Fahn Tolosa Marin Tremor Rating Scale Pdf Acrobat

Background Efficacy in previous studies of surgical treatments of refractory multiple sclerosis tremor using lesioning or deep brain stimulation (DBS) has been variable. The aim of this study was to investigate the safety and efficacy of dual-lead thalamic DBS (one targeting the ventralis intermedius–ventralis oralis posterior nucleus border the VIM lead and one targeting the ventralis oralis anterior–ventralis oralis posterior border the VO lead) for the treatment of multiple sclerosis tremor. Methods We did a single centre, single-blind, prospective, randomised pilot trial at the University of Florida Center for Movement Disorders and Neurorestoration clinic (Gainesville, FL, USA). We recruited adult patients with a clinical diagnosis of multiple sclerosis tremor refractory to previous medical therapy. Before surgery to implant both leads, we randomly assigned patients (1:1) to receive 3 months of optimised single-lead DBS—either VIM or VO. We did the randomisation with a computer-generated sequence, using three blocks of four patients, and independent members of the Center did the assignment. Patients and all clinicians other than the DBS programming nurse were masked to the choice of lead.

• Fahn Tolosa Marin Tremor Rating Scale Pdf Acrobat Reader

Patients underwent surgery 1 month after their baseline visit for implantation of the dual lead DBS system. A pulse generator and two extension cables were implanted in a second surgery 3–4 weeks later. Patients then received an initial 3-month period of continuous stimulation of either the VIM or VO lead followed by blinded safety assessment of their tremor with the Tolosa-Fahn-Marin Tremor Rating Scale (TRS) during optimised VIM or VO lead stimulation at the end of the 3 months. After this visit, both leads were activated in all patients for an additional 3 months, and optimally programmed during serial visits as dictated by a prespecified programming algorithm. At the 6-month follow-up visit, TRS score was measured, and mood and psychological batteries were administered under four stimulation conditions: VIM on, VO on, both on, and both off (the order of testing was chosen by a computer-generated random sequence, assigned by independent members of the centre, and enacted by an unmasked DBS programming nurse).

Each of four stimulation settings were tested over 4 consecutive days, with stimulation settings held constant for at least 12 h before testing. The primary outcome was change in mean total TRS score at the 6-month postoperative assessment with both leads activated, compared with the preoperative baseline mean TRS score. Analysis was by intention to treat.

Safety was analysed in all patients who received the surgical implantation except in one patient who discontinued before the safety assessment. This trial is registered with, number. Findings Between Jan 16, 2007, and Dec 17, 2013, we enrolled 12 patients who were randomly assigned either to 3 initial months of VIM-only or VO-only stimulation. One patient from the VO-only group developed an infection necessitating DBS explantation, and was excluded from the assessment of the primary outcome. Compared with the mean baseline TRS score of 570 (SD 102), the mean score at 6 months decreased to 401 (176), −296% reduction; t=–028, p=003.

Three of 11 patients did not respond to surgical intervention. One patient died suddenly 2 years after surgery, but this was judged to be unrelated to DBS implantation. Serious adverse events included a superficial wound infection in one patient that resolved with antibiotic therapy, and transient altered mental status and late multiple sclerosis exacerbation in another patient. The most common non-serious adverse events were headache and fatigue.

. HOLDEN, N.E. 2005-05-08 The published scientific literature is scanned and periodically evaluated for neutron and non-neutron nuclear data and the resulting recommendations are published 1,2. After the literature has been scanned and appropriate data collected, there are often problems with regard to the treatment of the various types of data during this evaluation process and with regard to the method by which the recommendations are drawn from the assessment of the collection of individual measurements.

Some-problems with uncertainties are presented. Fulton, J.C. 1994-10-01 Volume I of the Hanford Spent Nuclear Fuel Project - Recommended Path Forward constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. Volume II provided a comparative evaluation of four Alternatives for the Path Forward and an evaluation for the Recommended Path Forward. Although Volume II contained extensive appendices, six supporting documents have been compiled in Volume III to provide additional background for Volume II.

