WorldWideScience

Sample records for evaluated nuclear parameter

  1. RIPL - Reference Input Parameter Library for Calculation of Nuclear Reactions and Nuclear Data Evaluations

    Science.gov (United States)

    Capote, R.; Herman, M.; Obložinský, P.; Young, P. G.; Goriely, S.; Belgya, T.; Ignatyuk, A. V.; Koning, A. J.; Hilaire, S.; Plujko, V. A.; Avrigeanu, M.; Bersillon, O.; Chadwick, M. B.; Fukahori, T.; Ge, Zhigang; Han, Yinlu; Kailas, S.; Kopecky, J.; Maslov, V. M.; Reffo, G.; Sin, M.; Soukhovitskii, E. Sh.; Talou, P.

    2009-12-01

    We describe the physics and data included in the Reference Input Parameter Library, which is devoted to input parameters needed in calculations of nuclear reactions and nuclear data evaluations. Advanced modelling codes require substantial numerical input, therefore the International Atomic Energy Agency (IAEA) has worked extensively since 1993 on a library of validated nuclear-model input parameters, referred to as the Reference Input Parameter Library (RIPL). A final RIPL coordinated research project (RIPL-3) was brought to a successful conclusion in December 2008, after 15 years of challenging work carried out through three consecutive IAEA projects. The RIPL-3 library was released in January 2009, and is available on the Web through http://www-nds.iaea.org/RIPL-3/. This work and the resulting database are extremely important to theoreticians involved in the development and use of nuclear reaction modelling (ALICE, EMPIRE, GNASH, UNF, TALYS) both for theoretical research and nuclear data evaluations. The numerical data and computer codes included in RIPL-3 are arranged in seven segments: MASSES contains ground-state properties of nuclei for about 9000 nuclei, including three theoretical predictions of masses and the evaluated experimental masses of Audi et al. (2003). DISCRETE LEVELS contains 117 datasets (one for each element) with all known level schemes, electromagnetic and γ-ray decay probabilities available from ENSDF in October 2007. NEUTRON RESONANCES contains average resonance parameters prepared on the basis of the evaluations performed by Ignatyuk and Mughabghab. OPTICAL MODEL contains 495 sets of phenomenological optical model parameters defined in a wide energy range. When there are insufficient experimental data, the evaluator has to resort to either global parameterizations or microscopic approaches. Radial density distributions to be used as input for microscopic calculations are stored in the MASSES segment. LEVEL DENSITIES contains

  2. RIPL-Reference Input Parameter Library for Calculation of Nuclear Reactions and Nuclear Data Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Capote, R.; Herman, M.; Capote,R.; Herman,M.; Oblozinsky,P.; Young,P.G.; Goriely,S.; Belgy,T.; Ignatyuk,A.V.; Koning,A.J.; Hilaire,S.; Pljko,V.A.; Avrigeanu,M.; Bersillon,O.; Chadwick,M.B.; Fukahori,T.; Ge, Zhigang; Han,Yinl,; Kailas,S.; Kopecky,J.; Maslov,V.M.; Reffo,G.; Sin,M.; Soukhovitskii,E.Sh.; Talou,P

    2009-12-01

    We describe the physics and data included in the Reference Input Parameter Library, which is devoted to input parameters needed in calculations of nuclear reactions and nuclear data evaluations. Advanced modelling codes require substantial numerical input, therefore the International Atomic Energy Agency (IAEA) has worked extensively since 1993 on a library of validated nuclear-model input parameters, referred to as the Reference Input Parameter Library (RIPL). A final RIPL coordinated research project (RIPL-3) was brought to a successful conclusion in December 2008, after 15 years of challenging work carried out through three consecutive IAEA projects. The RIPL-3 library was released in January 2009, and is available on the Web through http://www-nds.iaea.org/RIPL-3/. This work and the resulting database are extremely important to theoreticians involved in the development and use of nuclear reaction modelling (ALICE, EMPIRE, GNASH, UNF, TALYS) both for theoretical research and nuclear data evaluations. The numerical data and computer codes included in RIPL-3 are arranged in seven segments: MASSES contains ground-state properties of nuclei for about 9000 nuclei, including three theoretical predictions of masses and the evaluated experimental masses of Audi et al. (2003). DISCRETE LEVELS contains 117 datasets (one for each element) with all known level schemes, electromagnetic and {gamma}-ray decay probabilities available from ENSDF in October 2007. NEUTRON RESONANCES contains average resonance parameters prepared on the basis of the evaluations performed by Ignatyuk and Mughabghab. OPTICAL MODEL contains 495 sets of phenomenological optical model parameters defined in a wide energy range. When there are insufficient experimental data, the evaluator has to resort to either global parameterizations or microscopic approaches. Radial density distributions to be used as input for microscopic calculations are stored in the MASSES segment. LEVEL DENSITIES contains

  3. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M., E-mail: sarker_md@yahoo.co [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2010-03-15

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k{sub eff} and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  4. Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh)], E-mail: jahirulkhan@yahoo.com; Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2009-10-15

    The aim of this paper is to present the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through the analysis of the integral parameters of TRX and BAPL benchmark lattices of thermal reactors for neutronics analysis of TRIGA Mark-II Research Reactor at AERE, Bangladesh. In this process, the 69-group cross-section library for lattice code WIMS was generated using the basic evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 with the help of nuclear data processing code NJOY99.0. Integral measurements on the thermal reactor lattices TRX-1, TRX-2, BAPL-UO{sub 2}-1, BAPL-UO{sub 2}-2 and BAPL-UO{sub 2}-3 served as standard benchmarks for testing nuclear data files and have also been selected for this analysis. The integral parameters of the said lattices were calculated using the lattice transport code WIMSD-5B based on the generated 69-group cross-section library. The calculated integral parameters were compared to the measured values as well as the results of Monte Carlo Code MCNP. It was found that in most cases, the values of integral parameters show a good agreement with the experiment and MCNP results. Besides, the group constants in WIMS format for the isotopes U-235 and U-238 between two data files have been compared using WIMS library utility code WILLIE and it was found that the group constants are identical with very insignificant difference. Therefore, this analysis reflects the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through benchmarking the integral parameters of TRX and BAPL lattices and can also be essential to implement further neutronic analysis of TRIGA Mark-II research reactor at AERE, Dhaka, Bangladesh.

  5. Research on the attribution evaluating methods of dynamic effects of various parameter uncertainties on the in-structure floor response spectra of nuclear power plant

    Science.gov (United States)

    Li, Jianbo; Lin, Gao; Liu, Jun; Li, Zhiyuan

    2017-01-01

    Consideration of the dynamic effects of the site and structural parameter uncertainty is required by the standards for nuclear power plants (NPPs) in most countries. The anti-seismic standards provide two basic methods to analyze parameter uncertainty. Directly manually dealing with the calculated floor response spectra (FRS) values of deterministic approaches is the first method. The second method is to perform probability statistical analysis of the FRS results on the basis of the Monte Carlo method. The two methods can only reflect the overall effects of the uncertain parameters, and the results cannot be screened for a certain parameter's influence and contribution. In this study, based on the dynamic analyses of the floor response spectra of NPPs, a comprehensive index of the assessed impact for various uncertain parameters is presented and recommended, including the correlation coefficient, the regression slope coefficient and Tornado swing. To compensate for the lack of guidance in the NPP seismic standards, the proposed method can effectively be used to evaluate the contributions of various parameters from the aspects of sensitivity, acuity and statistical swing correlations. Finally, examples are provided to verify the set of indicators from systematic and intuitive perspectives, such as the uncertainty of the impact of the structure parameters and the contribution to the FRS of NPPs. The index is sensitive to different types of parameters, which provides a new technique for evaluating the anti-seismic parameters required for NPPs.

  6. Evaluated Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    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.

  7. Stereological estimation of nuclear volume and other quantitative histopathological parameters in the prognostic evaluation of supraglottic laryngeal squamous cell carcinoma

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Bennedbaek, O; Pilgaard, J

    1989-01-01

    The aim of this study was to investigate various approaches to the grading of malignancy in pre-treatment biopsies from patients with supraglottic laryngeal squamous cell carcinoma. The prospects of objective malignancy grading based on stereological estimation of the volume-weighted mean nuclear...

  8. Performance Parameters Pertinent to Nuclear Powered Aircraft

    Energy Technology Data Exchange (ETDEWEB)

    Ruffman, B.F.

    1952-02-06

    A review of the present design information and studies relating to nuclear power plants indicates that the weight of the power plant components, exclusive of crew shield and nacelles, may at a particular design point be represented by an equation of the form, W{subpp} = W{subo} + K{subt}T. By use of this, a power plant parameter psi is defined as the ratio of the part of the power plant plus nacelle weight that varies with thrust to the net thrust of the power plant less nacelle drag. The funamentall part that this parameter plays in determining the gross weight of a nuclaer powered aircraft is shown. This parameter depends on the design point Mach number and altitude, and the weight and drag increments attributable to the nacelle installation.

  9. Adaptive Monte Carlo for nuclear data evaluation

    Directory of Open Access Journals (Sweden)

    Schnabel Georg

    2017-01-01

    Full Text Available An adaptive Monte Carlo method for nuclear data evaluation is presented. A fast evaluation method based on the linearization of the nuclear model guides the adaptation of the sampling distribution towards the posterior distribution. The method is suited for parallel computation and provides detailed uncertainty information about nuclear model parameters. Especially, the posterior distribution of the model parameters is not restricted to be multivariate normal. The method is demonstrated in an evaluation of the 181Ta total cross section for incident neutrons. Future applications are as an efficient sampling scheme in the Total Monte Carlo method, and the restriction of parameter uncertainties in nuclear models by both differential and integral data.

  10. Evaluated Nuclear Structure Data File

    Science.gov (United States)

    Tuli, Jagdish K.

    2004-10-01

    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, a publication of Elsevier. This presentation will briefly review this and other databases and dissemination services of the US and international network, and reflect on how the network resources can help scientists in both the basic as well as the applied fields.

  11. Using neural networks for prediction of nuclear parameters

    Energy Technology Data Exchange (ETDEWEB)

    Pereira Filho, Leonidas; Souto, Kelling Cabral, E-mail: leonidasmilenium@hotmail.com, E-mail: kcsouto@bol.com.br [Instituto Federal de Educacao, Ciencia e Tecnologia do Rio de Janeiro (IFRJ), Rio de Janeiro, RJ (Brazil); Machado, Marcelo Dornellas, E-mail: dornemd@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (GCN.T/ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Gerencia de Combustivel Nuclear

    2013-07-01

    Dating from 1943, the earliest work on artificial neural networks (ANN), when Warren Mc Cullock and Walter Pitts developed a study on the behavior of the biological neuron, with the goal of creating a mathematical model. Some other work was done until after the 80 witnessed an explosion of interest in ANNs, mainly due to advances in technology, especially microelectronics. Because ANNs are able to solve many problems such as approximation, classification, categorization, prediction and others, they have numerous applications in various areas, including nuclear. Nodal method is adopted as a tool for analyzing core parameters such as boron concentration and pin power peaks for pressurized water reactors. However, this method is extremely slow when it is necessary to perform various core evaluations, for example core reloading optimization. To overcome this difficulty, in this paper a model of Multi-layer Perceptron (MLP) artificial neural network type backpropagation will be trained to predict these values. The main objective of this work is the development of Multi-layer Perceptron (MLP) artificial neural network capable to predict, in very short time, with good accuracy, two important parameters used in the core reloading problem - Boron Concentration and Power Peaking Factor. For the training of the neural networks are provided loading patterns and nuclear data used in cycle 19 of Angra 1 nuclear power plant. Three models of networks are constructed using the same input data and providing the following outputs: 1- Boron Concentration and Power Peaking Factor, 2 - Boron Concentration and 3 - Power Peaking Factor. (author)

  12. NUCLEAR DATA EVALUATIONS AND RECOMMENDATIONS

    Energy Technology Data Exchange (ETDEWEB)

    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.

  13. Determination of parameters of a nuclear reactor through noise measurements

    Science.gov (United States)

    Cohn, C.E.

    1975-07-15

    A method of measuring parameters of a nuclear reactor by noise measurements is described. Noise signals are developed by the detectors placed in the reactor core. The polarity coincidence between the noise signals is used to develop quantities from which various parameters of the reactor can be calculated. (auth)

  14. Nuclear explosives testing readiness evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Valk, T.C.

    1993-09-01

    This readiness evaluation considers hole selection and characterization, verification, containment issues, nuclear explosive safety studies, test authorities, event operations planning, canister-rack preparation, site preparation, diagnostic equipment setup, device assembly facilities and processes, device delivery and insertion, emplacement, stemming, control room activities, readiness briefing, arming and firing, test execution, emergency response and reentry, and post event analysis to include device diagnostics, nuclear chemistry, and containment. This survey concludes that the LLNL program and its supporting contractors could execute an event within six months of notification, and a second event within the following six months, given the NET group`s evaluation and the following three restraints: (1) FY94 (and subsequent year) funding is essentially constant with FY93, (2) Preliminary work for the initial event is completed to the historical sic months status, (3) Critical personnel, currently working in dual use technologies, would be recallable as needed.

  15. Cytological evaluation of thyroid lesions by nuclear morphology and nuclear morphometry

    OpenAIRE

    R Yashaswini; T N Suresh; Sagayaraj, A.

    2017-01-01

    Introduction: Fine needle aspiration (FNA) of the thyroid gland is an effective diagnostic method. The Bethesda system for reporting thyroid cytopathology classifies them into six categories and gives implied risk for malignancy and management protocol in each category. Though the system gives specific criteria, diagnostic dilemma still exists. Using nuclear morphometry, we can quantify the number of parameters, such as those related to nuclear size and shape. The evaluation of nuclear morpho...

  16. Nuclear Fuel Cycle Evaluation and Real Options

    Directory of Open Access Journals (Sweden)

    L. Havlíček

    2008-01-01

    Full Text Available The first part of this paper describes the nuclear fuel cycle. It is divided into three parts. The first part, called Front-End, covers all activities connected with fuel procurement and fabrication. The middle part of the cycle includes fuel reload design activities and the operation of the fuel in the reactor. Back-End comprises all activities ensuring safe separation of spent fuel and radioactive waste from the environment. The individual stages of the fuel cycle are strongly interrelated. Overall economic optimization is very difficult. Generally, NPV is used for an economic evaluation in the nuclear fuel cycle. However the high volatility of uranium prices in the Front-End, and the large uncertainty of both economic and technical parameters in the Back-End, make the use of NPV difficult. The real option method is able to evaluate the value added by flexibility of decision making by a company under conditions of uncertainty. The possibility of applying this method to the nuclear fuel cycle evaluation is studied. 

  17. Nuclear parameters from muonic and pionic x rays

    Energy Technology Data Exchange (ETDEWEB)

    Steffen, R M

    1980-01-01

    In view of the higher precision of the experimental data in measurements of the energies and relative intensities of the muonic and pionic x-ray transitions, the validity of the approximations made in extracting nuclear spectroscopic values from the raw data must be scrutinized more carefully if the reliability of the extracted parameters are to approach the accuracy of the experimental data. (GHT)

  18. Nuclear matter equation of state and σ-meson parameters

    Indian Academy of Sciences (India)

    Abstract. We try to determine phenomenologically the extent of in-medium modifi- cation of σ-meson parameters so that the saturation observables of the nuclear matter equation of state (EOS) are reproduced. To calculate the EOS we have used Brueckner–. Bethe–Goldstone formalism with Bonn potential as two-body ...

  19. Angular momentum dependence of the nuclear level density parameter

    Directory of Open Access Journals (Sweden)

    Gohil M.

    2014-03-01

    Full Text Available Neutron evaporation spectra alongwith γ-multiplicity has been measured from the 185Re* compound nucleus at the excitation energies ~27 and 37 MeV. Statistical model analysis of the experimental data has been carried out to extract the value of the inverse level density parameter k at different angular momentum regions (J corresponding to different γ-multiplicity. It is observed that, for the present system the value of k remains almost constant for different J. The present results on the angular momentum dependence of the nuclear level density (NLD parameter ã (=A/k, for nuclei with A ~180 is quite different from our earlier measurements in case of light and medium mass systems. The present analysis provides useful information to understand the angular momentum dependence of NLD at different nuclear mass regions.

  20. Working Party on International Nuclear Data Evaluation Cooperation (WPEC)

    Energy Technology Data Exchange (ETDEWEB)

    Dupont, E.; Herman, M.; Dupont, E.; Chadwick, M. B.; Danon, Y.; De Saint Jean, C.; Dunn, M.; Fischer, U.; Forrest, R. A.; Fukahori, T.; Ge, Z.; Harada, H.; Herman, M.; Igashira, M.; Ignatyuk, A.; Ishikawa, M.; Iwamoto, O.; Jacqmin, R.; Kahler, A. C.; Kawano, T.; Koning, A. J.; Leal, L.; Lee, Y. O.; McKnight, R.; McNabb, D.; Mills, R. W.; Palmiotti, G.; Plompen, A.; Salvatores, M.; Schillebeeckx, P.

    2014-06-01

    The OECD Nuclear Energy Agency (NEA) organizes cooperation between the major nuclear data evaluation projects in the world. Moreover, the NEA Working Party on International Nuclear Data Evaluation Cooperation (WPEC) was established to promote the exchange of information on nuclear data evaluation, measurement, nuclear model calculation, validation, and related topics, and to provide a framework for cooperative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint activities in the framework of dedicated WPEC subgroups. Studies recently completed comprise a number of works related to nuclear data covariance and associated processing issues, as well as more specific studies related to the resonance parameter representation in the unresolved resonance region, the gamma production from fission product capture reactions, the 235U capture cross section, the EXFOR database, and the improvement of nuclear data for advanced reactor systems. Ongoing activities focus on the evaluation of 239Pu in the resonance region, scattering angular distribution in the fast energy range, and reporting/usage of experimental data for evaluation in the resolved resonance region. New activities include two subgroups on improved fission product yield evaluation methodologies and on modern nuclear database structures. Some future activities under discussion include a pilot project for a Collaborative International Evaluated Library Organization (CIELO) and methods to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data. In addition to the above mentioned short-term task-oriented subgroups, WPEC also hosts a longer-term subgroup charged with reviewing and compiling the most important nuclear data requirements in a high priority request list (HPRL).

  1. Working Party on International Nuclear Data Evaluation Cooperation (WPEC)

    Energy Technology Data Exchange (ETDEWEB)

    Dupont, E., E-mail: wpec@oecd-nea.org [OECD Nuclear Energy Agency, Issy-les-Moulineaux (France); Chadwick, M.B. [Los Alamos National Laboratory, Los Alamos, NM (United States); Danon, Y. [Rensselaer Polytechnic Institute, Troy, NY (United States); De Saint Jean, C. [CEA, Nuclear Energy Division, Cadarache (France); Dunn, M. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Fischer, U. [Karlsruhe Institute of Technology, Karlsruhe (Germany); Forrest, R.A. [Nuclear Data Section, International Atomic Energy Agency (Austria); Fukahori, T. [Japan Atomic Energy Agency (Japan); Ge, Z. [China Institute of Atomic Energy (China); Harada, H. [Japan Atomic Energy Agency (Japan); Herman, M. [Brookhaven National Laboratory, Upton, NY (United States); Igashira, M. [Tokyo Institute of Technology, Tokyo (Japan); Ignatyuk, A. [Institute of Physics and Power Engineering, Obninsk (Russian Federation); Ishikawa, M.; Iwamoto, O. [Japan Atomic Energy Agency (Japan); Jacqmin, R. [CEA, Nuclear Energy Division, Cadarache (France); Kahler, A.C.; Kawano, T. [Los Alamos National Laboratory, Los Alamos, NM (United States); Koning, A.J. [Nuclear Research and Consultancy Group, Petten (Netherlands); Leal, L. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); and others

    2014-06-15

    The OECD Nuclear Energy Agency (NEA) organizes cooperation between the major nuclear data evaluation projects in the world. The NEA Working Party on International Nuclear Data Evaluation Cooperation (WPEC) was established to promote the exchange of information on nuclear data evaluation, measurement, nuclear model calculation, validation, and related topics, and to provide a framework for cooperative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint activities in the framework of dedicated WPEC subgroups. Studies recently completed comprise a number of works related to nuclear data covariance and associated processing issues, as well as more specific studies related to the resonance parameter representation in the unresolved resonance region, the gamma production from fission product capture reactions, the {sup 235}U capture cross section, the EXFOR database, and the improvement of nuclear data for advanced reactor systems. Ongoing activities focus on the evaluation of {sup 239}Pu in the resonance region, scattering angular distribution in the fast energy range, and reporting/usage of experimental data for evaluation in the resolved resonance region. New activities include two subgroups on improved fission product yield evaluation methodologies and on modern nuclear database structures. Future activities under discussion include a pilot project for a Collaborative International Evaluated Library Organization (CIELO) and methods to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data. In addition to the above mentioned short-term task-oriented subgroups, WPEC also hosts a longer-term subgroup charged with reviewing and compiling the most important nuclear data requirements in a high priority request list (HPRL)

  2. Nuclear Structure Data Evaluation and the US Nuclear Data Program

    Science.gov (United States)

    Helmer, Richard G.

    2001-10-01

    The United States Nuclear Data Program and the Nuclear Structure and Decay Data network of the International Atomic Energy Agency work in collaboration to provide recommended nuclear structure and decay data for use in basic and applied research. Data are evaluted for nuclear levels and for various types of radiation. In addition, an extensive bibliographic database of nuclear structure, reaction, and decay data references is maintained. The databases maintained by the National Nuclear Data Center at Brookhaven National Laboratory include the Evaluated Nuclear Structure Data File (ENSDF), the Experimental Unevaluated Nuclear Data Library (XUNDL), and the Nuclear Sciences References (NSR). These data are all available via the Internet and some are available in hard-copy. Although the data in the ENSDF database for a particular nucleus has often not been updated in the last few fears, XUNDL provides compiled experimental data from papers with a delay of only about one month. Also, the NSR bibliographic database is current for the many journals that are monitored regularly.

  3. Comparative analysis of dosimetry parameters for nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Toohey, R.E.; Stabin, M.G. [Oak Ridge Inst. for Science and Education, TN (United States)

    1999-01-01

    For years many have employed the concept of ``total-body dose`` or ``whole-body dose,`` i.e., the total energy deposited in the body divided by the mass of the body, when evaluating the risks of different nuclear medicine procedures. The effective dose equivalent (H{sub E}), first described in ICRP Publication 26, has been accepted by some as a better quantity to use in evaluating the total risk of a procedure, but its use has been criticized by others primarily because the tissue weighting factors were intended for use in the radiation worker, rather than the nuclear medicine patient population. Nevertheless, in ICRP Publication 52, the ICRP has suggested that the H{sub E} may be used in nuclear medicine. The ICRP also has published a compendium of dose estimates, including H{sub E} values, for various nuclear medicine procedures at various ages in ICRP Publication 53. The effective dose (E) of ICRP Publication 60 is perhaps more suitable for use in nuclear medicine, with tissue weighting factors based on the entire population. Other comparisons of H{sub E} and E have been published. The authors have used the program MIRDOSE 3.1 to compute total-body dose, H{sub E}, and E for 62 radiopharmaceutical procedures, based on the best current biokinetic data available.

  4. Cytological evaluation of thyroid lesions by nuclear morphology and nuclear morphometry

    Directory of Open Access Journals (Sweden)

    R Yashaswini

    2017-01-01

    Full Text Available Introduction: Fine needle aspiration (FNA of the thyroid gland is an effective diagnostic method. The Bethesda system for reporting thyroid cytopathology classifies them into six categories and gives implied risk for malignancy and management protocol in each category. Though the system gives specific criteria, diagnostic dilemma still exists. Using nuclear morphometry, we can quantify the number of parameters, such as those related to nuclear size and shape. The evaluation of nuclear morphometry is not well established in thyroid cytology. Objective: To classify thyroid lesions on fine needle aspiration cytology (FNAC using Bethesda system and to evaluate the significance of nuclear parameters in improving the prediction of thyroid malignancy. Materials and Methods: In the present study, 120 FNAC cases of thyroid lesions with histological diagnosis were included. Computerized nuclear morphometry was done on 81 cases which had confirmed cytohistological correlation, using Aperio computer software. One hundred nuclei from each case were outlined and eight nuclear parameters were analyzed. Results: In the present study, thyroid lesions were common in female with M: F ratio of 1:5 and most commonly in 40–60 yrs. Under Bethesda system, 73 (60.83% were category II; 14 (11.6% were category III, 3 (2.5% were category IV, 8 (6.6% were category V, and 22 (18.3% were category VI, which were malignant on histopathological correlation. Sensitivity, specificity, and diagnostic accuracy of Bethesda reporting system are 62.5, 84.38, and 74.16%, respectively. Minimal nuclear diameter, maximal nuclear diameter, nuclear perimeter, and nuclear area were higher in malignant group compared to nonneoplastic and benign group. Conclusion: The Bethesda system is a useful standardized system of reporting thyroid cytopathology. It gives implied risk of malignancy. Nuclear morphometry by computerized image analysis can be utilized as an additional diagnostic tool.

