•A comparative study of demulsification by microwave and oil bath heating.•Results were confirmed by steady state fluorescence spectrometry.•The effect of a demulsifier on the oil-in-water (O/W) ...emulsion stability was studied.•The effect of salt content on the O/W emulsion stability was evaluated.
Oil-in-water (O/W) emulsions are an innovate manner by which otherwise highly viscous heavy and extra-heavy crude oils can be transported from producing sites to transforming sites through pipelines. In spite of the important reduction in viscosity and pressure drops, water must be removed from the crude oil before further process or refining. Hence, the present study discusses the demulsification of an O/W emulsion prepared with Mexican heavy crude oil. A comparative study was carried out between microwave and oil bath heating with regard to water separation time. The effect of a chemical demulsifier and salt content of the O/W emulsion’s aqueous phase was also investigated. Microwave dielectric heating of O/W emulsions showed a greater degree of water separation in less time than conventional oil bath heating. Water separation of O/W emulsions increased with microwave power and salt content of the aqueous phase, and in the presence of a chemical demulsifier. Finally, the fluorescence emission spectra of the initial and treated O/W emulsions were in agreement with the water separation results and provide a quick and effective way to study the demulsification processes.
Full text
Available for:
GEOZS, IJS, IMTLJ, KILJ, KISLJ, NUK, OILJ, PNG, SAZU, SBCE, SBJE, UL, UM, UPCLJ, UPUK
•A Beam Dump shielding has been devised, designed, analyzed, manufactured and tested.•Radiological, structural, commissioning and dimensional requirements are described.•Mechanical design and ...analysis of the Beam Dump Shielding is described.•Manufacturing process of the Beam Dump Shielding is described.•Inspections and final acceptance tests have been performed and successfully passed.
The International Fusion Materials Irradiation Facility (IFMIF) aims to provide an accelerator-based, D-Li neutron source to produce high energy neutrons at enough intensity and irradiation volume for DEMO materials qualification. As part of the Broader Approach (BA) agreement between Japan and EURATOM, the goal of the IFMIF/EVEDA project is to work on the engineering design of IFMIF and to validate the main technological challenges which, among a wide diversity of hardware includes the LIPAc (Linear IFMIF Prototype Accelerator), a 125 mA continuous wave deuteron accelerator up to 9 MeV mainly designed and manufactured in Europe.
The beam is stopped in a copper cone involving a high production of neutron and gamma radiation and activation of its surface. A shield has been designed to attenuate both the radiation produced during accelerator operation and the residual radiation. This shield is made of an inner layer of polyethylene to moderate neutrons and an outer layer of iron to attenuate gammas produced by deuteron interactions with Cu but also those generated by neutrons in the polyethylene.
The present work summarizes the upgraded design of the shielding, as well as its upgraded mechanical analysis following the ASME Boiler and Pressure Vessel Code Division VIII Section 2. It also shows the manufacturing processes and requirements imposed on the shielding along with the acceptance tests performed and the lessons learned.
Full text
Available for:
GEOZS, IJS, IMTLJ, KILJ, KISLJ, NUK, OILJ, PNG, SAZU, SBCE, SBJE, UL, UM, UPCLJ, UPUK, ZRSKP
El 2021 fue un año de cambios y de retos en Chile, producto de un nuevo marco político gestado, entre otras razones, por las protestas de 2019. Conforme al Plebiscito Nacional de 2020 y por motivos ...de la pandemia, flagelo que ha ocasionado varias postergaciones electorales, se definió un calendario contentivo de todos los cargos de elección popular, a saber: elecciones subnacionales (gobernadores regionales, alcaldes y concejales), junto con la Convención Constitucional, así como la segunda vuelta para los gobernadores regionales, primarias presidenciales oficiales, “primarias presidenciales convencionales” (no organizadas por el Servicio Electoral, máximo órgano electoral administrativo) y, para cerrar, elecciones nacionales: presidente de la República, renovación parcial de senadores, diputados al Congreso y consejeros regionales, con una eventual segunda vuelta presidencial. No queda duda, en virtud de los eventos realizados, de la fortaleza institucional electoral y de la cultura política en Chile; no obstante, son varias las materias que pudieran evaluarse, tales como: actualización del registro electoral, financiamiento electoral, reelección, regulación de encuestas electorales, y políticas de acción afirmativas por género y otros grupos. Una mayor autonomía del ente administrativo electoral y la necesidad de formalizar la observación electoral pudieran ser claves para esta revisión.