Ferrari, Robert 2015-09-01 The objective of this study was to evaluate the Canadian Rheumatology Association Choosing Wisely recommendation concerning anti- nuclear antibody (ANA) testing. Patients with joint pain/stiffness/swelling were assessed to determine if ANA testing was indicated. An a priori threshold was set before ANA testing would be considered.

Those who did not have ANA testing ordered were followed for 1 year to determine if any of them went on to have a diagnosis of systemic lupus erythematosus (SLE) or other connective tissue disease. A parallel study was conducted with a similar a priori threshold for the use of rheumatoid factor (RF) and anti-cyclic citrullinated peptide (anti-CCP) antibody testing in the diagnosis of rheumatoid arthritis (RA), and again, patients were followed for 1 year. A total of 866 subjects were examined, 509 females (58.8%) and 357 males (41.2%).

The mean age of the group was 47.5 ± 16.8 years. The mean duration of symptoms was 12.0 ± 5.6 weeks. Of the 866 subjects, 68 met an a priori threshold for ordering ANA, RF, and anti-CCP testing.

Of these 68, there was a newly diagnosed case of SLE, 4 newly diagnosed cases of RA, and 3 cases of polymyalgia rheumatica. The remaining 798 subjects were followed for approximately 1 year and none developed evidence of SLE, RA, or other connective tissue disease. In the evaluation of non-specific musculoskeletal symptoms, setting an a priori threshold for ordering serology in keeping with the spirit of the Canadian Rheumatology Association Choosing Wisely recommendation for antibody testing results in a very low risk of missing a case of systemic lupus erythematosus or rheumatoid arthritis.

None, None 2013-02-01 In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made. These actions and recommendations were addressed in an August 2011 report to the Secretary of Energy, Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events.

Based on recommendations in the August 2011 report, DOE embarked on a project to develop and refine guidance that supports improvements in DOE’s processes for analyzing and mitigating beyond design basis events (BDBEs), i.e., events such as earthquakes that are more severe than the events that formed the basis of the design for DOE’s nuclear facilities. The results of this BDBE project and recommendations for further DOE actions are provided in this follow-on report. The main activity of the BDBE project was the pilot application of guidance for evaluation of BDBE analysis and mitigation features at four DOE nuclear facilities representing a range of DOE sites, nuclear facility types/activities, and responsible program offices. The pilot evaluations focused on: (1) BDBE evaluations as documented in the facility Documented Safety Analysis (DSA); (2) potential BDBE vulnerabilities and margins to failure for facility safety features as obtained from general area and specific system walkdowns and design document reviews; and, (3) preparations made in facility and site emergency management programs to respond to severe accidents. The BDBE project also evaluated whether draft BDBE guidance on safety analysis and emergency management could be used to improve the analysis of, and preparations for, mitigating severe accidents and BDBEs.

The pilot evaluation team paid close attention to related actions being pursued by the U.S. Nuclear Regulatory Commission, the U.S. Commercial nuclear industry, and the.

Showstack, Randy 2012-02-01 During an 8 February U.S. Congressional hearing to examine how to move forward on dealing with spent nuclear fuel and to review other recommendations of the recently released final report of the White House-appointed Blue Ribbon Commission on America's Nuclear Future (BRC), Yucca Mountain was the 65,000-ton gorilla in the room.

BRC's charge was to conduct a comprehensive review of policies to manage the back end of the nuclear fuel cycle and recommend a new strategy for dealing with the 65,000 tons of spent nuclear fuel currently stored at 75 sites around the country and the 2000 tons of new spent fuel being produced each year. However, BRC specifically did not evaluate Yucca Mountain. A 26 January letter from BRC to U.S. Secretary of energy Steven Chu states, 'You directed that the Commission was not to serve as a siting body. Accordingly, we have not evaluated Yucca Mountain or any other location as a potential site for the storage of spent nuclear fuel or disposal of high-level waste nor have we taken a position on the administration's request to withdraw the Yucca Mountain license application.'

