High-Temperature Deformation During Continental-Margin Subduction & Exhumation: The Ultrahigh-Pressure Western Gneiss Region of Norway

A new dataset for the high-pressure to ultrahigh-pressure Western Gneiss Region allows the definition of distinct structural and petrological domains. Much of the study area is an E-dipping homocline with E-plunging lineations that exposes progressively deeper, more strongly deformed, more eclogite-rich structural levels westward. Although eclogites crop out across the WGR, Scandian deformation is weak and earlier structures are well preserved in the southeastern half of the study area. The Scandian reworking increases westward, culminating in strong Scandian fabrics with only isolated pockets of older structures; the dominant Scandian deformation was coaxial E–W stretching. The sinistrally sheared Møre–Trøndelag Fault Complex and Nordfjord Mylonitic Shear Zone bound these rocks to the north and south. There was moderate top-E, amphibolite-facies deformation associated with translation of the allochthons over the basement along its eastern edge, and the Nordfjord–Sogn Detachment Zone underwent strong lower amphibolite-facies to greenschist-facies top-W shearing. A northwestward increase in exhumation-related melting is indicated by leucosomes with hornblende, plagioclase, and Scandian sphene. In the western 2/3 of the study area, exhumation-related, amphibolite-facies symplectite formation in quartzofeldspathic gneiss postdated most Scandian deformation; further deformation was restricted to slip along biotite-rich foliation planes and minor local folding. That the Western Gneiss Region quartzofeldspathic gneiss exhibits a strong gradient in degree of deformation, implies that continental crust in general need not undergo pervasive deformation during subduction

Aspects of the Fundamental Chemistry of Cesium Extraction from Acidic Media by HCCD

The unique extraction properties of univalent polyhedral borate anions, are well known and have been extensively studied over the past three decades. This is particularly true of the hexachlorinated derivative of the chloro-protected cobalt bis(dicarbollide) anion [(8, 9, 12-Cl3-C2B9H8)2-3-Co]-, (CCD-), typically in the acid form (HCCD) and dissolved in a suitably polar diluent, such as nitrobenzene, which is known to have a high affinity for selective extraction of the Cs+ cation. Recent collaborations between Russian and USA researchers expanded the use of HCCD in the Universal Extraction (UNEX) process where Cs, Sr, actinides (An) and lanthanides (Ln) are all extracted simultaneously by incorporating a neutral extractant (specifically diphenyl-N,N-di-n-butylcarbamoylmethyl phosphine oxide, CMPO) with HCCD and PEG-400 in the organic diluent phenyl trifluoromethyl sulfone (FS-13). In recent efforts to understand the complicated and unique synergistic chemical phenomena associated with simultaneous radionuclide (Cs, Sr, An, Ln) in the UNEX process, additional insight into Cs extraction by the HCCD system has been obtained. Four data sets with 25 experimental measurements of Cs distribution ratios, DCs [Cs]org/[Cs]aq, at a variety of initial conditions (various [HCCD] and [HNO3]) have been modeled using the SXLSQI computer program developed at ORNL. The SXLSQI program was used in this analysis to help elucidate the general chemical equilibria operative in the extraction of Cs+ into an organic phase comprised of HCCD in FS-13. The experimental data is best modeled with the following (simplified) chemical equilibria and the associated equilibrium constants (T = 25°C): (1) (2) (3) Where the over bar represents species formed in the organic phase. The equilibrium constant for the primary exchange reaction (1) of log Keq = 3.07 is in excellent agreement with values reported in the literature of log K = 3.00 for the dicarbollide/ nitrobenzene system. In general, the equilibria representing the mechanism of Cs extraction by HCCD is consistent with earlier works reported in the literature, albeit derived by different experimental and modeling schemes. The details of the experimental and modeling efforts are summarized in this work

Factors associated with Condom Use Problems during Vaginal Sex with main and non-main partners

Incorrect condom use is a common problem that can undermine their prevention impact. We assessed the prevalence of 2 condom use problems, breakage/slippage and partial use, compared problems by partnership type, and examined associations with respondent, partner, and partnership characteristics