  5. Cytological Evaluation of Thyroid Lesions by Nuclear Morphology and Nuclear Morphometry.

    Science.gov (United States)

    Yashaswini, R; Suresh, T N; Sagayaraj, A

    2017-01-01

    Fine needle aspiration (FNA) of the thyroid gland is an effective diagnostic method. The Bethesda system for reporting thyroid cytopathology classifies them into six categories and gives implied risk for malignancy and management protocol in each category. Though the system gives specific criteria, diagnostic dilemma still exists. Using nuclear morphometry, we can quantify the number of parameters, such as those related to nuclear size and shape. The evaluation of nuclear morphometry is not well established in thyroid cytology. To classify thyroid lesions on fine needle aspiration cytology (FNAC) using Bethesda system and to evaluate the significance of nuclear parameters in improving the prediction of thyroid malignancy. In the present study, 120 FNAC cases of thyroid lesions with histological diagnosis were included. Computerized nuclear morphometry was done on 81 cases which had confirmed cytohistological correlation, using Aperio computer software. One hundred nuclei from each case were outlined and eight nuclear parameters were analyzed. In the present study, thyroid lesions were common in female with M: F ratio of 1:5 and most commonly in 40-60 yrs. Under Bethesda system, 73 (60.83%) were category II; 14 (11.6%) were category III, 3 (2.5%) were category IV, 8 (6.6%) were category V, and 22 (18.3%) were category VI, which were malignant on histopathological correlation. Sensitivity, specificity, and diagnostic accuracy of Bethesda reporting system are 62.5, 84.38, and 74.16%, respectively. Minimal nuclear diameter, maximal nuclear diameter, nuclear perimeter, and nuclear area were higher in malignant group compared to nonneoplastic and benign group. The Bethesda system is a useful standardized system of reporting thyroid cytopathology. It gives implied risk of malignancy. Nuclear morphometry by computerized image analysis can be utilized as an additional diagnostic tool.

  6. Three-dimensional Monte Carlo calculation of some nuclear parameters

    Science.gov (United States)

    Günay, Mehtap; Şeker, Gökmen

    2017-09-01

    In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel structural material and the molten salt-heavy metal mixtures 99-95% Li20Sn80 + 1-5% RG-Pu, 99-95% Li20Sn80 + 1-5% RG-PuF4, and 99-95% Li20Sn80 + 1-5% RG-PuO2, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion-fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. This study analyzes the nuclear parameters such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones and investigates effects of reactor grade Pu content in the designed system on these nuclear parameters. Three-dimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.

  7. Dynamic testing of nuclear power plant structures: an evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Weaver, H.J.

    1980-02-01

    Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes work in three main areas: (1) analytical qualification of a set of computer programs developed at LLL to extract model parameters from the time histories; (2) examination of the feasibility of safely exciting nuclear power plant structures and accurately recording the resulting time-history motions; (3) study of how the model parameters that are extracted from the data be used best to evaluate structural integrity and analyze nuclear power plants.

  8. Genetic algorithm for nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Arthur, Jennifer Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-02-02

    These are slides on genetic algorithm for nuclear data evaluation. The following is covered: initial population, fitness (outer loop), calculate fitness, selection (first part of inner loop), reproduction (second part of inner loop), solution, and examples.

  9. Towards consistent nuclear models and comprehensive nuclear data evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Bouland, O [Los Alamos National Laboratory; Hale, G M [Los Alamos National Laboratory; Lynn, J E [Los Alamos National Laboratory; Talou, P [Los Alamos National Laboratory; Bernard, D [FRANCE; Litaize, O [FRANCE; Noguere, G [FRANCE; De Saint Jean, C [FRANCE; Serot, O [FRANCE

    2010-01-01

    The essence of this paper is to enlighten the consistency achieved nowadays in nuclear data and uncertainties assessments in terms of compound nucleus reaction theory from neutron separation energy to continuum. Making the continuity of theories used in resolved (R-matrix theory), unresolved resonance (average R-matrix theory) and continuum (optical model) rangcs by the generalization of the so-called SPRT method, consistent average parameters are extracted from observed measurements and associated covariances are therefore calculated over the whole energy range. This paper recalls, in particular, recent advances on fission cross section calculations and is willing to suggest some hints for future developments.

  10. 78 FR 56749 - Site Characteristics and Site Parameters for Nuclear Power Plants

    Science.gov (United States)

    2013-09-13

    ... COMMISSION Site Characteristics and Site Parameters for Nuclear Power Plants AGENCY: Nuclear Regulatory... NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants... Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition. The proposed changes to the SRP...

  11. International Cooperation in Nuclear Data Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Herman, M.; Herman, M.; Katakura, J.; Koning, A. J.; Nordborg, C.

    2011-08-01

    The OECD Nuclear Energy Agency (NEA) is organising a co-operation between the major nuclear data evaluation projects in the world. The co-operation involves the ENDF, JEFF, and JENDL projects, and, owing to the collaboration with the International Atomic Energy Agency (IAEA), also the Russian BROND and the Chinese CENDL projects. The Working Party on international nuclear data Evaluation Cooperation (WPEC), comprised of about 20 core members, manages this co-operation and meets annually to discuss progress in each evaluation project and also related experimental activities. The WPEC assesses common needs for nuclear data improvements and these needs are then addressed by initiating joint evaluation efforts. The work is performed in specially established subgroups, consisting of experts from the participating evaluation projects. The outcome of these subgroups is published in reports, issued by the NEA. Current WPEC activities comprise for example a number of studies related to nuclear data uncertainties, including a review of methods for the combined use of integral experiments and covariance data, as well as evaluations of some of the major actinides, such as {sup 235}U and {sup 239}Pu. This paper gives an overview of current and planned activities within the WPEC.

  12. The NUBASE2016 evaluation of nuclear properties

    Science.gov (United States)

    Audi, G.; Kondev, F. G.; Wang, Meng; Huang, W. J.; Naimi, S.

    2017-03-01

    This paper presents the NUBASE2016 evaluation that contains the recommended values for nuclear and decay properties of 3437 nuclides in their ground and excited isomeric (T1/2 >= 100 ns) states. All nuclides for which any experimental information is known were considered. NUBASE2016 covers all data published by October 2016 in primary (journal articles) and secondary (mainly laboratory reports and conference proceedings) references, together with the corresponding bibliographical information. During the development of NUBASE2016, the data available in the 'Evaluated Nuclear Structure Data File' (ENSDF) database were consulted and critically assessed for their validity and completeness. Furthermore, a large amount of new data and some older experimental results that were missing from ENSDF were compiled, evaluated and included in NUBASE2016. The atomic mass values were taken from the 'Atomic Mass Evaluation' (AME2016, second and third parts of the present issue). In cases where no experimental data were available for a particular nuclide, trends in the behavior of specific properties in neighboring nuclides (TNN) were examined. This approach allowed to estimate values for a range of properties that are labeled in NUBASE2016 as 'non-experimental' (flagged '#'). Evaluation procedures and policies used during the development of this database are presented, together with a detailed table of recommended values and their uncertainties. AMDC: http://amdc.impcas.ac.cn/ Contents The NUBASE2016 evaluation of nuclear propertiesAcrobat PDF (1.1 MB) Table I. The NUBASE2016 table of nuclear and decay propertiesAcrobat PDF (706 KB)

  13. Evaluation of microbiological and chemical parameters during ...

    African Journals Online (AJOL)

    Devika

    1 -Corresponding Author: Dr. EdrissBazrafshan, Department of Environmental Health, school of Health, Zahedan. University of Medical ... Evaluation of microbiological and chemical parameters during wastewater Sludge and. Sawdust Co-composting. 1 ..... the environmental impact of municipal solid waste management.

  14. Computer program system for evaluation of FP nuclear data for JENDL. Smooth part

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Watanabe, Takashi; Iijima, Shungo

    1997-12-01

    This report describes computer programs used to evaluate nuclear data of fission product (FP) nuclides stored in an evaluated nuclear data library JENDL, especially in the smooth part above the resonance region. Many programs were used for determination of nuclear model parameters, calculation of nuclear data, handling of experimental and/or calculated data, and so on. Among them, reported here are programs for determination of level density parameters (ENSDFRET, LVLPLOT, LEVDES), for making sets of JCL and input data for the theoretical calculation program CASTHY (JOBSETTER, INDES/CASTHY), and for conversion of format of CASTHY output files to the ENDF format (CTOB2). (author). 51 refs.

  15. Radiographic adenoid evaluation - suggestion of referral parameters

    Directory of Open Access Journals (Sweden)

    Murilo F.N. Feres

    2014-06-01

    Full Text Available OBJECTIVE: this study aimed to evaluate the usefulness of current radiographic measurements, which were originally conceived to evaluate adenoid hypertrophy, as potential referral parameters. METHODS: children aged from 4 to 14 years, of both genders, who presented nasal obstruction complaints, were subjected to cavum radiography. Radiographic examinations (n = 120 were evaluated according to categorical and quantitative parameters, and data were compared to gold-standard videonasopharyngoscopic examination, regarding accuracy (sensitivity, negative predictive value, specificity, and positive predictive value. RESULTS: radiographic grading systems presented low sensitivity for the identification of patients with two-thirds choanal space obstruction. However, some of these parameters presented relatively high specificity rates when three-quarters adenoid obstruction was the threshold of interest. Amongst the quantitative variables, a mathematical model was found to be more suitable for identifying patients with more than two-thirds obstruction. CONCLUSION: this model was shown to be potentially useful as a screening tool to include patients with, at least, two-thirds adenoid obstruction. Moreover, one of the categorical parameters was demonstrated to be relatively more useful, as well as a potentially safer assessment tool to exclude patients with less than three-quarters obstruction, to be indicated for adenoidectomy.

  16. Nuclear matter equation of state and σ-meson parameters

    Indian Academy of Sciences (India)

    Author Affiliations. A B Santra1 U Lambardo2. Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai 400 085, India; Dipartimento di Fisica, Universita di Catania and INFN-LNS, Via S. Sofia 44, I-95123 Catania, Italy ...

  17. Impact of New Nuclear Data Libraries on Small Sized Long Life CANDLE HTGR Design Parameters

    Science.gov (United States)

    Liem, Peng Hong; Hartanto, Donny; Tran, Hoai Nam

    2017-01-01

    The impact of new evaluated nuclear data libraries (JENDL-4.0, ENDF/B-VII.0 and JEFF-3.1) on the core characteristics of small-sized long-life CANDLE High Temperature Gas-Cooled Reactors (HTGRs) with uranium and thorium fuel cycles was investigated. The most important parameters of the CANDLE core characteristics investigated here covered (1) infinite multiplication factor of the fresh fuel containing burnable poison, (2) the effective multiplication factor of the equilibrium core, (3) the moving velocity of the burning region, (4) the attained discharge burnup, and (5) the maximum power density. The reference case was taken from the current JENDL-3.3 results. For the uranium fuel cycle, the impact of the new libraries was small, while significant impact was found for thorium fuel cycle. The findings indicated the needs of more accurate nuclear data libraries for nuclides involved in thorium fuel cycle in the future.

  18. Mean nuclear volume

    DEFF Research Database (Denmark)

    Mogensen, O.; Sørensen, Flemming Brandt; Bichel, P.

    1999-01-01

    We evaluated the following nine parameters with respect to their prognostic value in females with endometrial cancer: four stereologic parameters [mean nuclear volume (MNV), nuclear volume fraction, nuclear index and mitotic index], the immunohistochemical expression of cancer antigen (CA125...

  19. TENDL-2011: TALYS-based Evaluated Nuclear Data Library

    Energy Technology Data Exchange (ETDEWEB)

    Rochman, D.; Koning, A. J. [Nuclear Research and Consultancy Group, Petten (Netherlands)

    2012-07-01

    The 4. release of the TENDL library, TENDL-2011 (TALYS-based Evaluated Nuclear Data Library) is described. This library consists of a complete set of nuclear reaction data for incident neutrons, photons, protons, deuterons, tritons, helions and alpha particles, from 10-5 eV up to 200 MeV, for all isotopes from {sup 6}Li to {sup 281}Ds that are either stable of have a half-life longer than 1 second. All data are completely and consistently evaluated using a software system consisting of the TALYS-1.2 nuclear reaction code, and other programs to handle resonance data, experimental data, data from existing evaluations, and to provide the final ENDF-6 formatting. The result is a nuclear data library with mutually consistent reaction information for all isotopes and a quality that increases with yearly updates. To produce this library, TALYS input parameters are adjusted for many nuclides so that calculated cross sections agree with experimental data, while for important nuclides experimental data are directly included. All information is available on www.talys.eu and www.talys.eu/TENDL-2011. (authors)

  20. Comparison for some measured and calculated nuclear Parameters ...

    African Journals Online (AJOL)

    1994-12-17

    A 30 kW tank-in pool reactor, Ghana Research Reactor-1 (GHARR-1), installed at the National Nuclear Research Institute, Kwabenya, went critical on December 17, 1994. GHARR-1 is an inherently safe reactor employing Highly Enriched Uranium (HEU) as fuel, light water as moderator and beryllium as reflector. Reactor ...

  1. The NUBASE2016 evaluation of nuclear properties

    Energy Technology Data Exchange (ETDEWEB)

    Audi, G.; Kondev, F. G.; Wang, Meng; Huang, W. J.; Naimi, S.

    2017-03-01

    This paper presents the NUBASE2016 evaluation that contains the recommended values for nuclear and decay properties of 3437 nuclides in their ground and excited isomeric (T1/2≥100 ns) states. All nuclides for which any experimental information is known were considered. NUBASE2016 covers all data published by October 2016 in primary (journal articles) and secondary (mainly laboratory reports and conference proceedings) references, together with the corresponding bibliographical information. During the development of NUBASE2016, the data available in the “Evaluated Nuclear Structure Data File” (ENSDF) database were consulted and critically assessed for their validity and completeness. Furthermore, a large amount of new data and some older experimental results that were missing from ENSDF were compiled, evaluated and included in NUBASE2016. The atomic mass values were taken from the “Atomic Mass Evaluation” (AME2016, second and third parts of the present issue). In cases where no experimental data were available for a particular nuclide, trends in the behavior of specific properties in neighboring nuclides (TNN) were examined. This approach allowed to estimate values for a range of properties that are labeled in NUBASE2016 as “non-experimental” (flagged “#”). Evaluation procedures and policies used during the development of this database are presented, together with a detailed table of recommended values and their uncertainties. AMDC: http://amdc.impcas.ac.cn/

  2. Criticality parameters for tank waste evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.A.; Harris, H.

    1996-08-21

    A summary is provided of basic parameters used to evaluate criticality safety of high-level tank waste at the Hanford Site.Critical sizes and plutonium concentrations are based on a conservative waste model with reduced neutron absorption and optimized water. Figures were provided of sphere and slab minimum critical dimensions and plutonium critical masses.Minimum subcritical limit absorber/plutonium mass ratios are provided for selected waste components. Component contributions to subcriticality can be combined by adding the individual actual-to-minimum subcritical mass fractions. A discussion is provided of the margin of safety inherent in tank waste.

  3. Introducing Nuclear Data Evaluations of Prompt Fission Neutron Spectra

    Energy Technology Data Exchange (ETDEWEB)

    Neudecker, Denise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    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.

  4. Parameter Study for Optimizing the Mass of a Space Nuclear Power System Radiation Shield

    National Research Council Canada - National Science Library

    Kowash, Benjamin

    2002-01-01

    A parameter study was conducted for a space nuclear reactor radiation shield. The focus of this research was to explore alternatives to current radiation shield designs to reduce the mass while maintaining the same shielding performance...

  5. Nuclear Structure and Decay Data Evaluation: Status and Perspectives

    Science.gov (United States)

    Kondev, F. G.; Browne, E.; Ouellet, C.; Pritychenko, B.; Reich, C.; Sonzogni, A.; Tandel, S.; Tuli, J. K.; Cameron, J.; Chen, A.; Singh, B.; Kelley, J.; Kwan, E.; Baglin, C.; Basunia, M. S.; Firestone, R. B.; Nica, N.; Nesaraja, C. D.; Smith, M. S.

    2009-10-01

    Reliable nuclear structure data represent the fundamental building blocks of nuclear structure physics and astrophysics research, and are also of vital importance in a large number of applications. Members of the Nuclear Structure and Decay Data Working Group of the U.S. Nuclear Data Program, in collaboration with scientists from Japan and other countries within the International Nuclear Structure and Decay Data Network (under the auspices of IAEA), are involved in compilation, evaluation, and dissemination of nuclear structure and decay data for all known nuclei. The network's principal effort is devoted to the timely revision of information in the Evaluated Nuclear Structure Data File (ENSDF) library, which is the only comprehensive nuclear structure and decay data database that is updated continuously. This presentation will briefly review recent achievements of the network, present on-going activities, and reflect on ideas for future projects and challenges in the field of nuclear structure and decay data evaluation.

  6. Nuclear Structure and Decay Data Evaluation: Challenges and Perspectives

    Science.gov (United States)

    Kondev, F. G.; Tuli, J. K.

    2003-10-01

    The expression ``Nuclear Structure and Decay Data'' refers to complex nuclear level schemes and tables of numerical values, which quantify fundamental properties of nuclear structure, such as level energies, quantum numbers and state lifetimes, as well as various decay modes and associated radiation. These data are not only at the core of basic nuclear structure and nuclear astrophysics research, but they are also relevant for many applied technologies, including nuclear energy production, reactor design and safety, medical diagnostic and radiotherapy, health physics, environmental research and monitoring, safeguards, material analysis, etc. The mission of the Nuclear Structure and Decay Data Working Group of the US DOE funded Nuclear Data Program is to evaluate, compile, maintain, and disseminate nuclear structure and decay data for all known nuclei (more than 2900!). The network's principal effort is devoted to the timely revision of information in the ENSDF (Evaluated Nuclear Structure Data File) database. However, in recent years, special attention has been given to topical evaluations of properties of particular interest to the nuclear structure community, such as log ft values, α- and proton decay properties, super-deformed and magnetic dipole collective structures, nuclear moments, and nuclear isomers (under development). This presentation will briefly review recent achievements of the network, present on-going activities, and reflect on ideas for future projects and challenges in the field of nuclear structure and decay data evaluation.

  7. Vibroacoustic test plan evaluation: Parameter variation study

    Science.gov (United States)

    Stahle, C. V.; Gongloef, H. R.

    1976-01-01

    Statistical decision models are shown to provide a viable method of evaluating the cost effectiveness of alternate vibroacoustic test plans and the associated test levels. The methodology developed provides a major step toward the development of a realistic tool to quantitatively tailor test programs to specific payloads. Testing is considered at the no test, component, subassembly, or system level of assembly. Component redundancy and partial loss of flight data are considered. Most and probabilistic costs are considered, and incipient failures resulting from ground tests are treated. Optimums defining both component and assembly test levels are indicated for the modified test plans considered. modeling simplifications must be considered in interpreting the results relative to a particular payload. New parameters introduced were a no test option, flight by flight failure probabilities, and a cost to design components for higher vibration requirements. Parameters varied were the shuttle payload bay internal acoustic environment, the STS launch cost, the component retest/repair cost, and the amount of redundancy in the housekeeping section of the payload reliability model.

  8. TRITOX: a multiple parameter evaluation of tritium toxicity

    Energy Technology Data Exchange (ETDEWEB)

    Carsten, A.L.

    1982-01-01

    The increased use of nuclear reactors for power generation will lead to the introduction of tritium into the environment. The need for assessing possible immediate and long-term effects of exposure to this tritium led to the development of a broad program directed towards evaluating the possible somatic and genetic effects of continuous exposure to tritiated water (HTO). Among the parameters measured are the genetic, cytogenetic, reproductive efficiency, growth, nonspecific lifetime shortening, bone marrow cellularity and stem cell content, relative biological effectiveness as compared to /sup 137/Cesium gamma exposure, and related biochemical and microdosimetric evaluations. These parameters have been evaluated on animals maintained on HTO at 10 to 100 times the maximum permissible concentration (0.03 - 3.0 ..mu..Ci/ml) for HTO. Dominant lethal mutations, chromosome aberrations in regenerating liver, increased sister chromatid exchanges in bone marrow and reduction in bone marrow stem cell content have been observed at the higher concentrations. The relative biological effectiveness for HTO ingestion as compared to external /sup 137/Cesium gamma exposures has been found to be between 1 and 2.

  9. Evaluating intensity parameters for debris flow vulnerability

    Science.gov (United States)

    Keiler, Margreth

    2014-05-01

    In mountain regions natural hazard processes such as debris flows or hyper-concentrated flows repeatedly lead to high damages. After an event, detailed documentation of the meteorological, hydrological and geomorphological indicators are standardized, and additional data on debris covering run out areas, indicators for processes velocity and transported volumes are gathered. Information on deposition height of debris is an important parameter to estimate the intensity of the process impacting the buildings and infrastructure and hence to establish vulnerability curves. However, the deposition height of mobilized material in settlements and on infrastructure is mostly not directly evaluated because recovery work starts immediately or even during the event leading to a removal of accumulated material. Different approaches exist to reconstruct deposition heights after torrent events, such as mind mapping, comparison of LIDAR-based DEM before and after the event as well as the reconstruction by using photo documentation and the estimation of deposition heights according to standardised elements at buildings and infrastructure. In our study, these different approaches to estimate deposition height and the spatial distribution of the accumulated material are applied and compared against each other by using the case study of the debris flow event in Brienz (Switzerland) which occurred during the serve flood events of August 2005 in the Alps. Within the analysis, different factors including overall costs and time consumption (manpower, equipment), accuracy and preciseness are compared and evaluated to establish optimal maps of the extent and deposition depth after torrent events and to integrate this information in the vulnerability analysis.

  10. Parameter Study of the LIFE Engine Nuclear Design

    Energy Technology Data Exchange (ETDEWEB)

    Kramer, K J; Meier, W R; Latkowski, J F; Abbott, R P

    2009-07-10

    LLNL is developing the nuclear fusion based Laser Inertial Fusion Energy (LIFE) power plant concept. The baseline design uses a depleted uranium (DU) fission fuel blanket with a flowing molten salt coolant (flibe) that also breeds the tritium needed to sustain the fusion energy source. Indirect drive targets, similar to those that will be demonstrated on the National Ignition Facility (NIF), are ignited at {approx}13 Hz providing a 500 MW fusion source. The DU is in the form of a uranium oxycarbide kernel in modified TRISO-like fuel particles distributed in a carbon matrix forming 2-cm-diameter pebbles. The thermal power is held at 2000 MW by continuously varying the 6Li enrichment in the coolants. There are many options to be considered in the engine design including target yield, U-to-C ratio in the fuel, fission blanket thickness, etc. Here we report results of design variations and compare them in terms of various figures of merit such as time to reach a desired burnup, full-power years of operation, time and maximum burnup at power ramp down and the overall balance of plant utilization.

  11. Nuclear magnetic and nuclear quadrupole resonance parameters of β-carboline derivatives calculated using density functional theory

    Science.gov (United States)

    Ahmadinejad, Neda; Tari, Mostafa Talebi

    2017-04-01

    A density functional theory (DFT) calculations using B3LYP/6-311++G( d,p) method were carried out to investigate the relative stability of the molecules of β-carboline derivatives such as harmaline, harmine, harmalol, harmane and norharmane. Calculated nuclear quadrupole resonance (NQR) parameters were used to determine the 14N nuclear quadrupole coupling constant χ, asymmetry parameter η and EFG tensor ( q zz ). For better understanding of the electronic structure of β-carboline derivatives, natural bond orbital (NBO) analysis, isotropic and anisotropic NMR chemical shieldings were calculated for 14N nuclei using GIAO method for the optimized structures. The NBO analysis shows that pyrrole ring nitrogen (N9) atom has greater tendency than pyridine ring nitrogen (N2) atom to participate in resonance interactions and aromaticity development in the all of these structures. The NMR and NQR parameters were studied in order to find the correlations between electronic structure and the structural stability of the studied molecules.