1988-01-01 A study was conducted by NASA Lewis Research Center for the Triagency SP-100 program office. The objective was to determine which reactor, conversion and radiator technologies would best fulfill future Megawatt Class Nuclear Space Power System Requirements. The requirement was 10 megawatts for 5 years of full power operation and 10 years system life on orbit. A variety of liquid metal and gas cooled reactors, static and dynamic conversion systems, and passive and dynamic radiators were considered. Four concepts were selected for more detailed study: (1) a gas cooled reactor with closed cycle Brayton turbine-alternator conversion with heatpipe and pumped tube fin rejection, (2) a Lithium cooled reactor with a free piston Stirling engine-linear alternator and a pumped tube-fin radiator,(3) a Lithium cooled reactor with a Potassium Rankine turbine-alternator and heat pipe radiator, and (4) a Lithium cooled incore thermionic static conversion reactor with a heat pipe radiator. The systems recommended for further development to meet a 10 megawatt long life requirement are the Lithium cooled reactor with the K-Rankine conversion and heat pipe radiator, and the Lithium cooled incore thermionic reactor with heat pipe radiator.

1988-09-01 A study was conducted by NASA Lewis Research Center for the Triagency SP-100 program office. The objective was to determine which reactor, conversion and radiator technologies would best fulfill future Megawatt Class Nuclear Space Power System Requirements. The requirement was 10 megawatts for 5 years of full power operation and 10 years system life on orbit. A variety of liquid metal and gas cooled reactors, static and dynamic conversion systems, and passive and dynamic radiators were considered. Four concepts were selected for more detailed study: (1) a gas cooled reactor with closed cycle Brayton turbine-alternator conversion with heatpipe and pumped tube fin rejection, (2) a Lithium cooled reactor with a free piston Stirling engine-linear alternator and a pumped tube-fin radiator,(3) a Lithium cooled reactor with a Potassium Rankine turbine-alternator and heat pipe radiator, and (4) a Lithium cooled incore thermionic static conversion reactor with a heat pipe radiator. The systems recommended for further development to meet a 10 megawatt long life requirement are the Lithium cooled reactor with the K-Rankine conversion and heat pipe radiator, and the Lithium cooled incore thermionic reactor with heat pipe radiator. Oblozinsky, P.; Oblozinsky,P.; Herman,M.; Mughabghab,S.F.

2010-10-01 This chapter describes the current status of evaluated nuclear data for nuclear technology applications. We start with evaluation procedures for neutron-induced reactions focusing on incident energies from the thermal energy up to 20 MeV, though higher energies are also mentioned. This is followed by examining the status of evaluated neutron data for actinides that play dominant role in most of the applications, followed by coolants/moderators, structural materials and fission products. We then discuss neutron covariance data that characterize uncertainties and correlations. We explain how modern nuclear evaluated data libraries are validated against an extensive set of integral benchmark experiments. Afterwards, we briefly examine other data of importance for nuclear technology, including fission yields, thermal neutron scattering and decay data.

A description of three major evaluated nuclear data libraries is provided, including the latest version of the US library ENDF/B-VII.0, European JEFF-3.1 and Japanese JENDL-3.3. A brief introduction is made to current web retrieval systems that allow easy access to a vast amount of up-to-date evaluated nuclear data for nuclear technology applications. Doherty, Michael P. 1992-01-01 Summarized are the findings and recommendations of a triagency (NASA/DOE/DOD) panel on Nuclear Electric Propulsion (NEP) Technology. NEP has been identified as a candidate nuclear propulsion technology for exploration of the Moon and Mars as part of the Space Exploration Initiative (SEI). The findings are stated in areas of system and subsystem considerations, technology readiness, and ground test facilities.

Recommendations made by the panel are summarized concerning: (1) existing space nuclear power and propulsion programs, and (2) the proposed multiagency NEP technology development program. Marshall, Albert C.; Lee, James H.; Mcculloch, William H.; Sawyer, J.

