1950’s radioactive wastes from a number of laboratories have been stored below ground at the Hanford site, Washington State, USA, in vertical pipe units (VPUs) made of five 200 litre drums without tops or bottoms, and in caissons, made out of corrugated pipe, or concrete and typically 2,500mm in diameter. The VPU’s are buried of the order of 2,100mm below grade, and the caissons are buried of the order of 6,000mm below grade.
The waste contains fuel pieces, fission products, and a range of chemicals used in the laboratory processes. This can include various energetic reactants such as un-reacted sodium potassium (NaK), potassium superoxide (KO2), and picric acid, as well as quantities of other liquids. The integrity of the containments is considered to present unacceptable risks from leakage of radioactivity to the environment.
This paper describes the successful development and full scale testing of in-ground augering equipment, grouting systems and removal equipment for remediation and removal of the VPUs, and the initial development work to test the utilization of the same basic augering and grouting techniques for the stabilization, size reduction and removal of caissons.
Optimised Management of Orphan Wastes in the UK
Authors: Doudou Slimane , McTeer Jennifer , Wickham Stephen , Thied Rob , Woodcock Richard , Turner Tom , Hamblin Clive , Buckley Matthew , Walsh Ciara 
Published: February 2014

Orphan wastes have properties preventing them from being managed according to existing or currently planned management routes, or lack characterisation so that their management is uncertain. The identification of new management opportunities for orphan wastes could realise significant benefits by reducing the number of processing facilities required, reducing waste volumes, reducing hazard or leading to the development of centres of excellence for the processing of certain types of orphan wastes.
Information on the characteristics of orphan waste existing at nuclear licensed sites across the UK has been collated and a database developed to act as a repository for the information gathered. The database provides a capability to analyse the data and to explore possible treatment technologies for each orphan waste type. Thirty five distinct orphan waste types have been defined and possible treatment options considered. Treatment technologies (including chemical, high temperature, immobilisation and physical technologies) that could be applied to one or more of the generic orphan waste streams have been identified. Wiring diagrams have been used to highlight the waste treatment / lifecycle management options that are available for each of the generic orphan groups as well as identifying areas for further research and development.
This work has identified the potential for optimising the management of orphan wastes in a number of areas, and many potential opportunities were identified. Such opportunities could be investigated by waste managers at waste producing nuclear sites, to facilitate the development of new management routes for orphan wastes.
Key Differentiators Influencing the Choice of Robust Shielded Containers
Authors: Morris Jenny , Wickham Stephen , Nicholls David , Walsh Ciara , McKinney James 
Published: February 2014

The NDA’s Upstream Optioneering project has examined the potential implications of using an alternative type of waste package and its influence on the waste management lifecycle across the NDA estate.
Robust Shielded Containers (RSCs) are radioactive waste packages that provide integral radiological shielding, reducing the need for remote handling. The robustness of the container could remove the need to immobilise waste by cement encapsulation. RSCs are routinely used to package ILW for interim storage in Germany and have fairly recently been considered for use in the UK because RSCs have the potential to simplify the waste management lifecycle and enable risk and hazard reduction. In particular, the current baseline (included in Magnox Limited lifetime plans) follows the strategy set out in the Magnox Operating Decommissioning Programme (MODP), in which Type II MOSAIK and Type VI Ductile Cast Iron Containers (DCICs) are used to package (in non-encapsulated form) most Magnox ILW arising prior to 2050.
By considering representative types of Intermediate Level Waste (ILW) and exploring potential packaging options for these wastes, this paper identifies the factors that could differentiate between cases in which RSCs would, or would not, be an appropriate option. The potential role of RSCs across the waste management lifecycle is examined, from retrieval of waste through to emplacement at a Geological Disposal Facility (GDF), including consideration of other potential uses of RSCs, such as temporary storage of raw wastes for which appropriate treatment and conditioning measures have yet to be developed.
Current Status and Performance Assessment for the Techa Cascade of Reservoirs: Liquid Radioactive Waste Storage Facility
Authors: Linge Igor I. , Utkin Sergey S. , Mokrov Yury G. , Drozhko Evgeny G. 
Published: February 2014

The Techa cascade of water reservoirs is the world’s largest open storage facility for liquid low-level radioactive waste. Its capacity is about 360 mln. m3, it occupies an area of more than 65 km2, the total activity accumulated in the water and sediments is about 6·1015 Bq. The major challenge facing the Techa cascade is virtually uncontrollable water level changes. The water level rise can cause significant pollution of the environment. From the late 1990’s onwards, the issue of the Techa cascade safety assurance is considered to be one of the major challenges pertaining to nuclear legacy for «Mayak» and Russia as a whole. Unlike other industrial water reservoirs the Techa cascade liquidation is estimated as highly unrealistic. The main objectives of the paper are:
– brief results summary of the practical works on safety improvement at the Techa cascade carried out over the past decade;
– introduction the works on the Techa cascade performance assessment;
– determination of the existing risks and strategic areas for solving the problem.
Barriers to Delivering Extracurricular School Sport and Physical Activity in Wales: A Qualitative Study of 5x60 Officers’ Views and Perspectives
Authors: Rainer Paul , Griffiths Robert , Cropley Brendan , Jarvis Stuart 
Published: February 2014