Treating systemic inflammation caused by SARS-COV 2 (COVID-19) has become a challenge for the clinician. Corticosteroids have been the turning point in the treatment of this disease. Preliminary data ...from Recovery clinical trial raises hope by showing that treatment with dexamethasone at doses of 6mg/day shows a reduction on morbidity in patients requiring added oxygen therapy. However, both the start day or what kind of corticosteroid, are still questions to be clarified. Since the pandemic beginning, we have observed large differences in the type of corticosteroid, dose and initiation of treatment. Our objective is to assess the predictive capacity of the characteristics of patients treated with methylprednisolone pulses to predict hospital discharge.
We presented a one-center observational study of a retrospective cohort. We included all patients admitted between 03/06/2020 and 05/15/2020 because of COVID-19. We have a total number of 1469 patients, of whom 322 received pulses of methylprednisolone. Previous analytical, radiographic, previous disease data were analyzed on these patients. The univariant analysis was performed using Chi-squared and the T test of Student according to the qualitative or quantitative nature of the variables respectively. For multivariate analysis, we have used binary logistic regression and ROC curves.
The analysis resulted statistically significant in dyspnea, high blood pressure, dyslipidemia, stroke, ischemic heart disease, cognitive impairment, solid tumor, C-reactive protein (CRP), lymphopenia and d-dimer within 5 days of admission. Radiological progression and FIO
input are factors that are associated with a worst prognosis in COVID-19 that receive pulses of methylprednisolone. Multivariate analysis shows that age, dyspnea and C-reactive protein are markers of hospital discharge with an area below the curve of 0.816.
In patients with methylprednisolone pulses, the capacity of the predictive model for hospital discharge including variables collected at 5 days was (area under the curve) 0.816.
A new concept of stability of materials is introduced by defining the optimum hot forming temperature for any given strain rate. This temperature is obtained through forming maps that are based on ...Lyapunov concepts and the introduction of a Garofalo equation in the Lyapunov criterion. This new approach is applied to a magnesium alloy AZ61. Torsion tests were carried out in the temperature range 574-734 K and strain rate range 0.7-8.7 s
−1
and the microstructures were determined using optical microscopy. Using the peak stress, optimum workability at 630 K is obtained at 12 s
−1
. The results and the maps are compared with data and maps of other authors for AZ61 alloys in various states.
Full text
Available for:
DOBA, IZUM, KILJ, NUK, PILJ, PNG, SAZU, UILJ, UKNU, UL, UM, UPUK
IFMIF-DONES is a facility under construction in Granada, whose main goal is the validation and characterization of materials under a fusion prototypic irradiation field. This field is created by the ...interaction of a high energy intense continuous deuteron beam and a flowing liquid lithium target. The requirements imposed on the beam at the interaction point are a complex trade-off among the scientific experimental needs for the materials irradiation defined at the top-level requirements (20 dpa in a volume of 0.3 dm3 and 50 dpa in 0.1 dm3), and the technical constraints of several systems such as the Accelerator Systems, the Lithium Systems, and the Test Systems. Recent simulations with the initial definition of beam-on-target requirements showed the necessity of redefining them in order to fulfill the irradiation needs. This contribution will address the main challenges to gather the inputs for the definition and reassessment of the beam-on-target requirements. A comparison detailing the main changes compared to the previous ones will be given, together with a short overview of the studies ongoing by different systems to analyze the impact of each beam-on-target requirements on the performance of the whole facility.