Charles, Jr.; Bari, Robert A.; Cullingford, Hatice S.; Hardy, Alva C.; Niederauer, George F.; Remp, Kerry; Rice, John W. 1993-01-01 An interagency Nuclear Safety Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program. These recommendations, which are contained in this report, should facilitate the implementation of mission planning and conceptual design studies. The NSPWG has recommended a top-level policy to provide the guiding principles for the development and implementation of the SEI nuclear propulsion safety program. In addition, the NSPWG has reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. These recommendations should be useful for the development of the program's top-level requirements for safety functions (referred to as Safety Functional Requirements). The safety requirements and guidelines address the following topics: reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations.

Wang, Shih-chen 2009-03-01 This paper outlines briefly the role of nuclear medicine in life sciences and health care. Molecular imaging by using isotopic tracers can noninvasively visualize the chemistry or hidden process in the cells and tissues inside the body, obtaining 'functional' images to provide early information of any disease and revealing the secrets of life. The vitality of nuclear medicine is its ability to translate bench into new clinical application that can benefits the patients.

Although nuclear medicine community in China has made significant achievement with a great effort since 1950s, there are many obstacles to future development. Recommended measures are proposed here in an attempt to solve our existing problems. This document provides technical recommendations that both systems and primacy agencies can use to comply with LCR CCT requirements and effective evaluation and designation of optimal corrosion control treatment (OCCT).

Haas, P.M.; Carter, R.J.; Laughery, K.R. 1985-01-01 A methodology for evaluation of nuclear power plant simulation facilities with regard to their acceptability for use in the US Nuclear Regulatory Commission (NRC) operator licensing exam is described. The evaluation is based primarily on simulator fidelity, but incorporates some aspects of direct operator/trainee performance measurement. The panel presentation and paper discuss data requirements, data collection, data analysis and criteria for conclusions regarding the fidelity evaluation, and summarize the proposed use of direct performance measurment. While field testing and refinement of the methodology are recommended, this initial effort provides a firm basis for NRC to fully develop the necessary methodology. Shinn, Judy L.; Wilson, John W. 1991-01-01 The biological risk for energetic ion exposure cannot be reliably estimated exclusive of the target nuclear reaction products produced within the local tissue.

A theoretical basis is derived for evaluating target fragment contributions that are evaluated for the newly proposed quality factor. The Evaluated Nuclear Structure Data File (ENSDF) contains the evaluated nuclear properties of all known nuclides. These properties are derived both from nuclear reaction and radioactive decay measurements. All experimental data are evaluated to create the adopted properties for each nuclide. ENSDF, together with other numeric and biographic files, can be accessed on-line through the INTERNET or modem. Some of the databases are also available on the World Wide Web. The structure and the scope of ENSDF are presented along with the on-line access system of the National Nuclear Data Center at Brookhaven National Laboratory.

1996-02-01 The Evaluated Nuclear Structure Data File (ENSDF) contains the evaluated nuclear properties of all known nuclides, as derived both from nuclear reaction and radioactive decay measurements. All experimental data are evaluated to create the adopted properties for each nuclide.

ENSDF, together with other numeric and bibliographic files, can be accessed on-line through the INTERNET or modem, and some of the databases are also available on the World Wide Web. The structure and the scope of ENSDF are presented along with the on-line access system of the National Nuclear Data Center at Brookhaven National Laboratory. Gunther, W.E.; Subudhi, M. ); Aggarwal, S.K. ) 1992-01-01 Research conducted under the auspices of the US NRC's Nuclear Plant Aging Research (NPAR) Program has resulted in a large database of component and system operating, maintenance, and testing information. This database has been used to determine the susceptibility to aging of selected components, and the potential for equipment aging to impact plant safety and availability.