Background:In light of recent reports, schools must be realistic in that physical activity recommendations cannot be met through curriculum PE alone. However, extracurricular PE and school sport has the potential to further promote physical activity in adolescents. Consequently, the Welsh Government, UK, proposed through its Climbing Higher strategy (2006) for secondary school children to achieve 60 minutes of physical activity a day. This was implemented through Sport Wales and the 5×60 scheme.Method:This study aimed to examine the experiences of the 5×60 officers responsible for implementing the program, with a view to gain an understanding of the barriers associated with increasing participation in physical activity. Officers from 14 unitary authorities across Wales were interviewed using a socioecological approach that considered the impact of: personal behaviors, physical environment, social environment, and policy.Results:Participants reported a number of challenges affecting the delivery of the program, including: availability of facilities, lack of support from senior management, time, and conflict with PE staff.Conclusion:This study suggests that current methods used by personnel to facilitate extracurricular school sport may not be the most appropriate, and future direction should consider the place and contribution of physical activity to young people’s lives.
Exposure Analysis Methods Impact Associations Between Maternal Physical Activity and Cesarean Delivery
Authors: Bovbjerg Marit L. , Siega-Riz Anna Maria , Evenson Kelly R. , Goodnight William 
Published: February 2014

Background:Previous studies report conflicting results regarding a possible association between maternal physical activity (PA) and cesarean delivery.Methods:Seven-day PA recalls were collected by telephone from pregnant women (n = 1205) from North Carolina, without prior cesarean, during 2 time windows: 17 to 22 weeks and 27 to 30 weeks completed gestation. PA was treated as a continuous, nonlinear variable in binomial regressions (log-link function); models controlled for primiparity, maternal contraindications to exercise, preeclampsia, pregravid BMI, and percent poverty. We examined both total PA and moderate-tovigorous PA (MVPA) at each time. Outcomes data came from medical records.Results:The dose-response curves between PA or MVPA and cesarean risk at 17 to 22 weeks followed an inverse J-shape, but at 27 to 30 weeks the curves reversed and were J-shaped. However, only (total) PA at 27 to 30 weeks was strongly associated with cesarean risk; this association was attenuated when women reporting large volumes of PA (> 97.5 percentile) were excluded.Conclusion:We did not find evidence of an association between physical activity and cesarean birth. We did, however, find evidence that associations between PA and risk of cesarean may be nonlinear and dependent on gestational age at time of exposure, limiting the accuracy of analyses that collapse maternal PA into categories.
How Do Different Occupational Factors Influence Total, Occupational, and Leisure-Time Physical Activity?
Authors: Vandelanotte Corneel , Short Camille , Rockloff Matthew , Millia Lee Di , Ronan Kevin , Happell Brenda , Duncan Mitch J. 
Published: February 2014

Background:A better understanding of how occupational indicators influence physical activity levels will aid the design of workplace interventions.Methods:Cross-sectional data were collected from 1194 participants through a telephone interview in Queensland, Australia. The IPAQ-long was used to measure physical activity. Multiple logistic regression was applied to examine associations.Results:Of participants, 77.9% were employed full-time, 32.3% had professional jobs, 35.7% were engaged in shift work, 39.5% had physically-demanding jobs, and 66.1% had high physical activity levels. Participants with a physicallydemanding job were less likely to have low total (OR = 0.25, 95% CI = 0.17 to 0.38) and occupational (OR = 0.17, 95% CI = 0.12 to 0.25) physical activity. Technical and trade workers were less likely to report low total physical activity (OR = 0.44, 95% CI = 0.20 to 0.97) compared with white-collar workers. Part-time (OR = 1.74, 95% CI = 1.15 to 2.64) and shift workers (OR = 1.86, 95% CI = 1.21 to 2.88) were more likely to report low leisure-time activity.Conclusions:Overall, the impact of different occupational indicators on physical activity was not strong. As expected, the greatest proportion of total physical activity was derived from occupational physical activity. No evidence was found for compensation effects whereby physically-demanding occupations lead to less leisure-time physical activity or vice versa. This study demonstrates that workplaces are important settings to intervene, and that there is scope to increase leisure-time physical activity irrespective of occupational background.