  12. INPRO Methodology to evaluate the Mexico nuclear energy system; Metodologia INPRO para evaluar el sistema de energia nuclear de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Cruz S, R. R.; Martin del C, C., E-mail: crzslns.ricardoruben@gmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2016-09-15

    The International Atomic Energy Agency has developed the so-called International Project on Fuel Cycles and Innovative Nuclear Reactors (INPRO), in order to make nuclear energy available to meet the energy needs of the 21 century, in a sustainable way. One of the tasks of the project is the evaluation of the nuclear systems, to check whether they meet the objectives of the project and whether they are sustainable. This paper explains the rationale and general characteristics of the project in the evaluation of nuclear energy systems based on the concept of sustainable development. It describes the methodology developed to carry out this evaluation, divided into seven areas, such as economic, environmental, security, etc., which together make up the sustainable development of energy through nuclear systems. The economic area is analyzed and the evaluation criteria and parameters established by INPRO are discussed, in order to evaluate the Mexican nuclear energy system using Nest (software developed within the same project) as a tool to support the economic evaluation of nuclear systems. Based on the energy strategy proposed by the Energy Secretary of the Mexican Government which seeks to reduce the greenhouse gas emissions from the national electricity generation park, two types of reactor of currently available technology (A BWR and AP1000), were compared and these in turn with other alternative energy generation technologies, such as combined cycle, geothermal and wind plants. Also, the results of the application of the INPRO methodology are presented. Finally, the recommendations on actions that could lead the Mexican nuclear energy system towards sustainable development and conclusions on the application of the methodology to the Mexican case are mentioned. (Author)

  13. Nuclear imaging evaluation of galactosylation of chitosan

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Hwan Jeong; Kim, Eun Mi; Kim, Chang Guhn [School of Medicine, Wonkwang Univ., Iksan (Korea, Republic of); Park, In Kyu; Cho, Chong Su [Seoul National Univ., Seoul (Korea, Republic of); Bom, Hee Seung [School of Medicine, Chonnam National Univ., Gwangju (Korea, Republic of)

    2004-06-01

    Chitosan has been studied as a non-viral gene delivery vector, drug delivery carrier, metal chelater, food additive, and radiopharmaceutical, among other things. Recently, galactose-graft chitosan was studied as a non-viral gene and drug delivery vector to target hepatocytes. The aim of this study was to investigate the usefulness of nuclear imaging for in vivo evaluation of targeting the hepatocyte by galactose grafting. Galactosyl methylated chitosan (GMC) was produced by methylation to lactobionic acid coupled chitosan Cytotoxicity of {sup 99}mTc-GMC was determined by MTT assay. Rabbits were injected via their auricular vein with {sup 99}mTc-GMC and {sup 99}mTc-methylated chitosan (MC), the latter of which does not contain a galactose group, and images were acquired with a gamma camera equipped with a parallel hole collimator. The composition of the galactose group in galactosylated chitosan (GC), as well as the tri-, di-, or mono-methylation of GMC, was confirmed by NMR spectroscopy. The results of MTT assay indicated that {sup 99}mTc-GMC was non-toxic. {sup 99}mTc-GMC specifically accumulated in the liver within 10 minutes of injection and maintained high hepatic uptake. In contrast, {sup 99}mTc-MC showed faint liver uptake. {sup 99}mTc-GMC scintigraphy of rabbits showed that the galactose ligand principally targeted the liver while the chitosan functionalities led to excretion through the urinary system. Bioconjugation with a specific ligand endows some degree of targetability to an administered molecule or drug, as in the case of galactose for hepatocyte in vivo, and evaluating said targetability is a clear example of the great benefit proffered by nuclear imaging.

  14. Monte Carlo simulation of nuclear energy study (II). Annual report on Nuclear Code Evaluation Committee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-01-01

    In the report, research results discussed in 1999 fiscal year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. Present status of Monte Carlo simulation on nuclear energy study was described. Especially, besides of criticality, shielding and core analyses, present status of applications to risk and radiation damage analyses, high energy transport and nuclear theory calculations of Monte Carlo Method was described. The 18 papers are indexed individually. (J.P.N.)

  15. Feasibility Study on Nuclear Propulsion Ship according to Economic Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Gil, Youngmi; Yoo, Seongjin; Oh, June; Byun, Yoonchul; Woo, Ilguk [Daewoo Shipbuilding and Marine Engineering Co., Ltd, Seoul (Korea, Republic of); Kim, Jiho; Choi, Suhn [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The use of nuclear ships has been extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, the relevant regulations need to be considered. In this study, we reviewed the nuclear ship-related regulations. In addition, economic value is one of the most important factors which should be considered in the pre-design phase. To evaluate the economics of the nuclear ship, we calculated Capital Expenditure (abbreviated as CAPEX) and Operation Expenditure (abbreviated as OPEX) for various types of ships. We reviewed the nuclear ship-related regulations and evaluated the economics of the nuclear ship compared to the diesel ship. The calculation result shows that economic feasibility of the nuclear ship depends on the oil price as well as the cost of the nuclear reactor.

  16. Population parameters and mito-nuclear mosaicism of Anisakis spp. in the Adriatic Sea.

    Science.gov (United States)

    Mladineo, Ivona; Bušelić, Ivana; Hrabar, Jerko; Vrbatović, Anamarija; Radonić, Ivana

    2017-03-01

    Recombinant genotypes of A. simplex sensu stricto (s.s.) and A. pegreffii, two species of Anisakis simplex complex found in sympatric waters of the Mediterranean Sea, are believed to be a product of interspecific hybridisation and/or DNA introgression. In contrast, such events within an allopatric area as the Adriatic Sea are unlikely to occur and therefore observed recombination should be assessed more closely. We have genotyped 525 anisakids collected from migratory and non-migratory fish of the southern part of the Adriatic Sea, inferring its omniparentage at nuclear (ITS locus) and matrilineage at mitochondrial locus (cox2). The aim was to address the presence and cause of the recombination within the population and to test its genetic structure under admixture theory. Population parameters, i.e. prevalence, and mean abundance and intensity of anisakids were also evaluated to contribute for future epidemiological risk assessments. As a result, we have inferred the presence of A. pegreffii, A. typica and A. ziphidarum in the Adriatic, lacking type species A. simplex s.s. at both nuclear and mitochondrial locus. A. pegreffii population shows a high level of admixture and heterogeneity and a recent demographic expansion from a small population size. We argue that the observed recombinant genotypes in the Adriatic are a product of ancestral polymorphism and consequent remote genetic introgression. Copyright © 2017 Elsevier B.V. All rights reserved.

  17. Evaluated Nuclear Structure Data File and Related Products

    Science.gov (United States)

    Tuli, Jagdish K.

    2005-05-01

    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.

  18. EXTENSION OF THE NUCLEAR REACTION MODEL CODE EMPIRE TO ACTINIDES NUCLEAR DATA EVALUATION.

    Energy Technology Data Exchange (ETDEWEB)

    CAPOTE,R.; SIN, M.; TRKOV, A.; HERMAN, M.; CARLSON, B.V.; OBLOZINSKY, P.

    2007-04-22

    Recent extensions and improvements of the EMPIRE code system are outlined. They add new capabilities to the code, such as prompt fission neutron spectra calculations using Hauser-Feshbach plus pre-equilibrium pre-fission spectra, cross section covariance matrix calculations by Monte Carlo method, fitting of optical model parameters, extended set of optical model potentials including new dispersive coupled channel potentials, parity-dependent level densities and transmission through numerically defined fission barriers. These features, along with improved and validated ENDF formatting, exclusive/inclusive spectra, and recoils make the current EMPIRE release a complete and well validated tool for evaluation of nuclear data at incident energies above the resonance region. The current EMPIRE release has been used in evaluations of neutron induced reaction files for {sup 232}Th and {sup 231,233}Pa nuclei in the fast neutron region at IAEA. Triple-humped fission barriers and exclusive pre-fission neutron spectra were considered for the fission data evaluation. Total, fission, capture and neutron emission cross section, average resonance parameters and angular distributions of neutron scattering are in excellent agreement with the available experimental data.

  19. Some practical limits on achievable precision of determination of nuclear-physics parameters

    OpenAIRE

    Sukhovoj, A. M.; Khitrov, V. A.

    2011-01-01

    The status of experiments on determination of level density and partial widths of the nuclear reaction products emission in diapason of nucleon binding energy is presented. There are analyzed the sources and magnitude of probable systematical uncertainties of their determination. The maximally achievable precision of these parameters is estimated, as well. There is considered ability of new method for determination of distribution parameters of neutron resonances reduced widths in order to di...

  20. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

    2013-09-30

    This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

  1. CENDL project, the chinese evaluated nuclear data library

    Science.gov (United States)

    Ge, Zhigang; Wu, Haicheng; Chen, Guochang; Xu, Ruirui

    2017-09-01

    The status of Chinese Evaluated Nuclear Data Library (CENDL) and the relevant CENDL project are introduced in this paper. Recently, a new version CENDL-3.2b0 was being prepared on the basis of the previous CENDL-3.1. The data in the light and actinide nuclide regions are updated from CENDL-3.1, and the new evaluations and calculations are performed mainly around structure and fission product nuclide regions. Covariance was also evaluated for structure and actinide nuclides. At the same time, the methodologies are systematically developed to fulfil the requirements of evaluations for CENDL-3.2b0. The updated nuclear reaction models for light and middle-heavy nuclides, non-model dependent nuclear data evaluation, covariance evaluation approaches, systematics, and integral validation system of nuclear data are incorporated in present CENDL project. The future developments are also planned.

  2. Comparing the sustainability parameters of renewable, nuclear and fossil fuel electricity generation technologies

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Annette; Strezov, Vladimir; Evans, Tim

    2010-09-15

    The sustainability parameters of electricity generation have been assessed by the application of eight key indicators. Photovoltaics, wind, hydro, geothermal, biomass, natural gas, coal and nuclear power have been assessed according to their price, greenhouse gas emissions, efficiency, land use, water use, availability, limitations and social impacts on a per kilowatt hour basis. The relevance of this information to the Australian context is discussed. Also included are the results of a survey on Australian opinions regarding electricity generation, which found that Australian prefer solar electricity above any other method, however coal, biomass and nuclear power have low acceptance.

  3. Study of nuclear physics input-parameters via high-resolution γ-ray spectroscopy

    Science.gov (United States)

    Scholz, Philipp; Heim, Felix; Mayer, Jan; Spieker, Mark; Zilges, Andreas

    2018-01-01

    For nucleosynthesis networks of isotopes heavier than those in the iron-peak region, reaction rates are often calculated within the Hauser-Feshbach statistical model. The accuracy of the predicted cross sections strongly depends on the uncertainties of the nuclear-physics input-parameters. These are nuclear-level densities, γ-ray strength functions, and particle+nucleus optical-model potentials. Here we report on the investigation of statistical properties of nuclei via radiative proton-capture reactions using high-resolution γ-ray spectroscopy.

  4. Evaluation Parameters for Computer-Adaptive Testing

    Science.gov (United States)

    Georgiadou, Elisabeth; Triantafillou, Evangelos; Economides, Anastasios A.

    2006-01-01

    With the proliferation of computers in test delivery today, adaptive testing has become quite popular, especially when examinees must be classified into two categories (passfail, master nonmaster). Several well-established organisations have provided standards and guidelines for the design and evaluation of educational and psychological testing.…

  5. Average resonance parameters evaluation for actinides

    Energy Technology Data Exchange (ETDEWEB)

    Porodzinskij, Yu.V.; Sukhovitskij, E.Sh. [Radiation Physics and Chemistry Problems Inst., Minsk-Sosny (Belarus)

    1997-03-01

    New evaluated <{Gamma}{sub n}{sup 0}> and values for {sup 238}U, {sup 237}Np, {sup 243}Cm, {sup 245}Cm, {sup 246}Cm and {sup 241}Am nuclei in the resolved resonance region are presented. The applied method based on the idea that experimental resonance missing results in correlated changes of reduced neutron widths and level spacings distributions is discussed. (author)

  6. Performance evaluation of fiber optic components in nuclear plant environments

    Energy Technology Data Exchange (ETDEWEB)

    Hastings, M.C.; Miller, D.W. [Ohio State Univ., Columbus, OH (United States); James, R.W. [Electric Power Research Institute, Palo Alto, CA (United States)

    1996-03-01

    Over the past several years, the Electric Power Research Institute (EPRI) has funded several projects to evaluate the performance of commercially available fiber optic cables, connective devices, light sources, and light detectors under environmental conditions representative of normal and abnormal nuclear power plant operating conditions. Future projects are planned to evaluate commercially available fiber optic sensors and to install and evaluate performance of instrument loops comprised of fiber optic components in operating nuclear power plant applications. The objective of this research is to assess the viability of fiber optic components for replacement and upgrade of nuclear power plant instrument systems. Fiber optic instrument channels offer many potential advantages: commercial availability of parts and technical support, small physical size and weight, immunity to electromagnetic interference, relatively low power requirements, and high bandwidth capabilities. As existing nuclear power plants continue to replace and upgrade I&C systems, fiber optics will offer a low-cost alternative technology which also provides additional information processing capabilities. Results to date indicate that fiber optics are a viable technology for many nuclear applications, both inside and outside of containments. This work is funded and manage& under the Operations & Maintenance Cost Control research target of EPRI`s Nuclear Power Group. The work is being performed by faculty and students in the Mechanical and Nuclear Engineering Departments and the staff of the Nuclear Reactor Laboratory of the Ohio State University.

  7. Nuclear translocation of Nuclear Factor of Activated T cells (NFAT) as a quantitative pharmacodynamic parameter for tacrolimus

    Science.gov (United States)

    Maguire, Orla; Tornatore, Kathleen M.; O'Loughlin, Kieran L.; Venuto, Rocco C.; Minderman, Hans

    2014-01-01

    Nuclear Factor of Activated T cells (NFAT) is a family of transcription factors involved in regulating the immune response. The canonical NFAT pathway is calcium-dependent and upon activation, NFAT is dephosphorylated by the phosphatase, calcineurin. This results in its translocation from the cytoplasm to the nucleus and transcription of downstream target genes that include the cytokines IL-2, IL-10, and IFNγ. Calcineurin inhibitors including tacrolimus inhibit the NFAT pathway and are used as immunosuppressants in transplant settings to prevent graft rejection. There is, as yet, no direct means to monitor tacrolimus pharmacodynamics. In this study, a rapid, quantitative, image cytometry–based measurement of nuclear translocation of NFAT1 is used to evaluate NFAT activation in T cells and its tacrolimus-induced inhibition. A strong dose-dependent correlation between NFAT1 inhibition and tacrolimus dose is demonstrated in vitro. Time kinetic analysis of NFAT1 inhibition in plasma from stable renal transplant recipients before and after an in vivo dose with tacrolimus correlated with the expected pharmacokinetic profile of tacrolimus. This was further corroborated by analysis of patients' autologous CD4 and CD8 T cells. This is the first report to show that the measurement of NFAT1 activation potential by nuclear translocation can be used as a direct, sensitive, reproducible and quantitative pharmacodynamic readout for tacrolimus action. These results, and the rapid turnaround time for this assay, warrant its evaluation in a larger clinical setting to assess its role in therapeutic drug monitoring of calcineurin inhibitors. PMID:24136923

  8. CRECTJ: a computer program for compilation of evaluated nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1999-09-01

    In order to compile evaluated nuclear data in the ENDF format, the computer program CRECTJ has been developed. CRECTJ has two versions; CRECTJ5 treats the data in the ENDF/B-IV and ENDF/B-V format, and CRECTJ6 the data in the ENDF-6 format. These programs have been frequently used to make Japanese Evaluated Nuclear Data Library (JENDL). This report describes input data and examples of CRECTJ. (author)

  9. Evaluation of parameters in hydrodynamic model

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Tae-Hoon [Hanyang University, Seoul (Korea); Lee, Jong-Wook [Korea Institute of Construction Technology, Koyang (Korea); Jegal, Sun-Dong [Kumho Engineering Company, Anyang (Korea)

    2000-02-29

    Generally speaking, a hydrodynamic model needs a friction coefficient (Manning coefficient or Chezy coefficient) and eddy viscosity. For numerical solution the coefficients are usually determined by recursive calculations. The eddy viscosity in numerical model plays physical diffusion in flow and also acts as numerical viscosity. Hence its value has influence on the stability of numerical solution and for these reasons a consistent evaluation procedure is needed. By using records of stage and discharge in the downstream reach of the Han river, 1-D models (HEC-2 and NETWORK) and 2-D model (SMS), estimated values of Manning coefficient and an empirical equation for eddy viscosity are presented. The computed results are verified through the recorded flow elevation data. (author). 26 refs., 7 tabs., 14 figs.

  10. Classification of hydrological parameter sensitivity and evaluation of parameter transferability across 431 US MOPEX basins

    Science.gov (United States)

    Ren, Huiying; Hou, Zhangshuan; Huang, Maoyi; Bao, Jie; Sun, Yu; Tesfa, Teklu; Ruby Leung, L.

    2016-05-01

    The Community Land Model (CLM) represents physical, chemical, and biological processes of the terrestrial ecosystems that interact with climate across a range of spatial and temporal scales. As CLM includes numerous sub-models and associated parameters, the high-dimensional parameter space presents a formidable challenge for quantifying uncertainty and improving Earth system predictions needed to assess environmental changes and risks. This study aims to evaluate the potential of transferring hydrologic model parameters in CLM through sensitivity analyses and classification across watersheds from the Model Parameter Estimation Experiment (MOPEX) in the United States. The sensitivity of CLM-simulated water and energy fluxes to hydrological parameters across 431 MOPEX basins are first examined using an efficient stochastic sampling-based sensitivity analysis approach. Linear, interaction, and high-order nonlinear impacts are all identified via statistical tests and stepwise backward removal parameter screening. The basins are then classified according to their parameter sensitivity patterns (internal attributes), as well as their hydrologic indices/attributes (external hydrologic factors) separately, using Principal component analysis (PCA) and expectation-maximization (EM) - based clustering approach. Similarities and differences among the parameter sensitivity-based classification system (S-Class), the hydrologic indices-based classification (H-Class), and the Koppen climate classification systems (K-Class) are discussed. Within each parameter sensitivity-based classification system (S-Class) with similar parameter sensitivity characteristics, similar inversion modeling setups can be used for parameter calibration, and the parameters and their contribution or significance to water and energy cycling may also be more transferrable. This classification study provides guidance on identifiable parameters, and on parameterization and inverse model design for CLM but the

  11. Probabilistic Seismic Hazard Characterization and Design Parameters for the Sites of the Nuclear Power Plants of Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Savy, J.B.; Foxall, W.

    2000-01-26

    The U.S. Department of Energy (US DOE), under the auspices of the International Nuclear Safety Program (INSP) is supporting in-depth safety assessments (ISA) of nuclear power plants in Eastern Europe and the former Soviet Union for the purpose of evaluating the safety and upgrades necessary to the stock of nuclear power plants in Ukraine. For this purpose the Hazards Mitigation Center at Lawrence Livermore National Laboratory (LLNL) has been asked to assess the seismic hazard and design parameters at the sites of the nuclear power plants in Ukraine. The probabilistic seismic hazard (PSH) estimates were updated using the latest available data and knowledge from LLNL, the U.S. Geological Survey, and other relevant recent studies from several consulting companies. Special attention was given to account for the local seismicity, the deep focused earthquakes of the Vrancea zone, in Romania, the region around Crimea and for the system of potentially active faults associated with the Pripyat Dniepro Donnetts rift. Aleatory (random) uncertainty was estimated from the available data and the epistemic (knowledge) uncertainty was estimated by considering the existing models in the literature and the interpretations of a small group of experts elicited during a workshop conducted in Kiev, Ukraine, on February 2-4, 1999.

  12. Effects of radioactive fallout from a nuclear power plant accident on electrical parameters

    Science.gov (United States)

    Israelsson, S.; Knudsen, E.

    1986-10-01

    Continuous recordings of atmospheric electric parameters were carried out in Uppsala, Sweden. Because of the accident in the nuclear power plant in Chernobyl, USSR, a rainfall on April 27, 1986, caused a considerable increase of the radioactive background radiation in the surroundings of the recording station. A pronounced influence on the atmospheric electric field, the conductivity of the air, and the space charge density is reported.

  13. Modern Nuclear Data Evaluation with the TALYS Code System

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J., E-mail: koning@nrg.eu [Nuclear Research and Consultancy Group NRG, P.O. Box, 1755 ZG Petten (Netherlands); Rochman, D. [Nuclear Research and Consultancy Group NRG, P.O. Box, 1755 ZG Petten (Netherlands)

    2012-12-15

    This paper presents a general overview of nuclear data evaluation and its applications as developed at NRG, Petten. Based on concepts such as robustness, reproducibility and automation, modern calculation tools are exploited to produce original nuclear data libraries that meet the current demands on quality and completeness. This requires a system which comprises differential measurements, theory development, nuclear model codes, resonance analysis, evaluation, ENDF formatting, data processing and integral validation in one integrated approach. Software, built around the TALYS code, will be presented in which all these essential nuclear data components are seamlessly integrated. Besides the quality of the basic data and its extensive format testing, a second goal lies in the diversity of processing for different type of users. The implications of this scheme are unprecedented. The most important are: 1. Complete ENDF-6 nuclear data files, in the form of the TENDL library, including covariance matrices, for many isotopes, particles, energies, reaction channels and derived quantities. All isotopic data files are mutually consistent and are supposed to rival those of the major world libraries. 2. More exact uncertainty propagation from basic nuclear physics to applied (reactor) calculations based on a Monte Carlo approach: 'Total' Monte Carlo (TMC), using random nuclear data libraries. 3. Automatic optimization in the form of systematic feedback from integral measurements back to the basic data. This method of work also opens a new way of approaching the analysis of nuclear applications, with consequences in both applied nuclear physics and safety of nuclear installations, and several examples are given here. This applied experience and feedback is integrated in a final step to improve the quality of the nuclear data, to change the users vision and finally to orchestrate their integration into simulation codes.

  14. Practice Parameter for Child and Adolescent Forensic Evaluations

    Science.gov (United States)

    Journal of the American Academy of Child & Adolescent Psychiatry, 2011

    2011-01-01

    This Parameter addresses the key concepts that differentiate the forensic evaluation of children and adolescents from a clinical assessment. There are ethical issues unique to the forensic evaluation, because the forensic evaluator's duty is to the person, court, or agency requesting the evaluation, rather than to the patient. The forensic…

  15. The nuclear configurational entropy impact parameter dependence in the Color-Glass Condensate

    Science.gov (United States)

    Karapetyan, G.

    2017-05-01

    The impact parameter (b) dependence on the saturation scale, in the framework of the Color-Glass Condensate (b-CGC) dipole model, is investigated from the configurational point of view. During the calculations and analysis of the quantum nuclear states, the critical points of stability in the configurational entropy setup are computed, matching the experimental parameters that define the onset of the quantum regime in the b-CGC in the literature with very good accuracy. This new approach is crucial and important for understanding the stability of quantum systems in the study of deep inelastic scattering processes.

  16. Evaluation of Menstrual Cycle on Periodontal Parameters

    Directory of Open Access Journals (Sweden)

    Naser Sargolzaee

    2013-01-01

    Full Text Available Introduction: Bacterial plaque has been identified as the primary factor for the onset of periodontal disease. Although pathogens are very important in the pathogenesis of periodontal diseases, the hosts’ systemic and predisposing factors should also be considered. Sex hormones are important factors contributing to periodontal diseases. The purpose of this study was to investigate the effects of menstruation cycle on periodontal indices. Materials & Methods: In this study, 20 premenopausal women (17-45 years old were selected. Before the examination, scaling and oral health instruction for all subjects was done. Clinical examinations were done during the menstrual cycle specifically during ovulation (OV time, during pre-menstruation (PM and during menstruation (M with four month in tervals. Indices evaluated included: 1 Plaque index (PI 2 Gingival index (GI 3 Probing depth (PD around the (Ramfjord teeth. Friedman test was used for comparison among the three durations and for two by two comparisons, Wilcoxon test was used.Results: Results showed a significant difference among the phases of the menstrual cycle for gingival index (P0.05.Conclusion: During menstrual cycle due to the hormonal changes, gingival index and inflammation is significantly increased indicating that in order to prevent periodontal diseases, oral health should be maintained.

  17. To Evaluate the Applicability of Parameters of Cytological Grading Systems on Aspirates of Breast Carcinoma

    Science.gov (United States)

    Srivastava, Priyanshu; Kumar, Binay; Joshi, Usha; Bano, Mehar

    2018-01-01

    Background: Fine-needle aspiration cytology (FNAC) is still an important first line diagnostic procedure in developing countries. FNAC of breast lesions is quite specific and sensitive investigation and the results are comparable to histopathology. Aim: To evaluate applicability of parameters of different cytological grading (CG) systems, for aspirates of breast cancers, and its correlation with histopathology grading parameters. Materials and Methods: A cross-sectional observational study was carried out on 30 female patients with ductal carcinoma breast, diagnosed on FNAC and subsequently confirmed histopathologically. The cytological smears were graded using six different cytological parameters/criteria described by Robinson et al. (Robinson grading system) and modified Scarff-Bloom-Richardson (SBR) grading system considering three parameters. The results of cytological grade (CG) were compared with parameters of gold standard modified SBR histological grading (HG) system. Results: Important influential cytological parameters to predict final RBS cytological score came out to be chromatin, nucleoli, nuclear size, cell uniformity, and cell dissociation with statistically significant P value (0.0001) except for mitotic count. The important influential predictor of final SBR histological score is nuclear pleomorphism. Conclusion: SBR HG has good correlation with both RBS and SBR CG systems. The cytological nuclear grade provides important prognostic information which is very sensitive and equally specific hence should be done in breast aspirates and is now replaced by Core Needle biopsy. In developing country like India FNAC of breast aspirates still holds diagnostic value in the classification of breast lesions as compared to core guided image biopsy. PMID:29403164

  18. Thermal-Hydraulic Sensitivity Study of Intermediate Loop Parameters for Nuclear Hydrogen Production System

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Jong Hwa; Lee, Heung Nae; Park, Jea Ho [KONES Corp., Seoul (Korea, Republic of); Lee, Won Jae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Sang Il; Yoo, Yeon Jae [Hyundai Engineering Co., Seoul (Korea, Republic of)

    2016-10-15

    The heat generated from the VHTR is transferred to the intermediate loop through Intermediate Heat Exchanger (IHX). It is further passed on to the Sulfur-Iodine (SI) hydrogen production system (HPS) through Process Heat Exchanger (PHX). The IL provides the safety distance between the VHTR and HPS. Since the IL performance affects the overall nuclear HPS efficiency, it is required to optimize its design and operation parameters. In this study, the thermal-hydraulic sensitivity of IL parameters with various coolant options has been examined by using MARS-GCR code, which was already applied for the case of steam generator. Sensitivity study of the IL and PHX parameters has been carried out based on their thermal-hydraulic performance. Several parameters for design and operation, such as the pipe diameter, safety distance and surface area, are considered for different coolant options, He, CO{sub 2} and He-CO{sub 2} (2:8). It was found that the circulator work is the major factor affecting on the overall nuclear hydrogen production system efficiency. Circulator work increases with the safety distance, and decreases with the operation pressure and loop pipe diameter. Sensitivity results obtained from this study will contribute to the optimization of the IL design and operation parameters and the optimal coolant selection.