It has also identified methods for detecting and mitigating component and system aging. This paper describes the research recommendations on electrical components which could be applied to maintenance, testing, and inspection activities to detect and mitigate the effects of aging prior to equipment failures. Gunther, W.E.; Subudhi, M.; Aggarwal, S.K. 1992-12-01 Research conducted under the auspices of the US NRC`s Nuclear Plant Aging Research (NPAR) Program has resulted in a large database of component and system operating, maintenance, and testing information.

This database has been used to determine the susceptibility to aging of selected components, and the potential for equipment aging to impact plant safety and availability. It has also identified methods for detecting and mitigating component and system aging.

Fahn Tolosa Marin Tremor Rating Scale Pdf Acrobat Reader

This paper describes the research recommendations on electrical components which could be applied to maintenance, testing, and inspection activities to detect and mitigate the effects of aging prior to equipment failures. Vernig, P G; Schumacher, T A 2001-11-01 The revision of 10 CFR 35 approved on 23 September 2000 and due for implementation in 2001, reduces the number of required radiation and contamination surveys to one ambient radiation survey each day when an administration requiring a written directive is used.

This paper compares the current requirements in 10 CFR 35; the single, remaining, specific requirement in the revised part 35; the Nuclear Regulatory Commission's guidance in the proposed NUREG SR1556 and the general requirement for surveys to demonstrate compliance with 10 CFR 20. We also make recommendations on what periodic surveys are prudent. Neudecker, Denise 2015-06-17 Nuclear data evaluations provide recommended data sets for nuclear data applications such as reactor physics, stockpile stewardship or nuclear medicine.

The evaluated data are often based on information from multiple experimental data sets and nuclear theory using statistical methods. Therefore, they are collaborative efforts of evaluators, theoreticians, experimentalists, benchmark experts, statisticians and application area scientists. In this talk, an introductions is given to the field of nuclear data evaluation at the specific example of a recent evaluation of the outgoing neutron energy spectrum emitted promptly after fission from 239Pu and induced by neutrons from thermal to 30 MeV. Wright, R.Q.; MacFarlane, R.E.

2000-04-01 In response to concerns raised in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 93-2, the US Department of Energy (DOE) developed a comprehensive program to help assure that the DOE maintain and enhance its capability to predict the criticality of systems throughout the complex. Tasks developed to implement the response to DNFSB recommendation 93-2 included Critical Experiments, Criticality Benchmarks, Training, Analytical Methods, and Nuclear Data. The Nuclear Data Task consists of a program of differential measurements at the Oak Ridge Electron Linear Accelerator (ORELA), precise fitting of the differential data with the generalized least-squares fitting code SAMMY to represent the data with resonance parameters using the Reich-Moore formalism along with covariance (uncertainty) information, and the development of complete evaluations for selected nuclides for inclusion in the Evaluated Nuclear Data File (ENDFB). Ricard-McCutchan, E.; Dimitriou, P.; Nichols, A. 2015-08-01 The 21st meeting of the International Network of Nuclear Structure and Decay Data Evaluators was convened at the IAEA Headquarters, Vienna, from 20 to 24 April 2015 under the auspices of the IAEA Nuclear Data Section. This meeting was attended by 36 scientists from 15 Member States, plus IAEA staff, concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, data centre reports, various proposals considered, and actions agreed by the participants, as well as recommendations/conclusions are presented within this document.

Kunerth, D. C.; McJunkin, T. 2012-05-01 The material of choice for the core of the high-temperature gas-cooled reactors being developed by the U.S. Department of Energy's Next Generation Nuclear Plant Program is graphite. Graphite is a composite material whose properties are highly dependent on the base material and manufacturing methods. In addition to the material variations intrinsic to the manufacturing process, graphite will also undergo changes in material properties resulting from radiation damage and possible oxidation within the reactor.

Idaho National Laboratory is presently evaluating the viability of conventional nondestructive evaluation techniques to characterize the material variations inherent to manufacturing and in-service degradation. Approaches of interest include x-ray radiography, eddy currents, and ultrasonics. Kunerth, D. C.; McJunkin, T. 2012-05-17 The material of choice for the core of the high-temperature gas-cooled reactors being developed by the U.S. Department of Energy's Next Generation Nuclear Plant Program is graphite.