•Fusion materials irradiation.•Deuteron accelerator.•High current accelerator.•Beam delivery system.•Beam on-target.
Full text
Available for:
GEOZS, IJS, IMTLJ, KILJ, KISLJ, NLZOH, NUK, OILJ, PNG, SAZU, SBCE, SBJE, UILJ, UL, UM, UPCLJ, UPUK, ZAGLJ, ZRSKP
•Design, integration and manufacturing of MEBT and DPlate frames are presented.•Solutions to fulfill structural, seismic and alignment requirements are explained.•Beam dynamics requirements and ...compactness make the design an engineering challenge.•Lessons learned will be implemented in future facilities.
The International Fusion Materials Irradiation Facility (IFMIF) 1 aims to provide an accelerator-based, D-Li neutron source to produce high energy neutrons at sufficient intensity and irradiation volume for DEMO materials qualification. As part of the Broader Approach (BA) agreement between Japan and EURATOM, the goal of the IFMIF/EVEDA project is to work on the engineering design of IFMIF and to validate the main technological challenges which, among a wide diversity of hardware includes the LIPAc (Linear IFMIF Prototype Accelerator) 2, a 125mA continuous wave deuteron accelerator up to 9MeV mainly designed and manufactured in Europe.
The Medium Energy Beam Transport line (MEBT) 3,4 is in charge of the beam transport at 5 MeV/125mA and matching beam parameters between two acceleration structures, the RadioFrequency Quadrupole (RFQ) and the Superconducting RF linear accelerator (SRF Linac), while the Diagnostic Plate (DPlate) 5 is a movable module with a set of diagnostics and instrumentations in charge of characterizing the beam in the different accelerator commissioning stages (RFQ commissioning, SRF Linac commissioning) and to provide accelerator operational parameters. Both beamline designs are state of art, being a real engineering (and mechanical) challenge, due to the compactness and alignment requirements from beam dynamics, and the seismic requirements from the accelerator site. An optimized design is critical in order to reduce beam losses and production of radiation at high power beam.
The present paper summarizes the mechanical design and analysis of the MEBT and Diagnostic Plate support frames, as well as their manufacturing solutions and mechanical integration with the components installed both in the MEBT and Diagnostic Plate. The mechanical design and integration show the engineering development, adopted to fulfill the strict structural, seismic and alignment requirements.
Full text
Available for:
GEOZS, IJS, IMTLJ, KILJ, KISLJ, NUK, OILJ, PNG, SAZU, SBCE, SBJE, UL, UM, UPCLJ, UPUK, ZRSKP
The Water Cooled Lithium Lead (WCLL) blanket is one of the four breeder blanket technologies under consideration within the framework of the EUROfusion Consortium activities. The aim of this work is ...to develop a preliminary model that can track tritium concentration and tritium fluxes along each part of the WCLL blanket and its ancillary systems at any time.
Because of tritium's nature, the phenomena of diffusion, dissociation, recombination and solubilization have been taken into account when describing the tritium behavior inside the lead-lithium channels, the structural materials and the water coolant circuits. The simulations have been performed using the object oriented modeling software EcosimPro.
Results have been obtained for the pulsed generation scenario of the European demonstration power plant (DEMO). The tritium inventory in every part of the blanket has been computed. Permeation rates have been calculated as well allowing to know how much tritium ends up in the coolant system and how much remains in the liquid metal. The amount of tritium extracted from the lead-lithium loop has been also obtained. All this information allows having a global perspective of tritium behavior all over the blanket at any time.
The model provides valuable information for the design of the WCLL blanket. More complex upgrades are planned to be implemented based on this model in future stages of the EUROfusion project.