  19. Evaluation of coal mixture components using infrared-spectral parameters

    Energy Technology Data Exchange (ETDEWEB)

    Popov, S.E.; Rus' yanova, N.D.; Popov, V.K.; Bubnovskaya, L.M.; Stepanov, Yu.V.; Belyaeva, L.I. (Vostochnyi Nauchno-Issledovatel' skii Uglekhimicheskii Institut (USSR))

    1989-07-01

    Discusses use of infrared spectrometers for evaluation of black coal supplied by 6 coal preparation plants to the Nizhnii Tagil coking plant. Infrared-spectral parameters as alternative to the following indices are characterized: ash content, volatile matter, thickness of plastic layer, vitrinite reflectivity, vitrinite content, sum of inertinite components. Coal sample preparation and evaluation using standard laboratory measuring instruments are analyzed. Correlations of spectral parameters with conventional parameters are evaluated. Evaluations showed that infrared spectrometers supply accurate information on coal quality. Measuring time is reduced; measuring accuracy is satisfactory. 3 refs.

  20. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D., E-mail: mencarini@ieav.cta.b, E-mail: alexdc@ieav.cta.b [Instituto de Estudos Avancados (IEAv/CTA), Sao Jose dos Campos, SP (Brazil)

    2011-07-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  1. Objective parameters for engine noise quality evaluation; Objektive Parameter zur Bewertung der Motorgeraeuschqualitaet

    Energy Technology Data Exchange (ETDEWEB)

    Graf, Bernhard; Brandl, Stephan [AVL List GmbH, Graz (Austria); Sontacchi, Alois [Univ. fuer Musik und Darstellende Kunst, Graz (Austria). Inst. fuer Elektronische Musik und Akustik; Girstmair, Josef [Kompetenzzentrum Das Virtuelle Fahrzeug, Graz (Austria). Gruppe Antriebsstrang Dynamik und Akustik

    2013-06-01

    Due to ongoing downsizing efforts and more stringent emission regulations, relevance of sound quality monitoring during engine and vehicle development is strongly increasing. Therefore AVL developed new sound quality parameters like CKI (Combustion Knocking Index) and HI (Harshness Index). Using these parameters sound quality can be objectively monitored, without subjective evaluations, online throughout the complete development process. (orig.)

  2. Bayesian Monte Carlo method for nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J. [Nuclear Research and Consultancy Group NRG, P.O. Box 25, ZG Petten (Netherlands)

    2015-12-15

    A Bayesian Monte Carlo method is outlined which allows a systematic evaluation of nuclear reactions using the nuclear model code TALYS and the experimental nuclear reaction database EXFOR. The method is applied to all nuclides at the same time. First, the global predictive power of TALYS is numerically assessed, which enables to set the prior space of nuclear model solutions. Next, the method gradually zooms in on particular experimental data per nuclide, until for each specific target nuclide its existing experimental data can be used for weighted Monte Carlo sampling. To connect to the various different schools of uncertainty propagation in applied nuclear science, the result will be either an EXFOR-weighted covariance matrix or a collection of random files, each accompanied by the EXFOR-based weight. (orig.)

  3. Bayesian Monte Carlo method for nuclear data evaluation

    Science.gov (United States)

    Koning, A. J.

    2015-12-01

    A Bayesian Monte Carlo method is outlined which allows a systematic evaluation of nuclear reactions using the nuclear model code TALYS and the experimental nuclear reaction database EXFOR. The method is applied to all nuclides at the same time. First, the global predictive power of TALYS is numerically assessed, which enables to set the prior space of nuclear model solutions. Next, the method gradually zooms in on particular experimental data per nuclide, until for each specific target nuclide its existing experimental data can be used for weighted Monte Carlo sampling. To connect to the various different schools of uncertainty propagation in applied nuclear science, the result will be either an EXFOR-weighted covariance matrix or a collection of random files, each accompanied by the EXFOR-based weight.

  4. Evaluation of metallic osseous implants with nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Wellman, H.N.; Schauwecker, D.S.; Capello, W.N.

    1988-04-01

    Nuclear medicine has proven to have a valuable role in the evaluation of osseous metallic implants, particularly with joint prostheses, but can assist with evaluation of other appliances as well. The nuclear arthrogram has become an invaluable adjunct to simultaneously performed radiographic contrast arthrography. This application has been best evaluated in what is one of the most common of orthopedic prosthesis problems, namely, loosening of total hip prostheses. Experience indicates that both sensitivity and specificity of loosening of the femoral component can be increased to over 90% through combined use of nuclear with radiographic contrast arthrography. Furthermore the combination of routine skeletal scintimaging with the nuclear arthrogram adds a significant dimension to precise localizing of the nuclear arthrographics agent In-111 chloride. Nuclear medicine also plays an important role in further evaluating the presence of infection associated with metallic implants with In-111 WBC preparations being superior to Ga-67 as the radiopharmaceutical tracer. Infection has been detected with a sensitivity of 73% and a specificity of 93% in our series using combined In-111 WBC and simultaneous skeletal imaging with conventional Tc-99m MDP. Acute infections are more readily identifiable than chronic in association with prostheses. 29 references.

  5. INTERNATIONAL CO-OPERATION IN NUCLEAR DATA EVALUATION

    Energy Technology Data Exchange (ETDEWEB)

    Herman, M.; Katakura,J.; Koning,A.; Nordborg,C.

    2010-04-30

    The OECD Nuclear Energy Agency (NEA) is organising a co-operation between the major nuclear data evaluation projects in the world. The co-operation involves the ENDF, JEFF, and JENDL projects, and, owing to the collaboration with the International Atomic Energy Agency (IAEA), also the Russian RUSFOND and the Chinese CENDL projects. The Working Party on international nuclear data Evaluation Cooperation (WPEC), comprised of about 20 core members, manages this co-operation and meets annually to discuss progress in each evaluation project and also related experimental activities. The WPEC assesses common needs for nuclear data improvements and these needs are then addressed by initiating joint evaluation efforts. The work is performed in specially established subgroups, consisting of experts from the participating evaluation projects. The outcome of these subgroups is published in reports, issued by the NEA. Current WPEC activities comprise for example a number of studies related to nuclear data uncertainties, including a review of methods for the combined use of integral experiments and covariance data, as well as evaluations of some of the major actinides, such as {sup 235}U and {sup 239}Pu. This paper gives an overview of current and planned activities within the WPEC.

  6. Nuclear data evaluation methodology including estimates of covariances

    Directory of Open Access Journals (Sweden)

    Smith D.L.

    2010-10-01

    Full Text Available Evaluated nuclear data rather than raw experimental and theoretical information are employed in nuclear applications such as the design of nuclear energy systems. Therefore, the process by which such information is produced and ultimately used is of critical interest to the nuclear science community. This paper provides an overview of various contemporary methods employed to generate evaluated cross sections and related physical quantities such as particle emission angular distributions and energy spectra. The emphasis here is on data associated with neutron induced reaction processes, with consideration of the uncertainties in these data, and on the more recent evaluation methods, e.g., those that are based on stochastic (Monte Carlo techniques. There is no unique way to perform such evaluations, nor are nuclear data evaluators united in their opinions as to which methods are superior to the others in various circumstances. In some cases it is not critical which approaches are used as long as there is consistency and proper use is made of the available physical information. However, in other instances there are definite advantages to using particular methods as opposed to other options. Some of these distinctions are discussed in this paper and suggestions are offered regarding fruitful areas for future research in the development of evaluation methodology.

  7. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Kim, Yun Jae; Choi, Jae Boong [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2002-03-15

    This project focuses on developing reliable life evaluation technology for nuclear power plant components, and is divided into two parts, development of a life evaluation system for nuclear pressure vessels and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered in this project: defect assessment method for steam generator tubes, development of fatigue monitoring system, assessment of corroded pipes, domestic round robin analysis for constructing P-T limit curve for RPV, development of probabilistic integrity assessment technique, effect of aging on strength of dissimilar welds, applicability of LBB to cast stainless steel, and development of probabilistic piping fracture mechanics.

  8. Application of Dar Zarrouk parameters to evaluate aquifer ...

    African Journals Online (AJOL)

    The evaluation of the aquifer transmissivity in Ekpoma area of Edo State, Nigeria, was carried out by the application of the Dar Zarrouk Parameter (DZP). The Schlumberger array configuration in electrical resistivity survey was adopted in acquiring the data. The geoelectric parameters were obtained from the interpretation of ...

  9. Evaluation of physico-chemical parameters of agricultural soils ...

    African Journals Online (AJOL)

    Evaluation of physico-chemical parameters of agricultural soils irrigated by the waters of the hydrolic basin of Sebou River and their influences on the transfer of trace elements into sugar crops (the case of sugar cane)

  10. JUPITER PROJECT - JOINT UNIVERSAL PARAMETER IDENTIFICATION AND EVALUATION OF RELIABILITY

    Science.gov (United States)

    The JUPITER (Joint Universal Parameter IdenTification and Evaluation of Reliability) project builds on the technology of two widely used codes for sensitivity analysis, data assessment, calibration, and uncertainty analysis of environmental models: PEST and UCODE.

  11. Multi-objective genetic algorithm parameter estimation in a reduced nuclear reactor model

    Energy Technology Data Exchange (ETDEWEB)

    Marseguerra, M.; Zio, E.; Canetta, R. [Polytechnic of Milan, Dept. of Nuclear Engineering, Milano (Italy)

    2005-07-01

    The fast increase in computing power has rendered, and will continue to render, more and more feasible the incorporation of dynamics in the safety and reliability models of complex engineering systems. In particular, the Monte Carlo simulation framework offers a natural environment for estimating the reliability of systems with dynamic features. However, the time-integration of the dynamic processes may render the Monte Carlo simulation quite burdensome so that it becomes mandatory to resort to validated, simplified models of process evolution. Such models are typically based on lumped effective parameters whose values need to be suitably estimated so as to best fit to the available plant data. In this paper we propose a multi-objective genetic algorithm approach for the estimation of the effective parameters of a simplified model of nuclear reactor dynamics. The calibration of the effective parameters is achieved by best fitting the model responses of the quantities of interest to the actual evolution profiles. A case study is reported in which the real reactor is simulated by the QUAndry based Reactor Kinetics (Quark) code available from the Nuclear Energy Agency and the simplified model is based on the point kinetics approximation to describe the neutron balance in the core and on thermal equilibrium relations to describe the energy exchange between the different loops. (authors)

  12. Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability

    Energy Technology Data Exchange (ETDEWEB)

    Golay, Michael [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2016-10-30

    This project aims to go beyond effective communication in understanding how to design nuclear enterprise projects that will gain stakeholder acceptability. Much of what we are studying is generally applicable to controversial projects, and we expect our results to be of broad value beyond the nuclear arena. Acceptability is more than effective communication; it also requires varying degrees of engagement with a disparate number of stakeholder groups. In the nuclear enterprise, previous attempts have been well designed physically (i.e., technologically sound), but have floundered by being insensitive concerning acceptance. Though effective communication is a necessary, but insufficient, condition for such success, there is a lack of scholarship regarding how to gain stakeholder acceptance for new controversial projects, including nuclear ones. Our work is building a model for use in assessing the performance of a project in the area of acceptability. In the nuclear-social nexus, gaining acceptance requires a clear understanding of factors regarded as being important by the many stakeholders that are common to new nuclear project (many of whom hold an effective veto power). Projects tend to become socially controversial when public beliefs, expert opinion and decision-maker understanding are misaligned. As such, stakeholder acceptance is hypothesized as both an ongoing process and an initial project design parameter comprised of complex, social, cognitive and technical components. Controversial projects may be defined as aspects of modern technologies that some people question, or are cautious about. They could range from genetic modifications, biological hazards, effects of chemical agents, nuclear radiation or hydraulic fracturing operations. We intend that our work will result in a model likely to be valuable for refining project design and implementation to increase the knowledge needed for successful management of stakeholder relationships.

  13. Effective-range parameters and vertex constants for Λ-nuclear systems

    Science.gov (United States)

    Rakityansky, S. A.; Gopane, I. M.

    For a wide range of the core-nuclei (6 ≤ A ≤ 207), the scattering lengths, effective radii, and the other effective-range parameters (up to the order ˜ k8) for the angular momentum ℓ = 0, 1, 2 are calculated within a two-body ΛA-model. For the same hypernuclear systems, the S-matrix residues as well as the corresponding Nuclear-Vertex and Asymptotic-Normalization constants (NVC’s and ANC’s) for the bound states are also found.

  14. Microscopic evaluation of the nuclear dipole polarizability

    Energy Technology Data Exchange (ETDEWEB)

    Lipparini, E.; Orlandini, G.; Stringari, S.; Traini, M. (Trento Univ. (Italy). Dept. di Matematica e Fisica)

    1977-12-01

    The dipole polarizability sum rule has been evaluated by means of a restricted Hartree-Fock approach. The method leads to a simple and analytical expression for the dipole polarizability. Explicit calculations have been performed in /sup 16/O and /sup 40/Ca with different types of interaction.

  15. Evaluation of the main parameters affecting seismic performance of ...

    Indian Academy of Sciences (India)

    study aims to evaluate how much and when; seismic code, number of stories, concrete strength, amount ... This study aims to evaluate the main parameters affecting seismic performance of exist- ing low and .... proportional to the product of mass and the first mode shape amplitude at each storey level under consideration.

  16. Evaluation of physico-chemical and microbial parameters on water ...

    African Journals Online (AJOL)

    Microsoft Windows

    Evaluation of physico-chemical and microbial parameters on water quality of Narmada River, India ... This evaluation will be immensely helpful to estimate the effect of impoundments on the quality of water, ..... Water Quality Index-crossing the psychological barrier (Ed Jenkis,. S.H). Proc. Intl. Conf on water Poll, Jerusalem.

  17. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Chadwick, M B; Oblozinsky, P; Herman, M; Greene, N M; McKnight, R D; Smith, D L; Young, P G; MacFarlane, R E; Hale, G M; Haight, R C; Frankle, S; Kahler, A C; Kawano, T; Little, R C; Madland, D G; Moller, P; Mosteller, R; Page, P; Talou, P; Trellue, H; White, M; Wilson, W B; Arcilla, R; Dunford, C L; Mughabghab, S F; Pritychenko, B; Rochman, D; Sonzogni, A A; Lubitz, C; Trumbull, T H; Weinman, J; Brown, D; Cullen, D E; Heinrichs, D; McNabb, D; Derrien, H; Dunn, M; Larson, N M; Leal, L C; Carlson, A D; Block, R C; Briggs, B; Cheng, E; Huria, H; Kozier, K; Courcelle, A; Pronyaev, V; der Marck, S

    2006-10-02

    We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector

  18. Evaluation of efficiency calibration parameters of the LR-115 radon detector.

    Science.gov (United States)

    Mireles, F; Dávila, J I; García, M L; Pinedo, J L; López, H

    2010-05-01

    Measurement of 222Rn is an important research concern because of the high-energy alpha emission of its 218Po and 214Po progeny. The LR-115 passive detector is the basis of a solid-state nuclear track detector (SSNTD) whose use for radon measurements has been well established. The usage of the SSNTD technique requires calibration by comparison. The aim of this work is to evaluate the efficiency calibration parameters for the radon measurement system that three steps: (1) irradiation conditions, (2) etching conditions, and (3) track counting. The following parameters were evaluated: breakdown and counting voltages for the spark counter, detector thickness, etching time, temperature and NaOH concentration as etching conditions for the LR-115 detector. Calibrating factors of 0.035 and 0.028 tracks cm-2 Bq-1 m3 d-1 for the open- and closed-chamber radon monitors, respectively, were determined considering the best efficiency calibration parameter values.

  19. Assessment of Some Immune Parameters in Occupationally Exposed Nuclear Power Plant Workers

    Directory of Open Access Journals (Sweden)

    Ilona Mihaylova Gyuleva

    2015-11-01

    Full Text Available A 10-year survey of immune status of nuclear power plant (NPP workers was assessed by cellular and humoral immune parameters. The cumulative doses of NPP workers were in the range of 0.06 to 766.36 mSv. The results did not show significant deviations in the studied parameters of cellular and humoral immunity, but a tendency of elevated values in CD3+4+ helper inducers cells, especially its CD4+62L+ subpopulation, regulatory CD4+25+ cells, CD8+28+ cytotoxic subpopulation, and immunoglobulin M, was established. The observed trend of the above-mentioned parameters could be interpreted by assumption that while the adaptation processes are dominated with low prevalence of T-helper (Th 1 immune response to cumulative doses less than 100 mSv, a switch to Th-2 response occurred at doses above 100 mSv. The impact of a number of other confounding factors on the immune system does not allow definitive conclusions about the direct radiation-induced changes in immune parameters.

  20. Assessment of Some Immune Parameters in Occupationally Exposed Nuclear Power Plant Workers

    Science.gov (United States)

    Penkova, Kalina Ivanova; Rupova, Ivanka Tankova; Panova, Delyana Yonkova; Djounova, Jana Nikolaeva

    2015-01-01

    A 10-year survey of immune status of nuclear power plant (NPP) workers was assessed by cellular and humoral immune parameters. The cumulative doses of NPP workers were in the range of 0.06 to 766.36 mSv. The results did not show significant deviations in the studied parameters of cellular and humoral immunity, but a tendency of elevated values in CD3+4+ helper inducers cells, especially its CD4+62L+ subpopulation, regulatory CD4+25+ cells, CD8+28+ cytotoxic subpopulation, and immunoglobulin M, was established. The observed trend of the above-mentioned parameters could be interpreted by assumption that while the adaptation processes are dominated with low prevalence of T-helper (Th) 1 immune response to cumulative doses less than 100 mSv, a switch to Th-2 response occurred at doses above 100 mSv. The impact of a number of other confounding factors on the immune system does not allow definitive conclusions about the direct radiation-induced changes in immune parameters. PMID:26740807

  1. Bayesian Monte Carlo Method for Nuclear Data Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J., E-mail: koning@nrg.eu

    2015-01-15

    A Bayesian Monte Carlo method is outlined which allows a systematic evaluation of nuclear reactions using TALYS. The result will be either an EXFOR-weighted covariance matrix or a collection of random files, each accompanied by an experiment based weight.

  2. Emergy Evaluation of a Swedish Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kindberg, Anna

    2007-03-15

    Today it is common to evaluate and compare energy systems in terms of emission of greenhouse gases. However, energy systems should not only reduce their pollution but also give a large energy return. One method used to measure energy efficiency is emergy (embodied energy, energy memory) evaluation, which was developed by the system ecologist Howard T. Odum. Odum defines emergy as the available energy of one kind previously used up directly and indirectly to make a service or product. Both work of nature and work of human economy in generating products and services are calculated in terms of emergy. Work of nature takes the form of natural resources and work of human economy includes labour, services and products used to transform natural resources into something of value to the economy. The quotient between work of nature and work of human economy gives the emergy return on investment of the investigated product. With this in mind the present work is an attempt to make an emergy evaluation of a Swedish nuclear power plant to estimate its emergy return on investment. The emergy return on investment ratio of a Swedish nuclear power plant is calculated to approximately 11 in this diploma thesis. This means that for all emergy the Swedish economy has invested in the nuclear power plant it gets 11 times more emergy in return in the form of electricity generated by nuclear power. The method used in this work may facilitate future emergy evaluations of other energy systems.

  3. Evaluation and assessment of nuclear power plant seismic methodology

    Energy Technology Data Exchange (ETDEWEB)

    Bernreuter, D.; Tokarz, F.; Wight, L.; Smith, P.; Wells, J.; Barlow, R.

    1977-03-01

    The major emphasis of this study is to develop a methodology that can be used to assess the current methods used for assuring the seismic safety of nuclear power plants. The proposed methodology makes use of system-analysis techniques and Monte Carlo schemes. Also, in this study, we evaluate previous assessments of the current seismic-design methodology.

  4. Opinions on nuclear energy: Evaluations, beliefs, and attitudes.

    NARCIS (Netherlands)

    Meertens, R.W.; Stallen, P.J.

    1981-01-01

    Used the expectancy-value model of attitudes (M. Fishbein and I. Ajzen, 1975) to investigate the attitudes, evaluations, and beliefs concerning the peaceful use of nuclear energy in 252 Dutch social and natural scientists. The model received empirical support. A factor analysis revealed 2

  5. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Kwon, J. D. [Yeungnam Univ., Gyeongsan (Korea, Republic of); Kang, K. J. [Chonnam National Univ., Gwangju (Korea, Republic of)] (and others)

    2001-03-15

    This research focuses on development of reliable life evaluation technology for nuclear power plant (NPP) components, and is divided into two parts, development of life evaluation systems for pressurized components and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered: development of expert systems for integrity assessment of pressurized components, development of integrity evaluation systems of steam generator tubes, prediction of failure probability for NPP components based on probabilistic fracture mechanics, development of fatigue damage evaluation technique for plant life extension, domestic round robin analysis for pressurized thermal shock of reactor vessels, domestic round robin analysis of constructing P--T limit curves for reactor vessels, and development of data base for integrity assessment. For evaluation of applicability of emerging technology to operating plants, on the other hand, the following eight topics are covered: applicability of the Leak-Before-Break analysis to Cast S/S piping, collection of aged material tensile and toughness data for aged Cast S/S piping, finite element analyses for load carrying capacity of corroded pipes, development of Risk-based ISI methodology for nuclear piping, collection of toughness data for integrity assessment of bi-metallic joints, applicability of the Master curve concept to reactor vessel integrity assessment, measurement of dynamic fracture toughness, and provision of information related to regulation and plant life extension issues.

  6. Evaluation of nuclear magnetic resonance spectroscopy variability

    Energy Technology Data Exchange (ETDEWEB)

    Barreto, Felipe Rodrigues; Salmon, Carlos Ernesto Garrido, E-mail: garrido@ffclrp.usp.br [Universidade de Sao Paulo (FFCLRP/USP), Ribeirao Preto, SP (Brazil). Fac. de Filisofia, Ciencias e Letras; Otaduy, Maria Concepcion Garcia [Universidade de Sao Paulo (FAMUS/USP), Sao Paulo, SP (Brazil). Fac. de Medicina. Departamento de Radiologia

    2014-11-01

    Introduction: the intrinsically high sensitivity of Magnetic Resonance Spectroscopy (MRS) causes considerable variability in metabolite quantification. In this study, we evaluated the variability of MRS in two research centers using the same model of magnetic resonance image scanner. Methods: two metabolic phantoms were created to simulate magnetic resonance spectra from in vivo hippocampus. The phantoms were filled with the same basic solution containing the following metabolites: N-acetyl-aspartate, creatine, choline, glutamate, glutamine and inositol. Spectra were acquired over 15 months on 26 acquisition dates, resulting in a total of 130 spectra per center. Results: the phantoms did not undergo any physical changes during the 15-month period. Temporal analysis from both centers showed mean metabolic variations of 3.7% in acquisitions on the same day and of 8.7% over the 15-month period. Conclusion: The low deviations demonstrated here, combined with the high specificity of Magnetic Resonance Spectroscopy, confirm that it is feasible to use this technique in multicenter studies in neuroscience research. (author)

  7. Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model

    Directory of Open Access Journals (Sweden)

    Hao Shi

    2017-01-01

    Full Text Available The best estimation process of AP1000 Nuclear Power Plant (NPP requires proper selections of parameters and models so as to obtain the most accurate results compared with the actual design parameters. Therefore, it is necessary to identify and evaluate the influences of these parameters and modeling approaches quantitatively and qualitatively. Based on the best estimate thermal-hydraulic system code RELAP5/MOD3.2, sensitivity analysis has been performed on core partition methods, parameters, and model selections in AP1000 Nuclear Power Plant, like the core channel number, pressurizer node number, feedwater temperature, and so forth. The results show that core channel number, core channel node number, and the pressurizer node number have apparent influences on the coolant temperature variation and pressure drop through the reactor. The feedwater temperature is a sensitive factor to the Steam Generator (SG outlet temperature and the Steam Generator outlet pressure. In addition, the cross-flow model nearly has no effects on the coolant temperature variation and pressure drop in the reactor, in both the steady state and the loss of power transient. Furthermore, some fittest parameters with which the most accurate results could be obtained have been put forward for the nuclear system simulation.