Determination of the dead time of a stopped-flow fluorometer

This investigation was carried out to develop a convenient alternative method for examining the performance and determining the dead time of a stopped-flow fluorometer. We examined the kinetics for the formation of the fluorescent Mg2+-8-hydroxyquinoline chelate in aqueous solutions. The reversible association of the Mg2+ ion with 8-hydroxyquinoline is a second-order process whose on and off rate constants are dependent on pH. We estimated that the Mg2+ ion chelate has a fluorescence quantum yield of 0.02 in aqueous solutions. Using this reaction we measured the dead time of a stopped-flow fluorometer at different pH values. Measurements of the dead time were found to be reproducible and accurate. The Mg2+-8-hydroxyquinoline reaction fulfills the requirements for a convenient test reaction for dead time measurement of stopped-flow fluorometers. Although the usefulness of the reaction is primarily to determine the dead times of stopped-flow instruments operating in the fluorescence mode, the reaction can also be used for testing an instrument operating in the absorbance mode.Peer Reviewedhttp://deepblue.lib.umich.edu/bitstream/2027.42/27776/1/0000170.pd

Development of Technologies for the Simultaneous Separation of Cesium and Strontium from Spent Nuclear Fuel as Part of an Advanced Fuel Cycle

As part of the Advanced Fuel Cycle Initiative, two solvent extraction technologies are being developed to simultaneously separate cesium and strontium from dissolved spent nuclear fuel. The first process utilizes a solvent consisting of chlorinated cobalt dicarbollide and polyethylene glycol extractants in a phenyltrifluoromethyl sulfone diluent. Recent improvements to the process include development of a new, non-nitroaromatic diluent and development of new stripping reagents, including a regenerable strip reagent that can be recovered and recycled. Countercurrent flowsheets have been designed and tested on simulated and actual spent nuclear fuel feed streams with both cesium and strontium removal efficiencies of greater than 99 %. The second process developed to simultaneously separate cesium and strontium from spent nuclear fuel is based on two highly-specific extractants: 4,4',(5')-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) and Calix[4]arene-bis-(tert-octylbenzo-crown-6) (BOBCalixC6). The DtBuCH18C6 extractant is selective for strontium and the BOBCalixC6 extractant is selective for cesium. A solvent composition has been developed that enables both elements to be removed together and, in fact, a synergistic effect was observed with strontium distributions in the combined solvent that are much higher that in the strontium extraction (SREX) process. Initial laboratory test results of the new combined cesium and strontium extraction process indicate good extraction and stripping performance. A flowsheet for treatment of spent nuclear fuel is currently being developed

ADVANCED TECHNOLOGIES FOR THE SIMULTANEOUS SEPARATION OF CESIUM AND STRONTIUM FROM SPENT NUCLEAR FUEL

Two new solvent extraction technologies have been recently developed to simultaneously separate cesium and strontium from spent nuclear fuel, following dissolution in nitric acid. The first process utilizes a solvent consisting of chlorinated cobalt dicarbollide and polyethylene glycol extractants in a phenyltrifluoromethyl sulfone diluent. Recent improvements to the process include development of a new, non-nitroaromatic diluent and development of new stripping reagents, including a regenerable strip reagent that can be recovered and recycled. This new strip reagent reduces product volume by a factor of 20, over the baseline process. Countercurrent flowsheet tests on simulated spent nuclear fuel feed streams have been performed with both cesium and strontium removal efficiencies of greater than 99 %. The second process developed to simultaneously separate cesium and strontium from spent nuclear fuel is based on two highly-specific extractants: 4',4',(5')-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) and Calix[4]arene-bis-(tert-octylbenzo-crown-6) (BOBCalixC6). The DtBuCH18C6 extractant is selective for strontium and the BOBCalixC6 extractant is selective for cesium. A solvent composition has been developed that enables both elements to be removed together and, in fact, a synergistic effect was observed with strontium distributions in the combined solvent that are much higher that in the strontium extraction (SREX) process. Initial laboratory test results of the new combined cesium and strontium extraction process indicate good extraction and stripping performance