Full text
Available for:
BFBNIB, GIS, IJS, KISLJ, NUK, PNG, UL, UM, UPUK
The key system to know the neutron and gamma fields during the commissioning at IFMIF-DONES facility will be the STart-Up Monitoring Module (STUMM), which will include tens of very sophisticated and ...miniaturised detectors providing crucial information about the radiation fields. In particular, there will be MFCs (micro-fission chambers), ICs (Ionisation Chambers), SPNDs (Self-Powered Neutron Devices) and GTs (Gamma Thermometers).
The current state-of-the-art does not provide answers about the performance of the detectors in the very specific working conditions inside the IFMIF-DONES Test Cell, as a very high spatial density of detectors inside the STUMM vessel, an extremely harsh environment with neutron flux up to 5·1014n/cm2/s and the need of long mineral cables (>30 m) to drive the very weak current signals from the irradiation area to the closest electronics cubicles available in the facility.
Except for the extremely high neutron flux provided by IFMIF-DONES, all the other very critical conditions can be replicated by means of a 1:1 scaled prototype of the STUMM (STUMM-PROTO), which will be subjected to comprehensive testing and irradiation campaigns in order to increase the knowledge about the performance of the detectors above mentioned.
The present work shows the wide range of capabilities offered by STUMM-PROTO as well as the current status of its construction and some first notions about the experimental campaigns to be implemented.
Full text
Available for:
GEOZS, IJS, IMTLJ, KILJ, KISLJ, NLZOH, NUK, OILJ, PNG, SAZU, SBCE, SBJE, UILJ, UL, UM, UPCLJ, UPUK, ZAGLJ, ZRSKP
10.
The LIPAc beam dump Brañas, Beatriz; Arranz, Fernando; Nomen, Oriol ...
Fusion engineering and design,
02/2018, Volume:
127
Journal Article
Peer reviewed
•The complete design of the Beam dump for the LIPAc (1 MW 9 MeV continuous deuteron accelerator) is presented.•The beam stopping piece is a water cooled copper cone with a 6.8° angle and 2.5 ...length.•The neutron production and activation caused by the beam-copper interaction determines many of the design features.
The International Fusion Materials Irradiation Facility (IFMIF) aims to provide an accelerator-based, D-Li neutron source to produce high energy neutrons at sufficient intensity and irradiation volume for fusion materials qualification. The LIPAc is a 125 mA 9 MeV continuous wave deuteron accelerator whose components are under construction mainly in Europe, which is being installed in Rokkasho (Japan) with the purpose of validating the IFMIF accelerator design.
The beam generated by the LIPAc accelerator will be stopped by a copper cone (2.5 m long, 6.8° angle), cooled by water flowing at high velocity along its outer surface. This piece is surrounded by a shield made of iron and low Z materials for attenuating the neutron and gamma radiation originated by the interaction of the deuterons with the copper. It incorporates dedicated diagnostics for beam dump monitoring: accelerometers for detection of localized heating due to incorrect alignment of the beam and ionization chambers, which ensure that the deuteron beam footprint remains within the beam dump design limits.
A lead shutter has been designed to be inserted in the beam tube during beam-off periods to stop the gamma radiation from the activated copper cone escaping through the beam tube, allowing access inside the accelerator vault. The junction of the beam dump to the beam tube has a special design to allow its remote disconnection, enabling the end of life decommissioning operations of the facility. The design and material selection of the beam dump and neighboring elements are driven by a maintenance-free requirement after a short period of operations, as the cartridge activation precludes any maintenance activities in the beam dump and neighboring elements downstream the lead shutter.
This paper describes the design and manufacturing of the beam dump and related elements explaining the interrelations between them and the reasons behind their main features.
Full text
Available for:
GEOZS, IJS, IMTLJ, KILJ, KISLJ, NUK, OILJ, PNG, SAZU, SBCE, SBJE, UL, UM, UPCLJ, UPUK, ZRSKP
PDF