  8. Chemical kinetics parameters and model validation for the gasification of PCEA nuclear graphite

    Energy Technology Data Exchange (ETDEWEB)

    El-Genk, Mohamed S [University of New Mexico, Albuquerque; Tournier, Jean-Michel [University of New Mexico, Albuquerque; Contescu, Cristian I [ORNL

    2014-01-01

    A series of gasification experiments, using two right cylinder specimens (~ 12.7 x 25.4 mm and 25.4 x 25.4 mm) of PCEA nuclear graphite in ambient airflow, measured the total gasification flux at weight losses up to 41.5% and temperatures (893-1015 K) characteristics of those for in-pores gasification Mode (a) and in-pores diffusion-limited Mode (b). The chemical kinetics parameters for the gasification of PCEA graphite are determined using a multi-parameters optimization algorithm from the measurements of the total gasification rate and transient weight loss in experiments. These parameters are: (i) the pre-exponential rate coefficients and the Gaussian distributions and values of specific activation energies for adsorption of oxygen and desorption of CO gas; (ii) the specific activation energy and pre-exponential rate coefficient for the breakup of stable un-dissociated C(O2) oxygen radicals to form stable (CO) complexes; (iii) the specific activation energy and pre-exponential coefficient for desorption of CO2 gas and; (iv) the initial surface area of reactive free sites per unit mass. This area is consistently 13.5% higher than that for nuclear graphite grades of NBG-25 and IG-110 and decreases inversely proportional with the square root of the initial mass of the graphite specimens in the experiments. Experimental measurements successfully validate the chemical-reactions kinetics model that calculates continuous Arrhenius curves of the total gasification flux and the production rates of CO and CO2 gases. The model results at different total weight losses agree well with measurements and expand beyond the temperatures in the experiments to the diffusion-limited mode of gasification. Also calculated are the production rates of CO and CO2 gases and their relative contributions to the total gasification rate in the experiments as functions of temperature, for total weight losses of 5% and 10%.

  9. Chemical kinetics parameters and model validation for the gasification of PCEA nuclear graphite

    Energy Technology Data Exchange (ETDEWEB)

    El-Genk, Mohamed S., E-mail: mgenk@unm.edu [Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM (United States); Chemical and Nuclear Engineering Dept., University of New Mexico, Albuquerque, NM (United States); Mechanical Engineering Dept., University of New Mexico, Albuquerque, NM (United States); Tournier, Jean-Michel P. [Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM (United States); Contescu, Cristian I. [Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    2014-01-15

    A series of gasification experiments, using two right cylinder specimens (∼12.7 × 25.4 mm and 25.4 × 25.4 mm) of PCEA nuclear graphite in ambient airflow, measured the total gasification flux at weight losses up to 41.5% and temperatures (893–1015 K) characteristics of those for in-pores gasification Mode (a) and in-pores diffusion-limited Mode (b). The chemical kinetics parameters for the gasification of PCEA graphite are determined using a multi-parameters optimization algorithm from the measurements of the total gasification rate and transient weight loss in experiments. These parameters are: (i) the pre-exponential rate coefficients and the Gaussian distributions and values of specific activation energies for adsorption of oxygen and desorption of CO gas; (ii) the specific activation energy and pre-exponential rate coefficient for the breakup of stable un-dissociated C(O{sub 2}) oxygen radicals to form stable (CO) complexes; (iii) the specific activation energy and pre-exponential coefficient for desorption of CO{sub 2} gas and; (iv) the initial surface area of reactive free sites per unit mass. This area is consistently 13.5% higher than that for nuclear graphite grades of NBG-25 and IG-110 and decreases inversely proportional with the square root of the initial mass of the graphite specimens in the experiments. Experimental measurements successfully validate the chemical-reactions kinetics model that calculates continuous Arrhenius curves of the total gasification flux and the production rates of CO and CO{sub 2} gases. The model results at different total weight losses agree well with measurements and expand beyond the temperatures in the experiments to the diffusion-limited mode of gasification. Also calculated are the production rates of CO and CO{sub 2} gases and their relative contributions to the total gasification rate in the experiments as functions of temperature, for total weight losses of 5% and 10%.

  10. Development of an Integrity Evaluation System for Nuclear Power Plants

    Science.gov (United States)

    Kim, Young-Jin; Choi, Jae-Boong; Lee, Joon-Seong; Jun, Hyun-Kyu; Park, Youn-Won

    This paper describes the structure and development strategy for integrity evaluation system for nuclear power plants called NPP-KINS/SAFE. NPP-KINS/SAFE consists of three different programs covering the integrity assessment of reactor pressure vessel, pipings, and pressure tubes, respectively. The system has been developed based on currently available codes and standards, and includes a number of databases, expert systems, and numerical analysis schemes. NPP-KINS/SAFE is applicable for various types of nuclear power plants constructed in Korea with the aid of attached database systems including plant specific data. Case studies for the developed system are also provided.

  11. Assessment of Some Immune Parameters in Occupationally Exposed Nuclear Power Plants Workers

    Science.gov (United States)

    Panova, Delyana; Djounova, Jana; Rupova, Ivanka; Penkova, Kalina

    2015-01-01

    The purpose of this article is to analyze the results of a 10-year survey of the radiation effects of some immune parameters of occupationally exposed personnel from the Nuclear Power Plant “Kozloduy”, Bulgaria. 438 persons working in NPP with cumulative doses between 0.06 mSv and 766.36mSv and a control group with 65 persons were studied. Flow cytometry measurements of T, B, natural killer (NK) and natural killer T (NKT) cell lymphocyte populations were performed. Data were interpreted with regard to cumulative doses, length of service and age. The average values of the studied parameters of cellular immunity were in the reference range relative to age and for most of the workers were not significantly different from the control values. Low doses of ionizing radiation showed some trends of change in the number of CD3+CD4+ helper-inducer lymphocytes, CD3+ CD8+ and NKT cell counts. The observed changes in some of the studied parameters could be interpreted in terms of adaptation processes at low doses. At doses above 100–200 mSv, compensatory mechanisms might be involved to balance deviations in lymphocyte subsets. The observed variations in some cases could not be attributed only to the radiation exposure because of the impact of a number of other exogenous and endogenous factors on the immune system. PMID:26675014

  12. Parameter Data on the Radiocesium Transfer to Korean Staple Food Crops Following a Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yong-Ho; Lim, Kwang-Muk; Jun, In; Kim, Byung-Ho; Keum, Dong-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In order to decide an optimum countermeasure against farmland contaminations following a severe NPP accident, it is necessary to have a reliable tool for predicting the concentrations of radiocesium in crop plants. For the estimation of radionuclide concentrations in crop plants, various transfer parameters, which quantify the radionuclide transfer from one compartment to the next, are used in general. Some amount of transfer parameter data has been produced at the Korea Atomic Energy Research Institute (KAERI) over the last 30 years. The present work was conducted to collate the KAERI data on radiocesium in staple food crops and to suggest effective ways of using them for assessing the environmental impact of a nuclear accident. The transfer parameter values of radiocesium for rice, Chinese cabbage and radish varied considerably with soils and times of its deposition. The proposed representative values were mostly based on a limited amount of data so they cannot be considered to have a high representativeness. Accordingly, they are intended for provisional use and a continuous improvement should be made. It is necessary to produce a sufficient amount of additional domestic data on the indirect pathway by conducting root-uptake experiments with as many types of soil as possible.

  13. Evaluation of trapping parameters of annealed natural quartz

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, Rui [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China); Shisanling Seismic Station, Institute of Earthquake Science, CEA, 102200 Beijing (China); Wei, Ming-Jian, E-mail: weimj@cnu.edu.cn [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China); Song, Bo [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China); Beijing Jing Yuan School, 100040 Beijing (China); Zhang, Yan [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China); School of TaiPingqiao, Nan Lu of West Railway Station, 100073 Beijing (China); Zhao, Qiu-Yue [Key Laboratory of Tourism and Resources Environment in Universities of Shandong, Taishan University, 271000 Tai’an (China); Pan, Bao-Lin; Li, Teng-Fei [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China)

    2016-05-15

    The thermoluminescence (TL) trapping parameters of annealed quartz have been investigated. The apparent TL peaks observed at temperatures of 133 °C, 211 °C, 266 °C and 405 °C, respectively, were named Peak I, Peak II, Peak III and Peak IV. The T{sub m} − T{sub stop} method is applied to investigate the number of peaks and their positions, and to obtain the trap distributions in the quartz. Peak shape (PS), Hoogenstraaten method (Various Heating Rates Method, VHR), and Computerized Glow Curve Deconvolution (CGCD) are used to evaluate the trapping parameters of the annealed quartz. The glow curve can be considered as a superposition of at least nine overlapping peaks. These peaks show up at 133 °C, 211 °C, 266 °C, 308 °C, 333 °C, 384 °C, 441 °C, 466 °C and 484 °C. The PS method can be only used in evaluating the parameters for Peaks I. The VHR method can be used in evaluating the trapping parameters for the first three peaks. CGCD method is complementary to obtaining parameters for the sub-peaks, and the thermal quenching correction with the Urbach’s method is necessary. The Urbach’s coefficient for the quartz is 30.03 kT{sub m}.

  14. A Novel Parameter for Ramp Metering and Evaluation

    Science.gov (United States)

    Li, Jian; Jia, Yuanhua; Zhang, Yong; Chen, Feng; Ao, Guchang

    Real and scientific traffic flow parameter are the basis to make efficient traffic control strategy and establish control function and this will leads to an appropriate and impartial reflection to efficiency and equity of control property. Intelligent control is a new development where the control problem is to find the combination of control measures that result in the best road performance and control effectiveness. The problems of intelligent metering evaluation for local ramp are considered. In this paper, a novel ramp queuing parameter-the reduplicated waiting time was posed using the queuing theory. With in-situ traffic flow data, comparison between the novel and previous parameters are made to clarify the advantages of the novel parameter.

  15. Evaluation of the main parameters affecting seismic performance of ...

    Indian Academy of Sciences (India)

    Based on the considered values of the parameters, it is concluded that: modern code specifications and higher transverse reinforcement 50%, the concrete strength up to 66%, infill-walls 15% and number of story 55% increase the seismic performance for life safety level. Evaluations on the effect of the considered ...

  16. Evaluation of quality parameters of strawberry fruits in modified ...

    African Journals Online (AJOL)

    STORAGESEVER

    2009-03-06

    Mar 6, 2009 ... The objective of the present study is to evaluate the effect of modified atmosphere packaging (MAP) during storage on some quality parameters of strawberries. Strawberries (cv. Camarosa) were harvested when mature, forced air cooled and divided into two groups as fruits in MAP and control.

  17. Evaluation of quality parameters of strawberry fruits in modified ...

    African Journals Online (AJOL)

    The objective of the present study is to evaluate the effect of modified atmosphere packaging (MAP) during storage on some quality parameters of strawberries. Strawberries (cv. Camarosa) were harvested when mature, forced air cooled and divided into two groups as fruits in MAP and control. After packaging, fruits were ...

  18. Evaluation of Nutritional Quality and Haematological Parameters of ...

    African Journals Online (AJOL)

    Evaluation of Nutritional Quality and Haematological Parameters of Moringa ( Moringa oleifera ) Lam Leaves in the Diet of African Catfish ( Clarias gariepinus ). ... The PDF file you selected should load here if your Web browser has a PDF reader plug-in installed (for example, a recent version of Adobe Acrobat Reader).

  19. Analysis of reactor lattice and core parameters in view of nuclear data modifications

    Energy Technology Data Exchange (ETDEWEB)

    Becker Maarten [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Inst. fuer Neutronenphysik und Reaktortechnik

    2011-07-15

    A detailed assessment of the JEFF 3.1 and ENDF/B VII.0 nuclear data libraries with the KANEXT code system has been performed on each level of the reactor simulation steps. This allowed for the sensitivity estimation of the lattice and core parameters to changes in nuclide and specific reaction cross section. The direct calculation of cross section data influence, in particular for specific reaction types, is possible due to the unique substitution feature of the group constant module GRUCAL. Further on, the different impact of several reaction types on the lattice versus core calculation points out the 'engineering uncertainty' using the two major libraries for the identical problem. MCNP(X) and KANEXT cell models can be mutually adjusted such that differences between stochastic and deterministic data processing can be identified. The current analysis emphasizes, that the two major nuclear data libraries JEFF 3.1 and ENDF/B VII.0 exhibit to some extent compensation of deviations rather than reliable integral data calculation. On a special type of a fast reactor application we show that exchange of JEFF 3.1 and ENDF/B VII.0 cross sections introduce large discrepancies. A major part is attributed to the inelastic cross section. Further investigated discrepancies concerning the capture and the fission cross section in the epithermal energy range might be also a concern for LWR which was beyond the scope of the current study. (orig.)

  20. Research in nondestructive evaluation techniques for nuclear reactor concrete structures

    Science.gov (United States)

    Clayton, Dwight; Smith, Cyrus

    2014-02-01

    The purpose of the Materials Aging and Degradation (MAaD) Pathway of the Department of Energy's Light Water Reactor Sustainability (LWRS) Program is to develop the scientific basis for understanding and predicting longterm environmental degradation behavior of material in nuclear power plants and to provide data and methods to assess the performance of systems, structures, and components (SSCs) essential to safe and sustained nuclear power plant operations. The understanding of aging-related phenomena and their impacts on SSCs is expected to be a significant issue for any nuclear power plant planning for long-term operations (i.e. service beyond the initial license renewal period). Management of those phenomena and their impacts during long-term operations can be better enable by improved methods and techniques for detection, monitoring, and prediction of SSC degradation. The MAaD Pathway R&D Roadmap for Concrete, "Light Water Reactor Sustainability Nondestructive Evaluation for Concrete Research and Development Roadmap", focused initial research efforts on understanding the recent concrete issues at nuclear power plants and identifying the availability of concrete samples for NDE techniques evaluation and testing. [1] An overview of the research performed by ORNL in these two areas is presented here.

  1. TUNL Nuclear Structure Data Evaluation on A = 2-20 Nuclides

    Science.gov (United States)

    Truong, Thinh; Kelley, John; Sheu, Grace

    2016-09-01

    Nuclear data represents measured or evaluated probabilities of various physical interactions involving the nuclei of atoms. The nuclear data group at Triangle Universities Nuclear Laboratory (TUNL) compiles, evaluates and disseminates nuclear structure data relevant to light nuclei in the mass region of A = 2 - 20. Our activities primarily involve surveying literature articles and producing recommended values for inclusion into various United States Nuclear Data Program databases, such as Experimental Unevaluated Nuclear Data List (XUNDL) and Evaluated Nuclear Structure Data File (ENSDF). We have projects related to analyzing beta-decay lifetimes, compiling structure data from recently published articles, and producing full nuclear structure data evaluations of nuclides based on all existing literature. The nuclear data disseminated is used for theoretical model development of nuclear physics and for applications involving radiation and nuclear power technologies. This work is supported by the U.S. National Science Foundation Grant No. NSF-PHY-1461204 and Duke/TUNL.

  2. Advanced gas cooled nuclear reactor materials evaluation and development program

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    Results of work performed from January 1, 1977 through March 31, 1977 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Process Heat and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (impure Helium), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes progress to date on alloy selection for VHTR Nuclear Process Heat (NPH) applications and for DCHT applications. The present status on the simulated reactor helium loop design and on designs for the testing and analysis facilities and equipment is discussed.

  3. Evaluation of Haddam Neck (Connecticut Yankee) Nuclear Power Plant, environmental impact prediction, based on monitoring programs

    Energy Technology Data Exchange (ETDEWEB)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Mahaffey, J.A.; Waton, D.G.

    1976-12-01

    A study was undertaken by the U.S. Nuclear Regulatory Commission (NRC) to evaluate the nonradiological environmental data obtained from three nuclear power plants operating for a period of one year or longer. The document presented reports the second of three nuclear power plants to be evaluated in detail by Battelle, Pacific Northwest Laboratories. Haddam Neck (Connecticut Yankee) Nuclear Power Plant nonradiological monitoring data were assessed to determine their effectiveness in the measurement of environmental impacts. Efforts were made to determine if: (1) monitoring programs, as designed, can detect environmental impacts, (2) appropriate statistical analyses were performed and if they were sensitive enough to detect impacts, (3) predicted impacts could be verified by monitoring programs, and (4) monitoring programs satisfied the requirements of the Environmental Technical Specifications. Both preoperational and operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the methods used to measure ecological, chemical, and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data sets were available. From this type of analysis, deficiencies in both preoperational and operational monitoring programs may be identified and provide a basis for suggested improvement.

  4. Evaluation of nuclear data of {sup 244}Pu and {sup 237}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo; Konshin, V.A. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1995-10-01

    The evaluation of nuclear data for {sup 244}Pu and {sup 237}Pu was made in the neutron energy region from 10{sup -5} eV to 20 MeV. For the both nuclides, the total, elastic and inelastic scattering, fission, capture, (n,2n) and (n,3n) reaction cross sections were evaluated on the basis of theoretical calculation. The resonance parameters were given for {sup 244}Pu. The angular and energy distributions of secondary neutrons were also estimated for the both nuclides. The results were compiled in the ENDF-5 format and will be adopted in JENDL Actinoid File. (author).

  5. Kiwi: An Evaluated Library of Uncertainties in Nuclear Data and Package for Nuclear Sensitivity Studies

    Energy Technology Data Exchange (ETDEWEB)

    Pruet, J

    2007-06-23

    This report describes Kiwi, a program developed at Livermore to enable mature studies of the relation between imperfectly known nuclear physics and uncertainties in simulations of complicated systems. Kiwi includes a library of evaluated nuclear data uncertainties, tools for modifying data according to these uncertainties, and a simple interface for generating processed data used by transport codes. As well, Kiwi provides access to calculations of k eigenvalues for critical assemblies. This allows the user to check implications of data modifications against integral experiments for multiplying systems. Kiwi is written in python. The uncertainty library has the same format and directory structure as the native ENDL used at Livermore. Calculations for critical assemblies rely on deterministic and Monte Carlo codes developed by B division.

  6. Evaluating Voellmy resistance parameters for debris-flow simulation models

    Science.gov (United States)

    Schraml, Klaus; McArdell, Brian; Graf, Christoph; Thomschitz, Barbara; Kaitna, Roland

    2014-05-01

    Gravitationally-driven processes such as debris flows constitute a major risk in alpine regions. In order to avoid damages on infrastructure and settlements, the delineation of hazardous areas is required. For this, numerical simulation tools are often applied for use in engineering hazard assessment. For model calibration, information on past events provides a basis to estimate or constrain the essential input parameters. In this study we used two numerical simulation models for evaluating model friction parameters to best-fit runout lengths and deposition patterns of observed past debris-flow events on two alpine fans in Austria with flow deposit volumes of 10,000 m³ and 25,000 m³, respectively. The RAMMS-DF (RApid Mass MovementS - Debris Flow) runout model is based on a Voellmy-type relation to describe the flow friction, and the software DAN3D (Dynamic Analysis of Landslides) allows selecting different rheologies, including a Voellmy-type friction relation. All calculations were based on the same digital elevation model with a 1 m resolution and the same initial conditions. Our results show that both models are able to satisfactorily replicate observed deposition patterns. The best-fit parameter sets of the Voellmy-Coulomb friction coefficient and turbulent coefficient for both study sites and both simulation models were in the range of 0.07-0.11 and 200-400, respectively. In case the deposition area is forested, the Coulomb friction parameter was considerably increased by a factor of around 3 to account for additional surface roughness. A sensitivity analysis shows a slightly higher sensitivity of model parameters for the DAN3D model than for the RAMMS-DF model. This study contributes to the evaluation of realistic model parameters for the simulation of small alpine debris flows on forested and non-forested fans.

  7. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

  8. High-performance lighting evaluated by photobiological parameters.

    Science.gov (United States)

    Rebec, Katja Malovrh; Gunde, Marta Klanjšek

    2014-08-10

    The human reception of light includes image-forming and non-image-forming effects which are triggered by spectral distribution and intensity of light. Ideal lighting is similar to daylight, which could be evaluated by spectral or chromaticity match. LED-based and CFL-based lighting were analyzed here, proposed according to spectral and chromaticity match, respectively. The photobiological effects were expressed by effectiveness for blue light hazard, cirtopic activity, and photopic vision. Good spectral match provides light with more similar effects to those obtained by the chromaticity match. The new parameters are useful for better evaluation of complex human responses caused by lighting.

  9. Applicability of preoperative nuclear morphometry to evaluating risk for cervical lymph node metastasis in oral squamous cell carcinoma.

    Directory of Open Access Journals (Sweden)

    Masaaki Karino

    Full Text Available BACKGROUND: We previously reported the utility of preoperative nuclear morphometry for evaluating risk for cervical lymph node metastases in tongue squamous cell carcinoma. The risk for lymph node metastasis in oral squamous cell carcinoma, however, is known to differ depending on the anatomical site of the primary tumor, such as the tongue, gingiva, mouth floor, and buccal mucosa. In this study, we evaluated the applicability of this morphometric technique to evaluating the risk for cervical lymph node metastasis in oral squamous cell carcinoma. METHODS: A digital image system was used to measure the mean nuclear area, mean nuclear perimeter, nuclear circular rate, ratio of nuclear length to width (aspect ratio, and nuclear area coefficient of variation (NACV. Relationships between these parameters and nodal status were evaluated by t-test and logistic regression analysis. RESULTS: Eighty-eight cases of squamous cell carcinoma (52 of the tongue, 25 of the gingiva, 4 of the buccal mucosa, and 7 of the mouth floor were included: 46 with positive node classification and 42 with negative node classification. Nuclear area and perimeter were significantly larger in node-positive cases than in node-negative cases; however, there were no significant differences in circular rate, aspect ratio, or NACV. We derived two risk models based on the results of multivariate analysis: Model 1, which identified age and mean nuclear area and Model 2, which identified age and mean nuclear perimeter. It should be noted that primary tumor site was not associated the pN-positive status. There were no significant differences in pathological nodal status by aspect ratio, NACV, or primary tumor site. CONCLUSION: Our method of preoperative nuclear morphometry may contribute valuable information to evaluations of the risk for lymph node metastasis in oral squamous cell carcinoma.

  10. Sensitivity analysis of critical experiments with evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Fujiwara, D.; Kosaka, S. [Tepco Systems Corporation, Nuclear Engineering Dept., Tokyo (Japan)

    2008-07-01

    Criticality benchmark testing was performed with evaluated nuclear data libraries for thermal, low-enriched uranium fuel rod applications. C/E values for k{sub eff} were calculated with the continuous-energy Monte Carlo code MVP2 and its libraries generated from Endf/B-VI.8, Endf/B-VII.0, JENDL-3.3 and JEFF-3.1. Subsequently, the observed k{sub eff} discrepancies between libraries were decomposed to specify the source of difference in the nuclear data libraries using sensitivity analysis technique. The obtained sensitivity profiles are also utilized to estimate the adequacy of cold critical experiments to the boiling water reactor under hot operating condition. (authors)

  11. Resonance parameter and covariance evaluation for 16O up to 6 MeV

    Directory of Open Access Journals (Sweden)

    Leal Luiz

    2016-01-01

    Full Text Available A resolved resonance evaluation was performed for 16O in the energy range 0 eV to 6 MeV using the computer code SAMMY resulting in a set of resonance parameters (RPs that describes well the experimental data used in the evaluation. A RP covariance matrix (RPC was also generated. The RP were converted to the evaluated nuclear data file format using the R-Matrix Limited format and the compact format was used to represent the RPC. In contrast to the customary use of RP, which are frequently intended for the generation of total, capture, and scattering cross sections only, the present RP evaluation permits the computation of angle dependent cross sections. Furthermore, the RPs are capable of representing the (n, α cross section from the energy threshold (2.354 MeV of the (n, α reaction to 6 MeV. The intent of this paper is to describe the procedures used in the evaluation of the RP and RPC, the use of the RPC in benchmark calculations and to assess the impact of the 16O nuclear data uncertainties in the calculate dkeff for critical benchmark experiments.

  12. A cochlear implant phantom for evaluating CT acquisition parameters

    Science.gov (United States)

    Chakravorti, Srijata; Bussey, Brian J.; Zhao, Yiyuan; Dawant, Benoit M.; Labadie, Robert F.; Noble, Jack H.

    2017-03-01

    Cochlear Implants (CIs) are surgically implantable neural prosthetic devices used to treat profound hearing loss. Recent literature indicates that there is a correlation between the positioning of the electrode array within the cochlea and the ultimate hearing outcome of the patient, indicating that further studies aimed at better understanding the relationship between electrode position and outcomes could have significant implications for future surgical techniques, array design, and processor programming methods. Post-implantation high resolution CT imaging is the best modality for localizing electrodes and provides the resolution necessary to visually identify electrode position, albeit with an unknown degree of accuracy depending on image acquisition parameters, like the HU range of reconstruction, radiation dose, and resolution of the image. In this paper, we report on the development of a phantom that will both permit studying which CT acquisition parameters are best for accurately identifying electrode position and serve as a ground truth for evaluating how different electrode localization methods perform when using different CT scanners and acquisition parameters. We conclude based on our tests that image resolution and HU range of reconstruction strongly affect how accurately the true position of the electrode array can be found by both experts and automatic analysis techniques. The results presented in this paper demonstrate that our phantom is a versatile tool for assessing how CT acquisition parameters affect the localization of CIs.