Graphite is a composite material whose properties are highly dependent on the base material and manufacturing methods. In addition to the material variations intrinsic to the manufacturing process, graphite will also undergo changes in material properties resulting from radiation damage and possible oxidation within the reactor.

Idaho National Laboratory is presently evaluating the viability of conventional nondestructive evaluation techniques to characterize the material variations inherent to manufacturing and in-service degradation. Approaches of interest include x-ray radiography, eddy currents, and ultrasonics. Musgrave, B.C.; Grens, J.Z.; Knighton, J.B.; Coops, M.S. 1983-12-01 A working group was assigned the task of evaluating the status of nonaqueous processes for nuclear materials and the prospects for successful deployment of these technologies in the future. In the initial evaluation, the study was narrowed to the pyrochemical/pyrometallurgical processes closely related to the processes used for purification of plutonium and its conversion to metal. The status of the chemistry and process hardware were reviewed and the development needs in both chemistry and process equipment technology were evaluated.

Finally, the requirements were established for successful deployment of this technology. The status of the technology was evaluated along three lines: (1) first the current applications were examined for completeness, (2) an attempt was made to construct closed-cycle flow sheets for several proposed applications, (3) and finally the status of technical development and future development needs for general applications were reviewed. By using these three evaluations, three different perspectives were constructed that together present a clear picture of how complete the technical development of these processes are. 2016-07-14 guidance (including the Secretary of Defense memo Nuclear Enterprise Review Corrective Action Implementation), and documents from the Office of Cost.the recommendations. The tracking tool currently contains hundreds of unique milestones and metrics, and additional milestones and metrics are still.holder may be necessary if you wish to reproduce this material separately.

The Government Accountability Office, the audit. 2013-02-12. From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY DOE Response to Recommendation 2012-2 of the Defense Nuclear Facilities Safety Board, Hanford Tank Farms., Hanford Tank Farms Flammable Gas Safety Strategy. This document corrects an error in that notice. Ala, Maureen; Gruidl, Jeremiah; Buddemeier, Brooke 2015-09-30 This document describes the development of the ROSS SKAs, the cross-mapping of the SKAs to the available training, identifies gaps in the SKA and training, and provides recommendations to address those gaps. 2000-09-15 explosive growth of the world-wide-web and the emergence of e - commerce has led to the development of recommender systems—a personalized information.of e - commerce has led to the development of recom- mender systems 11.

Recommender systems is a personalized information filtering technology, used to.items, utilized by many e - commerce sites, cannot take advantage of pre-computed user-to-user similarities. Consequently, even though the throughput of. Rodabaugh, E.C.; Gwaltney, R.C.; Moore, S.E.

1993-11-01 This report collects and uses available data to reexamine the criteria for controlling primary loads in nuclear piping branch connections as expressed in Section III of the ASME Boiler and Pressure Vessel Code. In particular, the primary load stress indices given in NB-3650 and NB-3683 are reexamined. The report concludes that the present usage of the stress indices in the criteria equations should be continued.

However, the complex treatment of combined branch and run moments is not supported by available information. Therefore, it is recommended that this combined loading evaluation procedure be replaced for primary loads by the separate leg evaluation procedure specified in NC/ND-3653.3(c) and NC/ND-3653.3(d).

No recommendation is made for fatigue or secondary load evaluations for Class 1 piping. Further work should be done on the development of better criteria for treatment of combined branch and run moment effects. Mashal, Ibrahim; Alsaryrah, Osama; Chung, Tein-Yaw 2016-06-01 Internet of Things (IoT) is the next wave of industry revolution that will initiate many services, such as personal health care and green energy monitoring, which people may subscribe for their convenience. Recommending IoT services to the users based on objects they own will become very crucial for the success of IoT. In this work, we introduce the concept of service recommender systems in IoT by a formal model.