Reflections From Engaging a Network of Local Stakeholders in Discussing Training Needs for Sustainable Renovation

Sustainable renovation of buildings is essential to create comfortable, affordable buildings fit for the future. Sustainable renovation delivers on a triple bottom line of improving environmental, social and economic impacts. There is a clear policy driver for reducing environmental impact in the form of carbon emissions and alongside achieving this homes and communities can become more comfortable places to live, creating jobs and economic value. The purpose of this paper is to share reflections from stakeholder engagement in identifying workforce training requirements and needs to achieve sustainable renovation. The paper stems from data collected in an exploratory workshop and follow up discussions gathering multiple construction stakeholders in Leeds, United Kingdom, early 2018. Participants represented a networked system of roles including policy influencers, procurement staff, training providers, employers and skilled professionals. These stakeholders identified two areas of training need for sustainable renovation: building performance and social value. Within these two themes, we consider potential training routes in delivery as well as incentives and opportunities. We hope this reflection offers a platform for further research, training and practice in developing environmental, social and economic benefits from building renovation

Development of Cesium and Strontium Separation and Immobilization Technologies in Support of an Advanced Nuclear Fuel Cycle

As part of the Advanced Fuel Cycle Initiative, two solvent extraction technologies are being developed at the Idaho National Laboratory to simultaneously separate cesium and strontium from dissolved spent nuclear fuel. The chlorinated cobalt dicarbollide/polyethylene glycol (CCD/PEG) process utilizes a solvent consisting of chlorinated cobalt dicarbollide for the extraction of Cs and polyethylene glycol for the synergistic extraction of Sr in a phenyltrifluoromethyl sulfone diluent. Countercurrent flowsheets have been designed and tested on simulated and actual spent nuclear fuel feed streams with both cesium and strontium removal efficiencies of greater than 99%. The Fission Product Extraction (FPEX) process is based on two highly-specific extractants: 4,4',(5')-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) for the extraction of Sr and Calix[4]arene-bis-(tert-octylbenzo-crown-6) (BOBCalixC6) for the extraction of Cs. Laboratory test results of the FPEX process, using simulated feed solution spiked with radiotracers, indicate good Cs and Sr extraction and stripping performance. A preliminary solvent extraction flowsheet for the treatment of spent nuclear fuel with the FPEX process has been developed, and testing of the flowsheet with simulated spent nuclear fuel solutions is planned in the near future. Steam reforming is currently being developed for stabilization of the Cs/Sr product stream because it can produce a solid waste form while retaining the Cs and Sr in the solid, destroy the nitrates and organics present in these aqueous solutions, and convert the Cs and Sr into leach resistant aluminosilicate minerals. A bench-scale steam reforming pilot plant has been operated with several potential feed compositions and steam reformed product has been generated and analyzed

LENDA, a Low Energy Neutron Detector Array for experiments with radioactive beams in inverse kinematics

The Low Energy Neutron Detector Array (LENDA) is a neutron time-of-flight (TOF) spectrometer developed at the National Superconducting Cyclotron Lab- oratory (NSCL) for use in inverse kinematics experiments with rare isotope beams. Its design has been motivated by the need to study the spin-isospin response of unstable nuclei using (p, n) charge-exchange reactions at intermediate energies (> 100 MeV/u). It can be used, however, for any reaction study that involves emission of low energy neutrons (150 keV - 10 MeV). The array consists of 24 plastic scintillator bars and is capable of registering the recoiling neutron energy and angle with high detection efficiency. The neutron energy is determined by the time-of-flight technique, while the position of interaction is deduced using the timing and energy information from the two photomultipliers of each bar. A simple test setup utilizing radioactive sources has been used to characterize the array. Results of test measurements are compared with simulations. A neutron energy threshold of < 150 keV, an intrinsic time (position) resolution of \sim 400 ps (\sim 6 cm) and an efficiency > 20 % for neutrons below 4 MeV have been obtained.Comment: Version accepted for publication in Nucl. Instr. Methods A. Revised text, 2 new figures added (one in section 4 and one in section 7