  13. Monte Carlo code Serpent calculation of the parameters of the stationary nuclear fission wave

    Directory of Open Access Journals (Sweden)

    V. M. Khotyayintsev

    2017-12-01

    Full Text Available n this work, propagation of the stationary nuclear fission wave was simulated for series of fixed power values using Monte Carlo code Serpent. The wave moved in the axial direction in 5 m long cylindrical core of fast reactor with pure 238U raw fuel. Stationary wave mode arises some period later after the wave ignition and lasts sufficiently long to determine kef with high enough accuracy. The velocity characteristic of the reactor was determined as the dependence of the wave velocity on the neutron multiplication factor. As we have recently shown within a one-group diffusion description, the velocity characteristic is two-valued due to the effect of concentration mechanisms, while thermal feedback affects it only quantitatively. The shape and parameters of the velocity characteristic critically affect feasibility of the reactor design since stationary wave solutions of the lower branch are unstable and do not correspond to any real waves in self-regulated reactor, like CANDLE. In this work calculations were performed without taking into account thermal feedback. They confirm that theoretical dependence correctly describes the shape of the velocity characteristic calculated using the results of the Serpent modeling.

  14. Parameters and symbols for use in nuclear magnetic resonance (IUPAC recommendations 1997).

    Science.gov (United States)

    Harris, R K; Kowalewski, J; Cabral de Menezes, S

    1998-01-01

    NMR is now frequently the technique of choice for the determination of chemical structure in solution. Its uses also span structure in solids and mobility at the molecular level in all phases. The research literature in the subject is vast and ever-increasing. Unfortunately, many articles do not contain sufficient information for experiments to be repeated elsewhere, and there are many variations in the usage of symbols for the same physical quantity. It is the aim of the present recommendations to provide simple check-lists that will enable such problems to be minimised in a way that is consistent with general IUPAC formulation. The area of medical NMR and imaging is not specifically addressed in these recommendations, which are principally aimed at the mainstream use of NMR by chemists (of all sub-disciplines) and by many physicists, biologists, materials scientists and geologists etc. working with NMR. The document presents recommended notation for use in journal publications involving a significant contribution of nuclear magnetic resonance (NMR) spectroscopy. The recommendations are in two parts: (1) Experimental parameters which should be listed so that the work in question can be repeated elsewhere. (2) A list of symbols (using Roman or Greek characters) to be used for quantities relevant to NMR.

  15. Evaluation of the improvement suggestion system in a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Carnaval, Joao Paulo Rodrigues; Moraes, Geice Almeida, E-mail: joaocarnaval@inb.gov.br, E-mail: geice@inb.gov.br [Industrias Nucleares do Brasil S.A (INB), Resende, RJ (Brazil)

    2017-11-01

    This work evaluated methods for processing improvement suggestions of a nuclear factory, with the intention to verify those which best fits to the company purposes. Two methods for processing improvement suggestions were applied in the studied organization. The first one was guided to the processing suggestions by specific independent sectors of the company and the second one was conducted to the processing of suggestions by a multidisciplinary team. It has been concluded that a multidisciplinary team focused on research and development would be the best option to the implementation of improvement suggestions and technological innovation on this facility, instead of multi sector processing which revealed to be excessive bureaucratic before the expected goals. This study can be used by nuclear facilities to optimize an existing system of improvements analysis or even guide them for the implantation of a new one. It is more significant for the companies certified on ISO and OHSAS standards for the quality management, environmental and safety and occupational health systems which requires that the continuous improvement must exist and to be demonstrated. But it is also relevant for nuclear plants aiming to implement an Integrated Management System certified on ISO Standards. (author)

  16. EVALUATED NUCLEAR STRUCTURE DATA FILE -- A MANUAL FOR PREPARATION OF DATA SETS.

    Energy Technology Data Exchange (ETDEWEB)

    TULI, J.K.

    2001-02-01

    This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, A {le} 293), the Evaluated Nuclear Structure Data File (ENSDF) contains evaluated structure information. For masses A {ge} 44, this information is published in the Nuclear Data Sheets; for A < 44, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chain or by nuclide with a varying cycle time dependent on the availability of new information.

  17. Evaluated nuclear structure data file: A manual for preparation of data sets

    Energy Technology Data Exchange (ETDEWEB)

    Tuli, J.K.

    1987-04-01

    This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, Aless than or equal to263), the Evaluated Nuclear Structure Data File (ENSDF) contains evaluated structure information. For masses Agreater than or equal to45, this information is documented in the Nuclear Data Sheets; for A<45, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chains with a present cycle time of approximately six years.

  18. The ENSDF_toolbox program package: tool for the evaluator of nuclear data

    OpenAIRE

    Shulyak, G. I.; A. A. Rodionov

    2010-01-01

    The program package for the work with the Evaluated Nuclear Structure Data File is discussed. The program shell designed for the unification of the process of the evaluation of the nuclear data is proposed. This program shell may be used in the regular work of the nuclear data evaluator and for common use by scientists and engineers who need the actual data about nuclear states and transitions from the ENSDF database.

  19. Parameter Validation for Evaluation of Spaceflight Hardware Reusability

    Science.gov (United States)

    Childress-Thompson, Rhonda; Dale, Thomas L.; Farrington, Phillip

    2017-01-01

    Within recent years, there has been an influx of companies around the world pursuing reusable systems for space flight. Much like NASA, many of these new entrants are learning that reusable systems are complex and difficult to acheive. For instance, in its first attempts to retrieve spaceflight hardware for future reuse, SpaceX unsuccessfully tried to land on a barge at sea, resulting in a crash-landing. As this new generation of launch developers continues to develop concepts for reusable systems, having a systematic approach for determining the most effective systems for reuse is paramount. Three factors that influence the effective implementation of reusability are cost, operability and reliability. Therefore, a method that integrates these factors into the decision-making process must be utilized to adequately determine whether hardware used in space flight should be reused or discarded. Previous research has identified seven features that contribute to the successful implementation of reusability for space flight applications, defined reusability for space flight applications, highlighted the importance of reusability, and presented areas that hinder successful implementation of reusability. The next step is to ensure that the list of reusability parameters previously identified is comprehensive, and any duplication is either removed or consolidated. The characteristics to judge the seven features as good indicators for successful reuse are identified and then assessed using multiattribute decision making. Next, discriminators in the form of metrics or descriptors are assigned to each parameter. This paper explains the approach used to evaluate these parameters, define the Measures of Effectiveness (MOE) for reusability, and quantify these parameters. Using the MOEs, each parameter is assessed for its contribution to the reusability of the hardware. Potential data sources needed to validate the approach will be identified.

  20. Evaluations of Molecular Nuclear Medicine in pediatric urgencies; Evaluaciones de Medicina Nuclear Molecular en urgencias pediatricas

    Energy Technology Data Exchange (ETDEWEB)

    Martinez-Duncker R, C. [Departamento de Medicina Nuclear Molecular, Hospital Infantil de Mexico, Mexico D.F. (Mexico)

    2000-07-01

    Several diagnostic procedures of Molecular Nuclear Medicine are considered in first choice in clinical evaluation of patients with different illnesses. So, the gammagraphy is the diagnostic form more sensitive to detect alterations of the perfusion on organs and systems such as bones, heart, brain, lungs or kidneys. Also is possible to identify, localize, evaluate the activity of inflammatory processes such as cellulitis, arthritis, osteomyelitis, the abscesses and several primary or metastatic tumours before each other diagnostic technique. In this work is treated about the importance of treatments with radioactive materials have been an important reappearance in last years since with the present capacity to localize specifically intracellular processes (for example, synthesis of DNA) new gateways are opened to research which in coming years would be of great utility. (Author)

  1. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an

  2. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-10-01

    This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

  3. Relativistic theory of nuclear magnetic resonance parameters in a Gaussian basis representation.

    Science.gov (United States)

    Kutzelnigg, Werner; Liu, Wenjian

    2009-07-28

    The calculation of NMR parameters from relativistic quantum theory in a Gaussian basis expansion requires some care. While in the absence of a magnetic field the expansion in a kinetically balanced basis converges for the wave function in the mean and for the energy with any desired accuracy, this is not necessarily the case for magnetic properties. The results for the magnetizability or the nuclear magnetic shielding are not even correct in the nonrelativistic limit (nrl) if one expands the original Dirac equation in a kinetically balanced Gaussian basis. This defect disappears if one starts from the unitary transformed Dirac equation as suggested by Kutzelnigg [Phys. Rev. A 67, 032109 (2003)]. However, a new difficulty can arise instead if one applies the transformation in the presence of the magnetic field of a point nucleus. If one decomposes certain contributions, the individual terms may diverge, although their sum is regular. A controlled cancellation may become difficult and numerical instabilities can arise. Various ways exist to avoid these singularities and at the same time get the correct nrl. There are essentially three approaches intermediate between the transformed and the untransformed formulation, namely, the bispinor decomposition, the decomposition of the lower component, and the hybrid unitary transformation partially at operator and partially at matrix level. All three possibilities were first considered by Xiao et al. [J. Chem. Phys. 126, 214101 (2007)] in a different context and in a different nomenclature. Their analysis and classification in a more general context are given here for the first time. Use of an extended balanced basis has no advantages and has other drawbacks and is not competitive, while the use of a restricted magnetic balance basis can be justified.

  4. Evaluation of the feasibility, economic impact, and effectiveness of underground nuclear power plants. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    1978-05-01

    Information on underground nuclear power plants is presented concerning underground nuclear power plant concepts; public health impacts; technical feasibility of underground concepts; economic impacts of underground construction; and evaluation of related issues.

  5. Relativistic effects in the intermolecular interaction-induced nuclear magnetic resonance parameters of xenon dimer

    DEFF Research Database (Denmark)

    Hanni, Matti; Lantto, Perttu; Ilias, Miroslav

    2007-01-01

    Relativistic effects on the 129Xe nuclear magnetic resonance shielding and 131Xe nuclear quadrupole coupling (NQC) tensors are examined in the weakly bound Xe2 system at different levels of theory including the relativistic four-component Dirac-Hartree-Fock (DHF) method. The intermolecular intera...

  6. The Effects of Design Parameters on Nanoparticle Cellular Uptake, Nuclear Transport and Accumulation

    Science.gov (United States)

    Tang, Peter Shih-Yi

    Studying the effects of the physicochemical properties of nanomaterials on cellular uptake, toxicity, and exocytosis can provide the foundation for designing safer and more effective nanoparticles for clinical applications. However, an understanding of the effects of these properties on subcellular transport, accumulation and distribution remains limited. The present study investigates the effects of surface density and particle size of semiconductor quantum dots on cellular uptake as well as nuclear transport kinetics, retention, and accumulation. The current work illustrates that cellular uptake and nuclear accumulation of nanoparticles depends on surface density of the nuclear localization signal peptides with nuclear transport reaching a plateau at 20% surface nuclear localization signal peptide density in as little as 30 minutes. These intracellular nanoparticles have no effects on cell viability up to 72 hours post treatment. These findings will set a foundation for engineering more sophisticated nanoparticle systems for imaging and manipulating genetic targets in the nucleus.

  7. A Methodology for Evaluating Quantitative Nuclear Safety Culture Impact

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kiyoon; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

    2015-05-15

    Through several accidents of NPPs including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, nuclear safety culture has been emphasized in reactor safety world-widely. In Korea, KHNP evaluates the safety culture of NPP itself. KHNP developed the principles of the safety culture in consideration of the international standards. A questionnaire and interview questions are also developed based on these principles and it is used for evaluating the safety culture. However, existing methodology to evaluate the safety culture has some disadvantages. First, it is difficult to maintain the consistency of the assessment. Second, the period of safety culture assessment is too long (every two years) so it has limitations in preventing accidents occurred by a lack of safety culture. Third, it is not possible to measure the change in the risk of NPPs by weak safety culture since it is not clearly explains the effect of safety culture on the safety of NPPs. In this study, Safety Culture Impact Assessment Model (SCIAM) is developed overcoming these disadvantages. In this study, SCIAM which overcoming disadvantages of exiting safety culture assessment method is developed. SCIAM uses SCII to monitor the statues of the safety culture periodically and also uses RCDF to quantify the safety culture impact on NPP's safety. It is significant that SCIAM represents the standard of the healthy nuclear safety culture, while the exiting safety culture assessment presented only vulnerability of the safety culture of organization. SCIAM might contribute to monitoring the level of safety culture periodically and, to improving the safety of NPP.

  8. Impact-parameter dependent nuclear parton distribution functions: EPS09s and EKS98s and their applications in nuclear hard processes

    CERN Document Server

    Helenius, Ilkka; Honkanen, Heli; Salgado, Carlos A

    2012-01-01

    We determine the spatial (impact parameter) dependence of nuclear parton distribution functions (nPDFs) using the $A$-dependence of the spatially independent (averaged) global fits EPS09 and EKS98. We work under the assumption that the spatial dependence can be formulated as a power series of the nuclear thickness functions $T_A$. To reproduce the $A$-dependence over the entire $x$ range we need terms up to $[T_A]^4$. As an outcome, we release two sets, EPS09s (LO, NLO, error sets) and EKS98s, of spatially dependent nPDFs for public use. We also discuss the implementation of these into the existing calculations. With our results, the centrality dependence of nuclear hard-process observables can be studied consistently with the globally fitted nPDFs for the first time. As an application, we first calculate the LO nuclear modification factor $R^{1jet}_{AA}$ for primary partonic-jet production in different centrality classes in Au+Au collisions at RHIC and Pb+Pb collisions at LHC. Also the corresponding central-...

  9. GENETIC AND ENVIRONMENTAL PARAMETERS IN TROTTERS RACING PERFOMANCE EVALUATION

    Directory of Open Access Journals (Sweden)

    Mato Čačić

    2012-12-01

    Full Text Available Breeding goal and selection measures in breeding of trotter horses are subjected to horses production with the fastest possible speed in trotting. Evaluation of racing horses’ performances is important because of horse impact on horse industry. More valuable horses and larger prizing fond result in a higher attendance of hippodromes and more money paid in betting offices. Race horse industry notes a large number of data used in predictions during breeding of horses with better racing performances every year. Racing performances are affected by a large number of genetic and environmental (non-genetic factors caused by different environmental effects. Therefore, they are more variable. The major genetic and environmental parameters used in the models of breeding values racehorses in this case trotters are reviewed in this paper.

  10. Coherent investigation of nuclear data at CEA DAM: Theoretical models, experiments and evaluated data

    Energy Technology Data Exchange (ETDEWEB)

    Bauge, E.; Belier, G.; Cartier, J.; Chatillon, A.; Daugas, J.M.; Delaroche, J.P.; Dossantos-Uzarralde, P.; Duarte, H.; Dubray, N.; Ducauze-Philippe, M.; Gaudefroy, L.; Gosselin, G.; Granier, T.; Hilaire, S.; Chau, Huu-Tai P.; Laborie, J.M.; Laurent, B.; Ledoux, X.; Le Luel, C.; Meot, V.; Morel, P.; Morillon, B.; Roig, O.; Romain, P.; Taieb, J.; Varignon, C. [CEA, DAM, DIF, Arpajon (France); Authier, N.; Casoli, P.; Richard, B. [CEA Valduc, Is-sur-Tille (France)

    2012-08-15

    The domain of evaluated nuclear data involves at the same time, a close interaction between the field of nuclear applications and that of nuclear physics, and a close interaction between experiments and theory. The final product, the evaluated data file, synthesises vast amounts of information stemming from all of the above fields. In CEA DAM, all these aspects of nuclear data are investigated in a consistent way, making full use of experimental facilities and high-performance computing as well as numerous national and international collaborations, for the measurement, calculation, evaluation, and validation of nuclear data. (orig.)

  11. Spinopelvic parameters evaluation in a Brazilian population sample.

    Science.gov (United States)

    Jacob, C J; Cardoso, I M; Batista, J L J; Maia, T C; Roncaglio, B

    2015-07-01

    The morphology of the spine is variable within a population, and its maintenance in appropriate values implies a decrease in the energy expended. We need to know their normal values in population. This study aims to carry out a literature review and evaluate published papers on spinopelvic parameters in a Brazilian population sample. Eleven potentially eligible papers were initially identified for inclusion in this review: three papers from PubMed and eight from Medicine. Out of these, only five papers contained methodology and relevant significance level, and therefore, they were included in the final analytical run. According to a Brazilian study, Pratali mentions no significant difference in the average values of spinopelvic balance in the Brazilian population and those found in the literature; there was also no significant difference comparing Brazilian and Korean population; however, a difference was found in comparison with European population regarding PI parameters and SS, but the latter with higher values. According to Kulcheski (Column/Columna 12:224-227, 2013), the values of pelvic tilt in the Brazilian population evaluated in his research were 19° (10°-35°) and the sacral inclination was 38° (30°-55°), presenting similar values concerning the European population. In another Brazilian paper, Oliveira (Rev Bras Ort 49:189-193, 2014) reports that the research population had PI average of 45° (41.9°-48.1°). The values obtained are relatively minor when compared to the European population. However, all of these are within the normal margin considered in the worldwide literature.

  12. Evaluation by nuclear relaxation of hydrogen tucuman irradiated fruit

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Keila dos Santos Cople; Lima, Antonio Luis dos Santos, E-mail: keila@ime.eb.br, E-mail: santoslima@ime.eb.br [Instituto Militar de Engenharia. Secao de Engenharia Quimica (IME), Rio de Janeiro, RJ (Brazil); Araujo, Leandro Moreira; Tavares, Maria Ines Bruno, E-mail: mibt@ima.ufrj.br [Instituto de Macromoleculas Professora Eloisa Mano (IMA/UFRJ), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    The tucuman (Astrocarium vulgare Mart.) develops a yellow-orange fibrous pulp and a yellow-green peel as it gets mature. In Brazil it is considered a good source of carotenoids, which is the main precursor of vitamin A. Considering that the irradiation process is an alternative to avoid post-harvesting losses, without changing the nutritional value of food, this study had the objective of evaluating of different gamma irradiation doses (0.0; 0.5; 1.0; 2.0 kGy) in Tucuman samples, divided into control (non irradiated) and irradiated, by the low-field Magnetic Nuclear Resonance (NMR) analysis. The technique is used in quantitative determinations of nondestructively and non-invasive instrumentation employing low, with minimal sample, quickly, preserving its constitution and nature. (author)

  13. Dependence of nuclear quadrupole resonance transitions on the electric field gradient asymmetry parameter for nuclides with half-integer spins

    Science.gov (United States)

    Cho, Herman

    2016-09-01

    Allowed transition energies and eigenstate expansions have been calculated and tabulated in numerical form as functions of the electric field gradient asymmetry parameter for the zero field Hamiltonian of quadrupolar nuclides with I = 3 / 2 , 5 / 2 , 7 / 2, and 9 / 2. These results are essential to interpret nuclear quadrupole resonance (NQR) spectra and extract accurate values of the electric field gradient tensors. Applications of NQR methods to studies of electronic structure in heavy element systems are proposed.

  14. Evaluation of the 235U resonance parameters to fit the standard recommended values

    Directory of Open Access Journals (Sweden)

    Leal Luiz

    2017-01-01

    Full Text Available A great deal of effort has been dedicated to the revision of the standard values in connection with the neutron interaction for some actinides. While standard data compilation are available for decades nuclear data evaluations included in existing nuclear data libraries (ENDF, JEFF, JENDL, etc. do not follow the standard recommended values. Indeed, the majority of evaluations for major actinides do not conform to the standards whatsoever. In particular, for the n +  235U interaction the only value in agreement with the standard is the thermal fission cross section. A resonance re-evaluation of the n +  235U interaction has been performed to address the issues regarding standard values in the energy range from 10−5 eV to 2250 eV. Recently, 235U fission cross-section measurements have been performed at the CERN Neutron Time-of-Flight facility (TOF, known as n_TOF, in the energy range from 0.7 eV to 10 keV. The data were normalized according to the recommended standard of the fission integral in the energy range 7.8 eV to 11 eV. As a result, the n_TOF averaged fission cross sections above 100 eV are in good agreement with the standard recommended values. The n_TOF data were included in the 235U resonance analysis that was performed with the code SAMMY. In addition to the average standard values related to the fission cross section, standard thermal values for fission, capture, and elastic cross sections were also included in the evaluation. This paper presents the procedure used for re-evaluating the 235U resonance parameters including the recommended standard values as well as new cross section measurements.

  15. Impedance cardiography: A valuable method of evaluating haemodynamic parameters.

    Science.gov (United States)

    Sodolski, Tomasz; Kutarski, Andrzej

    2007-01-01

    This year marks 40 years since the technique was designed of measuring and monitoring the basic haemodynamic parameters in humans by means of impedance cardiography (ICG), also known as "impedance plethysmography of the chest", "electrical bioimpedance of the chest" or "reocardiography". The method makes it possible to denote stroke volume and cardiac output. It also enables the factors to be assessed that influence the following: preload (measurement of thoracic fluid content), afterload (measurement of systemic vascular resistance), the systemic vascular resistance index, contractibility (measurement of the acceleration index), the velocity index, the pre-ejection period, left ventricular ejection time, systolic time ratio and heart rate. Advances in hardware and software, including digital signal tooling and new algorithms, have certainly improved the quality of the results obtained. The accuracy and repeatability of the results have been confirmed in comparative studies with results obtained through invasive methods and echocardiography. Not only are haemodynamic changes monitored by means of ICG in intensive care units, in operating theatres and at haemodialysis stations, but repeated measurements also provide haemodynamic information during the treatment of patients with hypertension and heart failure and pregnant women with cardiological problems and gestosis. A single ICG investigation makes a great contribution to the basic information available about the circulatory system, which is helpful in the initial evaluation of patients in a severe general condition (for example in the admission room), and also makes it possible to make a swift diagnosis of the cause of complaints such as dyspnoea and hypotonia. A particular application of ICG is the assessment of haemodynamic parameters during the programming of atrioventricular and CRT pacemakers. Besides these uses, ICG is a valuable investigative tool. It is defect-free and does not have pulmonary artery

  16. Evaluation of Non-Nuclear Techniques for Well Logging: Technology Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Bond, Leonard J.; Denslow, Kayte M.; Griffin, Jeffrey W.; Dale, Gregory E.; Harris, Robert V.; Moran, Traci L.; Sheen, David M.; Schenkel, Thomas

    2010-11-01

    This report presents an initial review of the state-of-the-art nuclear and non-nuclear well logging methods and seeks to understand the technical and economic issues if AmBe, and potentially other isotope sources, are reduced or even eliminated in the oil-field services industry. Prior to considering alternative logging technologies, there is a definite need to open up discussions with industry regarding the feasibility and acceptability of source replacement. Industry views appear to range from those who see AmBe as vital and irreplaceable to those who believe that, with research and investment, it may be possible to transition to electronic neutron sources and employ combinations of non-nuclear technologies to acquire the desired petro-physical parameters. In one sense, the simple answer to the question as to whether petro-physical parameters can be sensed with technologies other than AmBe is probably "Yes". The challenges come when attention turns to record interpretation. The many decades of existing records form a very valuable proprietary resource, and the interpretation of subtle features contained in these records are of significant value to the oil-gas exploration community to correctly characterize a well. The demonstration of equivalence and correspondence/correlation between established and any new sensing modality, and correlations with historic records is critical to ensuring accurate data interpretation. Establishing the technical basis for such a demonstration represents a significant effort.