As a first attempt in this direction, we have proposed a hyper-graph model for IoT recommender system in which each hyper-edge connects users, objects, and services. Next, we studied the usefulness of traditional recommendation schemes and their hybrid approaches on IoT service recommendation (IoTSRS) based on existing well known metrics. The preliminary results show that existing approaches perform reasonably well but further extension is required for IoTSRS. Several challenges were discussed to point out the direction of future development in IoTSR. Han, Yinlu; Guo, Hairui; Xu, Yongli; Zhang, Zhengjun; Liang, Haiying; Wu, Zhendong; Su, Xinwu; Zhang, Yue; Cai, Chonghai; Shen, Qingbiao 2017-09-01 The neutron and proton reaction data up to 200 MeV are calculated and evaluated using both nuclear model calculations and experimental data for Accelerator Driven System (ADS).

The evaluated methods and results of neutron and proton reaction data and present status of evaluated nuclear data library in China are introduced. Schmelkin, Liora Pedhazur; Hoag, Jennifer; Liebling, Dana E; Kaufman, Aviele M 2004-04-01 Previous research on consumer satisfaction suggests that the anticipation of providing a later evaluation leads to more negative appraisals. Within the context of higher education, the current experiment focused on the evaluation of a presentation and its presenter. College students (35 men, 59 women) were randomly assigned to six conditions regarding evaluative expectations and peer recommendations. Students watched a brief video of a lecture on an educational topic and then evaluated the speaker and presentation. Anticipation of providing evaluations did not influence the subsequent evaluations; however, peers' positive recommendations led to more positive evaluations whereas negative recommendations led to more negative evaluations.

2004-09-26 The Evaluated Nuclear Structure Data File (ENSDF) is a leading resource for the experimental nuclear data. It is maintained and distributed by the National Nuclear Data Center, Brookhaven National Laboratory. The file is mainly contributed to by an international network of evaluators under the auspice of the International Atomic Energy Agency. The ENSDF is updated, generally by mass number, i.e., evaluating together all isobars for a given mass number. If, however, experimental activity in an isobaric chain is limited to a particular nuclide then only that nuclide is updated. The evaluations are published in the journal Nuclear Data Sheets, Academic Press, a division of Elsevier.

Tuli, Jagdish K. 2005-05-24 The Evaluated Nuclear Structure Data File (ENSDF) is a leading resource for experimental nuclear data. It is maintained and distributed by the National Nuclear Data Center, Brookhaven National Laboratory. The file is mainly contributed to by an international network of evaluators under the auspice of the International Atomic Energy Agency.

The ENSDF is updated, generally by mass number, i.e., evaluating together all isobars for a given mass number. If, however, experimental activity in an isobaric chain is limited to a particular nuclide, then only that nuclide is updated. The evaluations are published in the Journal of Nuclear Data Sheets, Academic Press, a division of Elsevier. Wang, Meng Nuclear mass data are crucial input for the astrophysics models. Thanks to the developments of radioactive nuclear beam facilities and novel mass spectrometers, the experimental knowledge of nuclear masses has been continuously expanding to the exotic nuclei far from the stability which play a critical role in astrophysics. The recent progress and future perspective of mass measurement relevant to astrophysics will be discussed. By evaluating all available experimental data from nuclear reactions, radioactive decays and direct mass measurements, the Atomic Mass Evaluation (AME) serve the research community with reliable source for comprehensive information related to the nuclear masses.

The next AME version is envisioned to be published at the end of 2016. McKenzie, W.F. 1990-01-01 The purpose of this report is to review previous work on the weathering of natural glasses; and to make recommendations for further work with respect to studying the alteration of natural glasses as it relates quantifying rates of dissolution. The first task was greatly simplified by the published papers of Jercinovic and Ewing (1987) and Byers, Jercinovic, and Ewing (1987). The second task is obviously the more difficult of the two and the author makes no claim of completeness in this regard. Glasses weather in the natural environment by reacting with aqueous solutions producing a rind of secondary solid phases.