  17. Evaluation of Cardiometabolic Parameters among Obese Women Using Oral Contraceptives.

    Science.gov (United States)

    Ferreira, Júnia Raquel Dutra; Aleluia, Milena Magalhães; Figueiredo, Camylla Vilas Boas; Vieira, Larissa Castro de Lima; Santiago, Rayra Pereira; da Guarda, Caroline Conceição; Barbosa, Cynara Gomes; Oliveira, Ricardo Riccio; Adorno, Elisângela Vitória; Gonçalves, Marilda de Souza

    2017-01-01

    Combined oral contraceptive (COC) use has been associated with an unfavorable impact on carbohydrate and lipid metabolism in diverse populations of normal weight and obese women. The present study aimed to evaluate the cardiometabolic and inflammatory profiles of women in northeastern Brazil with respect to COC use and obesity. We performed a cross-sectional study to verify cardiovascular parameters, including blood pressure (BP), fasting serum glucose, lipid, and inflammatory profile, in a population of women aged 15-45 years, considering obesity and COC use. Our sample consisted of 591 women, 481 women who were COC users, and 110 age-matched women who were COC non-users, classified as obese and non-obese according to BMI. COC use and obesity were associated with increased systolic (p ≤ 0.001) and diastolic BP (p = 0.001), blood glucose (p ≤ 0.001), total cholesterol (p = 0.008), low-density lipoprotein cholesterol (p ≤ 0.001), very low-density lipoprotein cholesterol (p ≤ 0.001), triglycerides (p ≤ 0.001), ferritin (p = 0.006), C-reactive protein (CRP) (p ≤ 0.001), and nitric oxide metabolites (p ≤ 0.001), as well as decreased high-density lipoprotein cholesterol (HDL-c) (p ≤ 0.001) in comparison to controls. CRP and HDL-c levels in obese COC users were determined to be outside reference range values. The odds of having lower levels of HDL-c and elevated CRP increased among obese COC users. COC use was independently associated with low levels of HDL-c, especially second-generation progestins (p < 0.001; OR = 8.976; 95% CI 2.786-28.914). Obesity and COC use were associated with alterations in lipid and inflammatory cardiometabolic parameters, particularly increased CRP levels and decreased HDL-c, which are considered markers of cardiovascular disease (CVD) risk. Given the need to prevent unintended pregnancy among obese women, together with weight loss counseling, it is important to evaluate the

  18. A Guidebook for Evaluating Organizations in the Nuclear Industry - an example of safety culture evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Oedewald, Pia; Pietikaeinen, Elina; Reiman, Teemu [VTT, Technical Research Centre of Finland, Espoo (Finland)

    2011-06-15

    Organizations in the nuclear industry need to maintain an overview on their vulnerabilities and strengths with respect to safety. Systematic periodical self assessments are necessary to achieve this overview. This guidebook provides suggestions and examples to assist power companies but also external evaluators and regulators in carrying out organizational evaluations. Organizational evaluation process is divided into five main steps. These are: 1) planning the evaluation framework and the practicalities of the evaluation process, 2) selecting data collection methods and conducting the data acquisition, 3) structuring and analysing the data, 4) interpreting the findings and 5) reporting the evaluation results with possible recommendations. The guidebook emphasises the importance of a solid background framework when dealing with multifaceted phenomena like organisational activities and system safety. The validity and credibility of the evaluation stem largely from the evaluation team's ability to crystallize what they mean by organization and safety when they conduct organisational safety evaluations - and thus, what are the criteria for the evaluation. Another important and often under-considered phase in organizational evaluation is interpretation of the findings. In this guidebook a safety culture evaluation in a Nordic nuclear power plant is presented as an example of organizational evaluation. With the help of the example, challenges of each step in the organizational evaluation process are described. Suggestions for dealing with them are presented. In the case example, the DISC (Design for Integrated Safety culture) model is used as the evaluation framework. The DISC model describes the criteria for a good safety culture and the organizational functions necessary to develop a good safety culture in the organization.

  19. Evaluation of nuclear energy in the context of energy security

    Energy Technology Data Exchange (ETDEWEB)

    Irie, Kazutomo; Kanda, Keiji [Kyoto Univ., Graduate School of Energy Science, Kyoto (Japan)

    2002-06-01

    This paper analyzes the view expressed by the Japanese government on the role of nuclear energy for energy security through scrutiny of Japan's policy documents. The analysis revealed that the contribution by nuclear energy to Japan's energy security has been defined in two ways. Nuclear energy improves short-term energy security with its characteristics such as political stability in exporting countries of uranium, easiness of stockpiling of nuclear fuels, stability in power generation cost, and reproduction of plutonium and other fissile material for use by reprocessing of spent fuel. Nuclear energy also contributes to medium- and long-term energy security through its characteristics that fissile material can be reproduced (multiplied in the case of breeder reactor) from spent fuels. Further contribution can be expected by nuclear fusion. Japan's energy security can be strengthened not only by expanding the share of nuclear energy in total energy supply, but also by improving nuclear energy's characteristics which are related to energy security. Policy measures to be considered for such improvement will include (a) policy dialogue with exporting countries of uranium, (b) government assistance to development of uranium mines, (c) nuclear fuel stockpiling, (d) reprocessing and recycling of spent fuels, (e) development of fast breeder reactor, and (f) research of nuclear fusion. (author)

  20. Evaluation of the 125Sb nuclear decay data

    Science.gov (United States)

    Lile, Liu; Xiaolong, Huang; Mengxiao, Kang; Guochang, Chen; Jimin, Wang; Liyang, Jiang

    2016-02-01

    Evaluation of the complete decay scheme and data for 125Sb/125mTe decay to nuclear levels in 125Te is presented in this report; literature data available up to June 2015 are included. The Limitation of Relative Statistical Weight Method (LRSW) was applied to average numbers throughout the evaluation. The uncertainty assigned to the average value was always greater than or equal to the smallest uncertainty of the values used to calculate the average. The half-life has been determined to be 1007.4±0.3 days. All known measured γ-ray absolute or relative intensities have been examined; the γ-ray emission probability of the reference γ-ray line of 427.874 keV is recommended to be 29.54±0.10%. The theoretical internal conversion coefficients and their uncertainties were used to obtain the complete decay scheme intensity balance. The values of other decay characteristics were calculated using the ENSDF analysis program. Finally the updated decay scheme for 125Sb is presented.

  1. Evaluation of the {sup 125}Sb nuclear decay data

    Energy Technology Data Exchange (ETDEWEB)

    Lile, Liu; Xiaolong, Huang, E-mail: huang@ciae.ac.cn; Mengxiao, Kang; Guochang, Chen; Jimin, Wang; Liyang, Jiang

    2016-02-01

    Evaluation of the complete decay scheme and data for {sup 125}Sb/{sup 125m}Te decay to nuclear levels in {sup 125}Te is presented in this report; literature data available up to June 2015 are included. The Limitation of Relative Statistical Weight Method (LRSW) was applied to average numbers throughout the evaluation. The uncertainty assigned to the average value was always greater than or equal to the smallest uncertainty of the values used to calculate the average. The half-life has been determined to be 1007.4±0.3 days. All known measured γ-ray absolute or relative intensities have been examined; the γ-ray emission probability of the reference γ-ray line of 427.874 keV is recommended to be 29.54±0.10%. The theoretical internal conversion coefficients and their uncertainties were used to obtain the complete decay scheme intensity balance. The values of other decay characteristics were calculated using the ENSDF analysis program. Finally the updated decay scheme for {sup 125}Sb is presented.

  2. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Song, Sung Jin; Kim, Young Hwan; Shin, Hyun Jae [Sungkwunkwan Univ., Seoul (Korea, Republic of); Lee, Hyang Beom [Soongsil Univ., Seoul (Korea, Republic of); Shin, Young Kil [Kunsan National Univ., Gunsan (Korea, Republic of); Chung, Hyun Jo [Wonkwang Univ., Iksan (Korea, Republic of); Park, Ik Keun; Park, Eun Soo [Seoul National University of Technology, Seoul (Korea, Republic of)

    2001-03-15

    Retaining reliabilities of nondestructive testing is essential for the life-time maintenance of nuclear power plant. In order to Improve reliabilities of ultrasonic testing and eddy current testing, the following five subjects were carried out in this study: development of BEM analysis technique for ECT of SG tube, development of neural network technique for the intelligent analysis of ECT flaw signals of SG tubes, development of RFECT technology for the inspection of SG tube, FEM analysis of ultrasonic scattering field and evaluation of statistical reliability of PD-RR test of ultrasonic testing. As results, BEM analysis of eddy current signal, intelligent analysis of eddy current signal using neural network, and FEM analysis of remote field eddy current testing have been developed for the inspection of SG tubes. FEM analysis of ultrasonic waves in 2-dimensional media and evaluation of statistical reliability of ultrasonic testing with PD-RR test also have been carried out for the inspection of weldments. Those results can be used to Improve reliability of nondestructive testing.

  3. Evaluation of wind capacity credit considering key system parameters

    Energy Technology Data Exchange (ETDEWEB)

    Hu, P.; Karki, R.; Billinton, R. [Saskatchewan Univ., Saskatoon, SK (Canada). Power Systems Research Group

    2008-07-01

    This paper discussed the importance of considering the capacity credit of wind sources given that wind power penetration in power generation continues to increase. The capacity credit of a wind source is the amount of conventional capacity that can be replaced by wind energy without the loss of system reliability. As such, the reliability benefit of adding a wind energy conversion system to a power system must be analyzed. A quantitative index was used to examine the effect of key system variables on system reliability in order to estimate wind capacity credit as a function of wind penetration in electric power systems. The size and the composition of the generating system were among the parameters examined along with the wind regime at the wind farm locations and the wind power penetration level. The method for evaluating the adequacy of a power system includes separate steps for wind data modeling, wind turbine generator (WTG) modeling, combined wind and conventional generation unit modeling, load modeling and convolution of generation and load models to obtain the system risk indices. The loss of load expectation (LOLE) was also used as the risk index for reliability evaluation. The different factors that affect the capacity credit of WTG were combined to obtain the general relationship between the effective capacity ratio (ECR) and the wind penetration level (WPL). The study showed that WTG capacity credit is highly influenced by the WPL, and the wind regime at the wind farm location. The size and composition of the system and the generating units, and the LOLE reliability criterion did not have much influence on the ECR of wind sources. The obtained results were combined to produce a general approximate relationship between the wind capacity credit and the wind penetration. It was concluded that the general approximation of capacity credit of wind sources presented in this study could prove useful in determining the capacity credit of wind sources at different

  4. Evaluation of electrocardiographic parameters in patients with diabetes insipidus.

    Science.gov (United States)

    Deniz, Ferhat; Kepez, Alper; Ay, Seyit Ahmet; Ergogan, Okan; Baskoy, Kamil; Guncıkan, Mustafa Nuri; Dogan, Zekeriya; Yonem, Arif

    2015-11-01

    There is limited data regarding the effect of altered serum osmolality on cardiac electrical activity. The aim of the present study is to evaluate the electrocardiographic (ECG) effects of diabetes insipidus (DI) and any related hyperosmolality in a population of young patients with DI and without any known cardiovascular disease or risk factors. Twelve-lead ECG's of 44 consecutive untreated young male patients (age: 21.8 ± 2.9 years) who had been referred to endocrinology clinic and diagnosed as DI based on water deprivation test were retrospectively evaluated. A total of 30 age-matched (21.9 ± 2.4 years) healthy males were selected as control group and ECG's of these controls were obtained for comparison with ECG's of DI patients. All ECG parameters were measured and compared. Duration of QRS complex was significantly shorter in patients with DI compared with controls (85.2 ± 12.0 vs. 94.0 ± 10.6 ms, p: 0.001). P wave dispersion (PWD) of patients with DI was significantly higher compared with controls (31.9 ± 9.9 vs. 26.5 ± 10.6 ms, p: 0.03) and it was significantly correlated with serum osmolality and serum sodium level (r = - 0.36, p: 0.02 and r: - 0.35, p: 0.02, respectively). DI patients without any cardiovascular disease or risk factors displayed significantly shorter QRS duration and increased p wave dispersion compared with controls.

  5. Improvement of evaluated neutron nuclear data for {sup 237}Np and {sup 241}Am

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo; Iwamoto, Osamu; Hasegawa, Akira [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-01-01

    The nuclear data of {sup 237}Np and {sup 241}Am that are particularly important among the minor actinides were investigated by comparing JENDL-3.2 with the recent evaluated data and available experimental data. As a result of the study, several defects of JENDL-3.2 data were revealed. They were improved on the basis of experimental data or recent evaluated data. For the both nuclides, main quantities revised in the present work were the resonance parameters, cross sections, angular and energy distributions of secondary neutrons, number of neutrons per fission. The data were given in the neutron energy range from 10{sup -5} eV to 20 MeV, and compiled in the ENDF-6 format. (author)

  6. Evaluating the parameters of a mobile maize dryer in practice

    Directory of Open Access Journals (Sweden)

    Josef Los

    2013-01-01

    Full Text Available The method of drying maize for grain has been recently employed on a large scale in the Czech Republic not only thanks to new maize hybrids but also thanks to the existence of new models of drying plants. One of the new post-harvest lines is a plant in Lipoltice (mobile dryer installed in 2010, storage base in 2012 where basic operational measurements were made of the energy intensiveness of drying and operating parameters of the maize dryer were evaluated. The process of maize drying had two stages, i.e. pre-drying from the initial average grain humidity of 28.55% to 19.6% in the first stage, and the additional drying from 16.7% to a final storage grain humidity of 13.7%. Mean volumes of natural gas consumed per 1 t% for drying in the first and second stage amounted to 1.275 m3 and 1.56 m3, respectively. The total mean consumption of electric energy per 1 t% was calculated to be 1.372 kWh for the given configuration of the post-harvest line.

  7. Evaluation of Critical Parameters to Improve Slope Drainage System

    Directory of Open Access Journals (Sweden)

    Yong Weng Long

    2017-01-01

    Full Text Available This study focuses on identifying and evaluating critical parameters of various drainage configurations, arrangement, and filter which affect the efficiency of water draining system in slopes. There are a total of seven experiments with different types of homogeneous soil, drainage envelope, filter material, and quantity of pipes performed utilizing a model box with a dimension of 0.8 m × 0.8 m × 0.6 m. The pipes were orientated at 5 degrees from the horizontal. Rainfall event was introduced via a rainfall simulator with rainfall intensity of 434.1 mm/h. From the experiments performed, the expected outcomes when utilizing double pipes and geotextile as envelope filter were verified in this study. The results obtained from these experiments were reviewed and compared with Chapter 14 “Subsurface Drainage Systems” of DID’s Irrigation and Agricultural Drainage Manual of Malaysia and the European standard. It is recommended that the pipe installed in the slope could be wrapped with geotextile and in tandem with application of granular filter to minimize clogging without affecting the water discharge rate. Terzaghi’s filter criteria could be followed closely when deciding on new materials to act as aggregate filter. A caging system could be introduced as it could maintain the integrity of the drainage system and could ease installation.

  8. Harvesting rockfall hazard evaluation parameters from Google Earth Street View

    Science.gov (United States)

    Partsinevelos, Panagiotis; Agioutantis, Zacharias; Tripolitsiotis, Achilles; Steiakakis, Chrysanthos; Mertikas, Stelios

    2015-04-01

    Rockfall incidents along highways and railways prove extremely dangerous for properties, infrastructures and human lives. Several qualitative metrics such as the Rockfall Hazard Rating System (RHRS) and the Colorado Rockfall Hazard Rating System (CRHRS) have been established to estimate rockfall potential and provide risk maps in order to control and monitor rockfall incidents. The implementation of such metrics for efficient and reliable risk modeling require accurate knowledge of multi-parametric attributes such as the geological, geotechnical, topographic parameters of the study area. The Missouri Rockfall Hazard Rating System (MORH RS) identifies the most potentially problematic areas using digital video logging for the determination of parameters like slope height and angle, face irregularities, etc. This study aims to harvest in a semi-automated approach geometric and qualitative measures through open source platforms that may provide 3-dimensional views of the areas of interest. More specifically, the Street View platform from Google Maps, is hereby used to provide essential information that can be used towards 3-dimensional reconstruction of slopes along highways. The potential of image capturing along a programmable virtual route to provide the input data for photogrammetric processing is also evaluated. Moreover, qualitative characterization of the geological and geotechnical status, based on the Street View images, is performed. These attributes are then integrated to deliver a GIS-based rockfall hazard map. The 3-dimensional models are compared to actual photogrammetric measures in a rockfall prone area in Crete, Greece while in-situ geotechnical characterization is also used to compare and validate the hazard risk. This work is considered as the first step towards the exploitation of open source platforms to improve road safety and the development of an operational system where authorized agencies (i.e., civil protection) will be able to acquire near

  9. Design of a digital system for operational parameters simulation of IPR-R1 TRIGA nuclear research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lage, Aldo M.F.; Mesquita, Amir Z.; Felippe, Adriano de A.M., E-mail: aldo@cdtn.br, E-mail: amir@cdtn.br, E-mail: adrianoamfelippe@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN /CNEN-MG), Belo Horizonte, MG (Brazil); Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil)

    2017-11-01

    The instrumentation of nuclear reactors is designed based on the reliability, redundancy and diversification of control systems. The monitoring of the parameters is of crucial importance with regard to the operational efficiency and safety of the installation. Since the first criticality of a nuclear reactor, achieved by Fermi et al. in 1942, there has been concern about the reliable monitoring of the parameters involved in the chain reaction. This paper presents the current stage of the system of simulation, which is under development at the CDTN, which intends to simulate the operation of the TRIGA IPR-R1 nuclear reactor, involving the evolution of neutron flux and reactor power related events. The system will be developed using LabVIEW® software, using the modern concept of virtual instruments (VIs) that are visualized in a video monitor. For the implementation of this model, computational tools and systems analysis are necessary, which help and facilitate the implementation of the simulator. In this article we will show some of these techniques and the initial design of the model to be implemented. The design of a computational system is of great importance, since it guides in the implementation stages and generates the documentation for later maintenance and updating of the computational system. It is noteworthy that the innovations developed in research reactors are normally used in power reactors. The relatively low costs enable research reactors to be an excellent laboratory for developing techniques for future reactors. (author)

  10. Site selection and containment evaluation for LLNL nuclear events

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, C.W.

    1993-06-01

    During approximately the past decade, the site selection process at LLNL has evolved as the Test Program needs and resources have changed, containment practices have been modified, and the DOE and other regulatory agencies have become more restrictive. Throughout this period the Containment Program and the Field Operations Program at LLNL have managed a cooperative effort to improve site selection. The site selection process actually is three inter-related tasks, namely, selection of a stockpile hole for a specific nuclear test, selection of a drill site for a stockpile hole, and selection of a new drill site for a specific test. Each proposed site is carefully reviewed for known or projected geologic structure and medium properties, nearby holes, containment experience in the region, likelihood of drilling problems, programmatic need for a given depth of hole, and scheduling of Test Program events and resources. By using our data bank, our general knowledge of the Nevada Test Site (NTS) geology, and other information sources, as well as our background in drilling large diameter holes at the NTS, we have been able to optimize our use of NTS real estate and programmatic resources. The containment evaluation of a site is facilitated by considering the location before the hole is drilled. Discuss imposed restraints and our criteria and guidelines for site selection and assignment of events to specific holes, along with the factors that influence selection of a Working Point (WP) depth. Since siting and containment evaluation are strongly related, most major factors related to the containment evaluation process will also be reviewed.

  11. Evaluation of nuclear data for R and D projects; development of database for medical nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Tae Suk [Catholic University, Seoul (Korea); Shin, D. O. [Kyung Hee University, Seoul (Korea); Joh, C. W.; Chang, J. S. [Ajou University, Suwon (Korea); Choi, Y. [Sungkyunkwan University, Seoul (Korea); Kim, S. H. [Hanyang University, Seoul (Korea); Park, S. Y. [National Cancer Center, Seoul (Korea); Shin, D. H.; Lee, S [Kyonggi University, Seoul (Korea)

    2002-04-01

    Medical nuclear data used in the country is not provided by academic associations and organizations concerned and even by government organizations concerned. This is aimed to investigate the diagnostic and therapeutic equipments in the clinical use and the domestic present status of nuclear data and physical properties of sealed or unsealed radioactive isotopes and to establish the nuclear database. About 120 domestic centers take nuclear medicine tests and 52 medical centers do radiotherapy. The 30-odd different kinds of radionuclides are usually used in nuclear medicine in the country. The 30-odd kinds of unsealed sources are used for diagnosis and therapy and 10-odd kinds of sealed sources for brachytherapy in the country. The special radiotherapy includes Gamma-knife, linac-based stereotactic radiosurgery, conformal radiotherapy and Intensity modulated radiotherapy. The nuclear data base has been completed on the basis of these data collected and the web site made is available with ease to anyone who want to get nuclear data. 39 refs., 20 figs., 8 tabs. (Author)

  12. Data formats and procedures for the Evaluated Nuclear Data File, ENDF

    Energy Technology Data Exchange (ETDEWEB)

    Garber, D.; Dunford, C.; Pearlstein, S.

    1975-10-01

    This report describes the philosophy of the Evaluated Nuclear Data File (ENDF) and the data formats and procedures that have been developed for it. The ENDF system was designed for the storage and retrieval of the evaluated nuclear data that are required for neutronics, photonics and decay heat calculations. This system is composed of several parts that include a series of data processing codes and neutron and photon cross section nuclear structure libraries.

  13. Environmental parameters of the Tennessee River in Alabama. 2: Physical, chemical, and biological parameters. [biological and chemical effects of thermal pollution from nuclear power plants on water quality

    Science.gov (United States)

    Rosing, L. M.

    1976-01-01

    Physical, chemical and biological water quality data from five sites in the Tennessee River, two in Guntersville Reservoir and three in Wheeler Reservoir were correlated with climatological data for three annual cycles. Two of the annual cycles are for the years prior to the Browns Ferry Nuclear Power Plant operations and one is for the first 14 months of Plant operations. A comparison of the results of the annual cycles indicates that two distinct physical conditions in the reservoirs occur, one during the warm months when the reservoirs are at capacity and one during the colder winter months when the reservoirs have been drawn-down for water storage during the rainy months and for weed control. The wide variations of physical and chemical parameters to which the biological organisms are subjected on an annual basis control the biological organisms and their population levels. A comparison of the parameters of the site below the Power plant indicates that the heated effluent from the plant operating with two of the three reactors has not had any effect on the organisms at this site. Recommendations given include the development of prediction mathematical models (statistical analysis) for the physical and chemical parameters under specific climatological conditions which affect biological organisms. Tabulated data of chemical analysis of water and organism populations studied is given.

  14. Referencing strategy for the direct comparison of nuclear magnetic resonance and molecular dynamics motional parameters in RNA.

    Science.gov (United States)

    Musselman, Catherine; Zhang, Qi; Al-Hashimi, Hashim; Andricioaei, Ioan

    2010-01-21

    Nuclear magnetic resonance (NMR) spectroscopy and molecular dynamics (MD) simulations are both techniques that can be used to characterize the structural dynamics of biomolecules and their underlying time scales. Comparison of relaxation parameters obtained through each methodology allows for cross validation of techniques and for complementarity in the analysis of dynamics. Here we present a combined NMR/MD study of the dynamics of HIV-1 transactivation response (TAR) RNA. We compute relaxation constants (R(1), R(2), and NOE) and model-free parameters (S(2) and tau) from a 65 ns molecular dynamics (MD) trajectory and compare them with the respective parameters measured in a domain-elongation NMR experiment. Using the elongated domain as the frame of reference for all computed parameters allows for a direct comparison between experiment and simulation. We see good agreement for many parameters and gain further insight into the nature of the local and global dynamics of TAR, which are found to be quite complex, spanning multiple time scales. For the few cases where agreement is poor, comparison of the dynamical parameters provides insight into the limits of each technique. We suggest a frequency-matching procedure that yields an upper bound for the time scale of dynamics to which the NMR relaxation experiment is sensitive.

  15. US-Based Drug Cost Parameter Estimation for Economic Evaluations.

    Science.gov (United States)

    Levy, Joseph F; Meek, Patrick D; Rosenberg, Marjorie A

    2015-07-01

    In the United States, more than 10% of national health expenditures are for prescription drugs. Assessing drug costs in US economic evaluation studies is not consistent, as the true acquisition cost of a drug is not known by decision modelers. Current US practice focuses on identifying one reasonable drug cost and imposing some distributional assumption to assess uncertainty. We propose a set of Rules based on current pharmacy practice that account for the heterogeneity of drug product costs. The set of products derived from our Rules, and their associated costs, form an empirical distribution that can be used for more realistic sensitivity analyses and create transparency in drug cost parameter computation. The Rules specify an algorithmic process to select clinically equivalent drug products that reduce pill burden, use an appropriate package size, and assume uniform weighting of substitutable products. Three diverse examples show derived empirical distributions and are compared with previously reported cost estimates. The shapes of the empirical distributions among the 3 drugs differ dramatically, including multiple modes and different variation. Previously published estimates differed from the means of the empirical distributions. Published ranges for sensitivity analyses did not cover the ranges of the empirical distributions. In one example using lisinopril, the empirical mean cost of substitutable products was $444 (range = $23-$953) as compared with a published estimate of $305 (range = $51-$523). Our Rules create a simple and transparent approach to creating cost estimates of drug products and assessing their variability. The approach is easily modified to include a subset of, or different weighting for, substitutable products. The derived empirical distribution is easily incorporated into 1-way or probabilistic sensitivity analyses. © The Author(s) 2014.

  16. Nuclear waste management issues: a multidisciplinary evaluation framework.

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, M.

    1980-02-01

    Initially, this paper characterizes the nuclear waste problem that requires analysis to establish the rationale for an interdisciplinary approach to resolve it. The problem characterization also explains why the specific concern with contaminated groundwater and intrusion through drilling has been selected for the focus of the panel meeting. The Nominal Group Technique (NGT), the group process format chosen for the experts' deliberations, is explained in some detail and its value in facilitating the desired dialogue is described. The dialogue is organized around the various issue areas that would be of concern to a program manager dealing with the potential problem of radioactivity escaping to the biosphere through human intrusion into contaminated groundwater. The participants are identified by professional discipline so that the dialogue can be presented in a realistic fashion. Both the content of the dialogue and its format are evaluated. Particular attention is given to their usefulness in generating a cross-section of subissues and factors that should be addressed when analyzing the waste disposal system's adequacy to prevent contaminated groundwater escaping to the biosphere.