It had been proposed by some workers that the thickness of this rind is a function of the age of the glass and thus could be used to estimate glass dissolution rates. However, Jercinovic and Ewing (1987) point out that in general the rind thickness does not correlate with the age of the glass owing to the differences in time of contact with the solution compared to the actual age of the sample. It should be noted that the rate of glass dissolution is also a function of the composition of both the glass and the solution, and the temperature. Quantification of the effects of these parameters (as well as time of contact with the aqueous phase and flow rates) would thus permit a prediction of the consequences of glass-fluid interactions under varying environmental conditions. Defense high- level nuclear waste (DHLW), consisting primarily of liquid and sludge, will be encapsulated by and dispersed in a borosilicate glass before permanent storage in a HLW repository. This glass containing the DHLW serves to dilute the radionuclides and to retard their dispersion into the environment.

Verbalis, Joseph G; Goldsmith, Steven R; Greenberg, Arthur; Korzelius, Cynthia; Schrier, Robert W; Sterns, Richard H; Thompson, Christopher J 2013-10-01 Hyponatremia is a serious, but often overlooked, electrolyte imbalance that has been independently associated with a wide range of deleterious changes involving many different body systems. Untreated acute hyponatremia can cause substantial morbidity and mortality as a result of osmotically induced cerebral edema, and excessively rapid correction of chronic hyponatremia can cause severe neurologic impairment and death as a result of osmotic demyelination.

The diverse etiologies and comorbidities associated with hyponatremia pose substantial challenges in managing this disorder. In 2007, a panel of experts in hyponatremia convened to develop the Hyponatremia Treatment Guidelines 2007: Expert Panel Recommendations that defined strategies for clinicians caring for patients with hyponatremia. In the 6 years since the publication of that document, the field has seen several notable developments, including new evidence on morbidities and complications associated with hyponatremia, the importance of treating mild to moderate hyponatremia, and the efficacy and safety of vasopressin receptor antagonist therapy for hyponatremic patients. Therefore, additional guidance was deemed necessary and a panel of hyponatremia experts (which included all of the original panel members) was convened to update the previous recommendations for optimal current management of this disorder.

The updated expert panel recommendations in this document represent recommended approaches for multiple etiologies of hyponatremia that are based on both consensus opinions of experts in hyponatremia and the most recent published data in this field. Sharifi, Mona; Rifas-Shiman, Sheryl L; Marshall, Richard; Simon, Steven R; Gillman, Matthew W; Finkelstein, Jonathan A; Taveras, Elsie M 2013-02-01 The increasing prevalence of childhood overweight/obesity and their associated morbidities are well established, yet rates of diagnosis and screening for related conditions by clinicians are low. Expert Committee recommendations were released in 2007 to facilitate management of pediatric overweight/obesity. From well-child visits to a Massachusetts multisite group practice, we randomly selected 1 visit per child in 2006 (n = 56 374) and in 2008 (n = 69 681) and used electronic health record data to identify children with incident overweight or obesity (BMI ≥ 85th percentile) and ascertained whether clinicians assigned relevant ICD-9 (International Classification of Diseases, Ninth Revision) codes and ordered laboratory tests recommended for children ≥10 years old. In the year following the release of recommendations, a large majority of children 2 to 17 years old with a BMI ≥85th percentile lack diagnosis codes for overweight/obesity and recommended laboratory orders for assessment of obesity-related comorbidities for children 10 years and older, suggesting the need to augment current approaches to increase uptake of guidelines. 2013-10-23.

Evaluation and Recommendation of Pharmacopoeial Texts for Use in the International Conference on. Availability of a guidance entitled ``Q4B Evaluation and Recommendation of Pharmacopoeial Texts for Use in the. ICH Q4B evaluation of the Bacterial Endotoxins Test General Chapter harmonized text from each of.