  17. Integrity evaluation project for nuclear materials and components

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Seong Sik; Lee, E. H.; Kim, K. M.; and others

    2012-01-15

    A test loop has been designed to check electrochemical properties and it can control flow velocity, dissolved oxygen, pH and temperature of the coolant. The piping material of the loop is AISI 316L stainless steel and it will be tested in the range of 150-270 .deg. C and designed to 300 .deg. C for the safety of the system. Its maximum pressure is 1,000 psi and can be operated in the range of pH 7.0-10.5 and dissolved oxygen 1-100 ppb. The flow velocity can be controlled up to 10 m/s. Some major items have been purchased and a test section has been manufactured in 2011. Other items will be prepared and the test loop will be made by the first half of 2012. Corrosion tests of SA 106 Gr. B performed using static autoclave system at the condition of pH 7, 8, 9, 10, 150 .deg. C, O{sub 2}. Various sources of error occurred in high temperature thickness measurement were reviewed. In order to develop a high temperature thickness measurement technique, a proto-type shear horizontal waveguide was designed and fabricated. The ultrasonic signals with shear mode piezoelectric ultrasonic transducers showed enough SN ratio. This technique will be applied to an actual FAC mockup after experiment with various high temperatures conditions. The basic mechanisms and models on FAC phenomena was studied for pipe materials and FAC estimation programs was reviewed which was used in nuclear power plants. CHECWORKS program was mostly used for FAC mangement including Korea, it is revewed on the FAC evaluation process and the applications of this code. The improvement method was considered to use the FAC evaluation program with effective and easy usage for domestic NPPs.

  18. Evaluated nuclear structure data file. a manual for preparation of data sets

    CERN Document Server

    Tuli, J K

    2001-01-01

    This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, A = 44, this information is published in the Nuclear Data Sheets; for A < 44, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chain or by nuclide with a varying cycle time dependent on the availability of new information.

  19. Evaluation of cable ageing in Nuclear Power Plants; Evaluacion del envejecimiento de cables en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Vergara, T. [Empresarios Agrupados, A. I. E. Madrid (Spain); Alonso Chicote, J. [TECNATOM, S. A. (Spain); Burnay, S. [AEA Technology (UK)

    2000-07-01

    The majority of power, control and instrumentation cables in nuclear power plants use polymers as their basic material for insulation and jacket. In many cases, these cables form part of safety-related circuits and should therefore be capable of operating correctly under both normal and accident conditions. Since polymeric materials are degraded by the long term action of the radiation and thermal environments found in the plant, it is important to be able to establish the cable condition during the plant lifetime. Nowadays there are a number of different methods to evaluate the remaining lifetime of cables. In the case of new plants, or new cables in old plants, accelerated ageing tests and predictive models can be used to establish the behaviour of the cable materials under operating conditions. There are verified techniques and considerable experience in the definition of predictive models. This type of approach is best carried out during the commissioning stage or in the early stages of operation. In older plants, particularly where there is a wide range of cable types in use, it is more appropriate to use condition monitoring methods to establish the state of degradation of cables in-plant. Over the last 10 years there have been considerable developments in methods for condition monitoring of cables and a tool-box of practical techniques are now available. There is no single technique which is suitable for all cable materials but the range of methods covers nearly all of the types currently in use, at present, the most established methods are the indented, thermal analysis (OIT, OITP and TGA) and dielectric loss measurements, All of these are either non-destructive methods or require only micro-samples of material. (Author) 15 refs.

  20. Evaluation method of nuclear data: half-lives, gamma-ray intensities etc

    Energy Technology Data Exchange (ETDEWEB)

    Yoshizawa, Yasukazu; Miyatake, Osamu; Toyama, Masao

    1998-03-01

    The evaluation method has been studied. The basic problem is how to estimate and treat the systematic error. Nuclear decay data were evaluated. Eight practical examples of half-lives are shown in this report. (author)

  1. Derivation of parameters necessary for the evaluation of performance of sites for deep geological repositories with particular reference to bedded salt, Livermore, California. Volume I. Main text

    Energy Technology Data Exchange (ETDEWEB)

    Ashby, J.P.; Rawlings, G.E.; Soto, C.A.; Wood, D.F.; Chorley, D.W.

    1979-12-01

    A survey of parameters to be considered in the evaluation of sites for deep geologic nuclear waste repositories is presented. As yet, no comprehensive site selection procedure or performance evaluation approach has been adopted. A basis is provided for the development of parameters by discussing both site selection and performance evaluation. Three major groups of parameters are considered in this report: geologic, mining/rock mechanics, and hydrogeologic. For each type, the role of the parameter in the evaluation of repository sites is discussed. The derivation of the parameter by measurement, correlation, inference, or other method is discussed. Geologic parameters define the framework of the repository site and can be used in development of conceptual models and the prediction of long-term performance. Methods for deriving geological parameters include mapping, surveying, drilling, geophysical investigation, and historical and regional analysis. Rock mechanics/mining parameters are essential for the prediction of short-term performance and the development of initial conditions for modeling of long-term performance. Rock mechanics/mapping parameters can be derived by field or laboratory investigation, correlation, and theoretically or empirically based inference. Hydrogeologic parameters are the most important for assessment of long-term radionuclide confinement, since transport throughout the regional hydrogeologic system is the most likely mode of radionuclide escape from geologic repositories. Hydrogeologic parameters can be derived by hydrogeologic mapping and interpretation, hydrogeologic system modeling, field measurements, and lab tests. Procedures used in determination and statistical evaluation of geologic and rock mechanics parameters are discussed.

  2. Evaluation of genetic parameters for agro-metrical characters in ...

    African Journals Online (AJOL)

    plant height at 50% flowering) per cent. Flowers per plant showed low genetic gain; hence, heterosis breeding would be recommended. These characters may serve as effective selection parameter in breeding programme for crop improvement ...

  3. Dependence of nuclear quadrupole resonance transitions on the electric field gradient asymmetry parameter for nuclides with half-integer spins

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Herman

    2016-09-01

    Allowed transition energies and eigenstate expansions have been calculated and tabulated in numerical form as functions of the electric field gradient asymmetry parameter for the zero field Hamiltonian of quadrupolar nuclides with I = 3/2, 5/2, 7/2, and 9/2. These results may be used to interpret nuclear quadrupole resonance (NQR) spectra and extract accurate values of the electric field gradient tensors. Applications of NQR methods to studies of electronic structure in heavy element systems are proposed. This material is based upon work supported by the U.S. Department of Energy Office of Science, Office of Basic Energy Sciences, Heavy Element Chemistry program.

  4. Evaluation of Injection Molding Process Parameters for Manufacturing Polyethylene Terephthalate

    Directory of Open Access Journals (Sweden)

    Marwah O.M.F.

    2017-01-01

    Full Text Available Quality control is an important aspect in manufacturing process. The quality of product in injection moulding is influenced by injection moulding process parameter. In this study, the effect of injection moulding parameter on defects quantity of PET preform was investigated. Optimizing the parameter of injection moulding process is critical to enhance productivity where parameters must operate at an optimum level for an acceptable performance. Design of Experiment (DOE by factorial design approach was used to find an optimum parameter setting and reduce the defects. In this case study, Minitab 17 software was used to analyses the data. The selected input parameters were mould hot runner temperature, water cooling chiller temperature 1 and water cooling chiller temperature 2. Meanwhile, the output for the process was defects quantity of the preform. The relationship between input and output of the process was analyzed using regression method and Analysis of Variance (ANOVA. In order to interpolate the experiment data, mathematical modeling was used which consists of different types of regression equation. Next, from the model, 95% confidence level (p-value was considered and the significant parameter was figured out. This study involved a collaboration with a preform injection moulding company which was Nilai Legasi Plastik Sdn Bhd. The collaboration enabled the researchers to collect the data and also help the company to improve the quality of its production. The results of the study showed that the optimum parameter setting that could reduce the defect quantity of preform was MHR= 88°C, CT1= 24°C and CT2= 27°C. The comparison defect quantity analysis between current companies setting with the optimum setting showed improvement by 21% reduction of defect quantity at the optimum setting. Finally, from the optimization plot, the validation error between the prediction value and experiment was 1.72%. The result proved that quality of products

  5. THE AIMS AND ACTIVITIES OF THE INTERNATIONAL NETWORK OF NUCLEAR STRUCTURE AND DECAY DATA EVALUATORS.

    Energy Technology Data Exchange (ETDEWEB)

    NICHOLS,A.L.; TULI, J.K.

    2007-04-22

    International Network of Nuclear Structure and Decay Data (NSDD) Evaluators consists of a number of evaluation groups and data service centers in several countries that appreciate the merits of working together to maintain and ensure the quality and comprehensive content of the ENSDF database (Evaluated Nuclear Structure Data File). Biennial meetings of the network are held under the auspices of the International Atomic Energy Agency (IAEA) to assign evaluation responsibilities, monitor progress, discuss improvements and emerging difficulties, and agree on actions to be undertaken by individual members. The evaluated data and bibliographic details are made available to users via various media, such as the journals ''Nuclear Physics A'' and ''Nuclear Data Sheets'', the World Wide Web, on CD-ROM, wall charts of the nuclides and ''Nuclear Wallet Cards''. While the ENSDF master database is maintained by the US National Nuclear Data Center at the Brookhaven National Laboratory, these data are also available from other nuclear data centers including the IAEA Nuclear Data Section. The Abdus Salam International Centre for Theoretical Physics (ICTP), Trieste, Italy, in cooperation with the IAEA, organizes workshops on NSDD at regular intervals. The primary aims of these particular workshops are to provide hands-on training in the data evaluation processes, and to encourage new evaluators to participate in NSDD activities. The technical contents of these NSDD workshops are described, along with the rationale for the inclusion of various topics.

  6. Evaluation of passive autocatalytic recombiners operation efficiency by means of the lumped parameter approach*

    Directory of Open Access Journals (Sweden)

    Bury Tomasz

    2015-06-01

    Full Text Available The problem of hydrogen behavior in containment buildings of nuclear reactors belongs to thermal-hydraulic area. Taking into account the size of systems under consideration and, first of all, safety issues, such type of analyses cannot be done by means of full-scale experiments. Therefore, mathematical modeling and numerical simulations are widely used for these purposes. A lumped parameter approach based code HEPCAL has been elaborated in the Institute of Thermal Technology of the Silesian University of Technology for simulations of pressurized water reactor containment transient response. The VVER-440/213 and European pressurised water reactor (EPR reactors containments are the subjects of analysis within the framework of this paper. Simulations have been realized for the loss-of-coolant accident scenarios with emergency core cooling system failure. These scenarios include core overheating and hydrogen generation. Passive autocatalytic recombiners installed for removal of hydrogen has been taken into account. The operational efficiency of the hydrogen removal system has been evaluated by comparing with an actual hydrogen concentration and flammability limit. This limit has been determined for the three-component mixture of air, steam and hydrogen. Some problems related to the lumped parameter approach application have been also identified.

  7. Nuclear Fission: from more phenomenology and adjusted parameters to more fundamental theory and increased predictive power

    Directory of Open Access Journals (Sweden)

    Bulgac Aurel

    2017-01-01

    Full Text Available Two major recent developments in theory and computational resources created the favorable conditions for achieving a microscopic description of fission dynamics in classically allowed regions of the collective potential energy surface, almost eighty years after its discovery in 1939 by Hahn and Strassmann [1]. The first major development was in theory, the extension of the Time-Dependent Density Functional Theory (TDDFT [2–5] to superfluid fermion systems [6]. The second development was in computing, the emergence of powerful enough supercomputers capable of solving the complex systems of equations describing the time evolution in three dimensions without any restrictions of hundreds of strongly interacting nucleons. Thus the conditions have been created to renounce phenomenological models and incomplete microscopic treatments with uncontrollable approximations and/or assumptions in the description of the complex dynamics of fission. Even though the available nuclear energy density functionals (NEDFs are phenomenological still, their accuracy is improving steadily and the prospects of being able to perform calculations of the nuclear fission dynamics and to predict many properties of the fission fragments, otherwise not possible to extract from experiments.

  8. Nuclear Fission: from more phenomenology and adjusted parameters to more fundamental theory and increased predictive power

    Science.gov (United States)

    Bulgac, Aurel; Jin, Shi; Magierski, Piotr; Roche, Kenneth; Schunck, Nicolas; Stetcu, Ionel

    2017-11-01

    Two major recent developments in theory and computational resources created the favorable conditions for achieving a microscopic description of fission dynamics in classically allowed regions of the collective potential energy surface, almost eighty years after its discovery in 1939 by Hahn and Strassmann [1]. The first major development was in theory, the extension of the Time-Dependent Density Functional Theory (TDDFT) [2-5] to superfluid fermion systems [6]. The second development was in computing, the emergence of powerful enough supercomputers capable of solving the complex systems of equations describing the time evolution in three dimensions without any restrictions of hundreds of strongly interacting nucleons. Thus the conditions have been created to renounce phenomenological models and incomplete microscopic treatments with uncontrollable approximations and/or assumptions in the description of the complex dynamics of fission. Even though the available nuclear energy density functionals (NEDFs) are phenomenological still, their accuracy is improving steadily and the prospects of being able to perform calculations of the nuclear fission dynamics and to predict many properties of the fission fragments, otherwise not possible to extract from experiments.

  9. Accurate nuclear masses from a three parameter Kohn-Sham DFT approach (BCPM)

    Energy Technology Data Exchange (ETDEWEB)

    Baldo, M.; Robledo, L. M.; Schuck, P.; Vinas, X. [Instituto Nazionale di Fisica Nucleare, Sezione di Catania, Via Santa Sofia 64, I-95123 Catania (Italy); Dep. Fisica Teorica (Modulo 15), Universidad Autonoma de Madrid, E-28049 Madrid (Spain); Inst. de Physique Nucleaire,CNRS-IN2P3 and Univ. Paris-Sud, 91406 Orsay cedex (France); Departament d' Estructura i Conastituents de la Materia and Institut de Ciencies del Cosmos Facultat de Fisica, Universitat de Barcelona, Marti i Franques 1, 08028 (Spain)

    2012-10-20

    Given the promising features of the recently proposed Barcelona-Catania-Paris (BCP) functional [1], it is the purpose of this work to still improve on it. It is, for instance, shown that the number of open parameters can be reduced from 4-5 to 2-3, i.e. by practically a factor of two without deteriorating the results.

  10. Evaluation of selected parameters of rat liver and kidney function ...

    African Journals Online (AJOL)

    The effects of administration of yohimbine, an aphrodisiac on some functional parameters of rat liver and kidney were investigated. White male albino rats weighing between 200-250g were grouped into two such that one group was orally administered with 14mg/kg body weight on daily basis for 15days while the control ...

  11. Evaluation of some handling and processing parameters for ...

    African Journals Online (AJOL)

    Biomass materials require reduction and densification for the purpose of handling and space requirements. Guinea corn (Sorghum bi-color) is a major source of biomass material in the tropic regions. The densification process involves some measurable parameters, namely: pressure, particles size and binder ratio. Guinea ...

  12. Evaluation of the growth parameters of six commercial crossbred pig ...

    African Journals Online (AJOL)

    To test whether animals grown under ideal temperature conditions would have different growth parameters to animals grown in more conventional housing, ... Furthermore, controlling temperature had minimal effect on the allometric relationships between protein and the remaining body components for different genotypes.

  13. Synthesis and evaluation of effective parameters in thermal ...

    Indian Academy of Sciences (India)

    Variations of lattice parameters of compounds have been monitored by in-situ XRD at different temperatures in order to study the thermo-chemical expansivity. Concentration of oxide ion vacancy has been determined by high temperature gravimetry. The results show more stability of Mn4+ ions in high temperature in ...

  14. Radiographic adenoid evaluation – suggestion of referral parameters

    Directory of Open Access Journals (Sweden)

    Murilo F.N. Feres

    2014-05-01

    Conclusion: this model was shown to be potentially useful as a screening tool to include patients with, at least, two-thirds adenoid obstruction. Moreover, one of the categorical parameters was demonstrated to be relatively more useful, as well as a potentially safer assessment tool to exclude patients with less than three-quarters obstruction, to be indicated for adenoidectomy.

  15. Sexual dimorphism in tooth morphometrics: An evaluation of the parameters.

    Science.gov (United States)

    Banerjee, Abhishek; Kamath, Venkatesh V; Satelur, Krishnanand; Rajkumar, Komali; Sundaram, Lavanya

    2016-01-01

    Sexual dimorphism refers to the variations in tooth size and shape between the sexes. The consistency of these variations is valuable in the identification of the sex of an individual in times of mass disaster when whole body parts get destroyed or are unavailable. There exist differences in the expression of these variables across races and regions. This study aims to tabulate and identify the variations in tooth measurements using standarized reference points in an attempt to establish parameters of sexual dimorphism. 100 individuals (50 of each sex) in the age group 19-23 years were assessed for standard morphometric parameters of the maxillary central incisor, canine, premolar and molar. Odontometric measurements of established parameters were recorded from impression casts of the maxillary jaws. The mesiodistal width (MDW), the bucco-ligual width (BLW), the crown length (CL) and the cervical angle (CA) were charted among the teeth. The consistency of the variations was statistically analyzed and a logistic regression table was prepared to identify the sex of the individual from the tooth measurements. The BLW, MDW and CL reflected significant variations among all the teeth to be effective in establishing sexual dimorphism. CA as a parameter was inadequate across all the teeth. The permanent maxillary canine was the most important tooth to be reflective of the gender and statistically significant to be utilized for gender determination.

  16. Cyber Security Risk Evaluation of a Nuclear I&C Using BN and ET

    OpenAIRE

    Jinsoo Shin; Hanseong Son; Gyunyoung Heo

    2017-01-01

    Cyber security is an important issue in the field of nuclear engineering because nuclear facilities use digital equipment and digital systems that can lead to serious hazards in the event of an accident. Regulatory agencies worldwide have announced guidelines for cyber security related to nuclear issues, including U.S. NRC Regulatory Guide 5.71. It is important to evaluate cyber security risk in accordance with these regulatory guides. In this study, we propose a cyber security risk evaluatio...

  17. Model development for quantitative evaluation of proliferation resistance of nuclear fuel cycles

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il; Kim, Ho Dong; Yang, Myung Seung

    2000-07-01

    This study addresses the quantitative evaluation of the proliferation resistance which is important factor of the alternative nuclear fuel cycle system. In this study, model was developed to quantitatively evaluate the proliferation resistance of the nuclear fuel cycles. The proposed models were then applied to Korean environment as a sample study to provide better references for the determination of future nuclear fuel cycle system in Korea. In order to quantify the proliferation resistance of the nuclear fuel cycle, the proliferation resistance index was defined in imitation of an electrical circuit with an electromotive force and various electrical resistance components. The analysis on the proliferation resistance of nuclear fuel cycles has shown that the resistance index as defined herein can be used as an international measure of the relative risk of the nuclear proliferation if the motivation index is appropriately defined. It has also shown that the proposed model can include political issues as well as technical ones relevant to the proliferation resistance, and consider all facilities and activities in a specific nuclear fuel cycle (from mining to disposal). In addition, sensitivity analyses on the sample study indicate that the direct disposal option in a country with high nuclear propensity may give rise to a high risk of the nuclear proliferation than the reprocessing option in a country with low nuclear propensity.

  18. Review of Overall Safety Manual for space nuclear systems. An evaluation of a nuclear safety analysis methodology for plutonium-fueled space nuclear systems

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, J.; Inhaber, H.

    1984-02-01

    As part of its duties in connection with space missions involving nuclear power sources, the Office of Nuclear Safety (ONS) of the Office of Assistant Secretary for Environmental Protection, Safety, and Emergency Preparedness has been assigned the task of reviewing the Overall Safety Manual (OSM) (memo from B.J. Rock to J.R. Maher, December 1, 1982). The OSM, dated July 1981 and in four volumes, was prepared by NUS Corporation, Rockville, Maryland, for the US Department of Energy. The OSM provides many of the technical models and much of the data which are used by (1) space launch contractors in safety analysis reports and (2) the broader Interagency Nuclear Safety Review Panel (INSRP) safety evaluation reports. If fhs interaction between the OSM, contractors, and INSRP is to work effectively, the OSM must be accurate, comprehensive, understandable, and usable.

  19. EVALUATION OF FERMENTATION PARAMETERS DURING HIGH-GRAVITY BEER PRODUCTION

    OpenAIRE

    Almeida,R.B.; J.B. Almeida e Silva; U.A. Lima; Silva, D P; Assis,A.N.

    2001-01-01

    A large number of advantages are obtained from the use of highly concentrated worts during the production of beer in a process referred to as "high-gravity". However, problems related to slow or stuck fermentations, which cause the lower productivity and possibility of contamination, are encountered. This study examines the influence of factors pH, percentage of corn syrup, initial wort concentration and fermentation temperature on the fermentation parameters, namely productivity, wort attenu...

  20. Thoughts on standardization of parameters for image evaluation

    Science.gov (United States)

    Billingsley, F. C.

    1976-01-01

    Images received for image processing and analysis are obtained from a wide variety of sources and with a wide variety of sensors. Because it is desirable to have image processing algorithms be as universally applicable as possible, they should be designed, where possible, to be insensitive to the parametric variations of the source material. Where this is not possible, these variations must be taken into account. Therefore, it is necessary to consider what parameters may be defined in common across a suite of image types. Objective parameters or measurements of images which, in the proper combinations, may serve as surrogates for real images may be pixel-specific, location dependent, or combinations thereof. Parameters which have proven useful in defining the characteristics of images include the gray scale linearity, granularity of the quantization, spectral content, geometrical fidelity, resolution of the system expressed as either the point spread function or the modulation transfer function, and the spatial frequency content and characteristics of the data itself.

  1. Estimation Source Parameters of Large-Scale Chemical Surface Explosions and Recent Underground Nuclear Tests

    Science.gov (United States)

    Gitterman, Y.; Kim, S.; Hofstetter, R.

    2013-12-01

    Large-scale surface explosions were conducted by the Geophysical Institute of Israel at Sayarim Military Range (SMR), Negev desert: 82 tons of strong HE explosives in August 2009, and 10&100 tons of ANFO explosives in January 2011. The main goal was to provide strong controlled sources in different wind conditions, for calibration of IMS infrasound stations. Numerous dense observations of blast waves were provided by high-pressure, acoustic and seismic sensors at near-source ( 2000 tons) ANFO surface shots at White Sands Military Range (WSMR) were analyzed for SS time delay. The Secondary Shocks were revealed on the records in the range 1.5-60 km and showed consistency with the SMR data, thus extending the charge and distance range for the developed SS delay relationship. Obtained results suggest that measured SS delays can provide important information about an explosion source character, and can be used as a new simple cost-effective yield estimator for explosions with known type of explosives. The new results are compared with analogous available data of surface nuclear explosions. Special distinctions in air-blast waves are revealed and analyzed, resulting from the different source phenomenology (energy release). Two underground nuclear explosions conducted by North Korea in 2009 and 2013 were recorded by several stations of Israel Seismic Network. Pronounced minima (spectral nulls) at 1.2-1.3 Hz were revealed in the spectra of teleseismic P-waves. For a ground-truth explosion with a shallow source depth (relatively to an earthquake), this phenomenon can be interpreted in terms of the interference between the down-going P-wave energy and the pP phase reflected from the Earth's surface. A similar effect was observed before at ISN stations for the Pakistan explosion (28.05.98) at a different frequency 1.7 Hz indicating the source- and not site-effect. Based on the null frequency dependency on the near-surface acoustic velocity and the source depth, the depth of

  2. Update on the U.S. Nuclear Structure and Decay Data Evaluation Program*

    Science.gov (United States)

    Baglin, Coral M.

    2000-04-01

    The U.S. Nuclear Data Program (USNDP) maintains and provides easy access to several large databases to assist scientists to sift through and assess the vast quantity of published nuclear structure and decay data. The Evaluated Nuclear Structure Data File (ENSDF) presents evaluated experimental nuclear data; the Nuclear Structure Reference (NSR) database provides bibliographic information; an Experimental Unevaluated Data Listing (XUNDL)has also recently been established to provide rapid access to data from the most recent publications (primarily in high-spin physics). In addition to the ongoing revision of data in ENSDF, information from the latest evaluations for A=21-44 by Endt[1] and evaluated data for recently-discovered heavy elements (up to Z=118) are currently being incorporated into ENSDF. An overview of nuclear structure and decay data available through the USNDP will be presented, with emphasis on recent and forthcoming additions to the material available. Feedback concerning the extent to which users' nuclear structure and decay data needs are being met by this data program will be welcomed. 1. P.M. Endt, Nucl. Phys. A521, 1 (1998). *On behalf of the U.S. Nuclear Data Program

  3. Sources of evaluation of nuclear and renewable energy contained in the local press

    NARCIS (Netherlands)

    van der Pligt, J.; Spears, R.; Eiser, J.R.

    1987-01-01

    Examined the sources of evaluative coverage concerning nuclear power and renewable alternatives contained in local UK daily press coverage. 10 categories of source were defined for their relevance to the nuclear debate and energy issues. Out of these, only pronuclear industries and national

  4. High-power fiber laser cutting parameter optimization for nuclear Decommissioning

    Directory of Open Access Journals (Sweden)

    Ana Beatriz Lopez

    2017-06-01

    Full Text Available For more than 10 years, the laser process has been studied for dismantling work; however, relatively few research works have addressed the effect of high-power fiber laser cutting for thick sections. Since in the nuclear sector, a significant quantity of thick material is required to be cut, this study aims to improve the reliability of laser cutting for such work and indicates guidelines to optimize the cutting procedure, in particular, nozzle combinations (standoff distance and focus position, to minimize waste material. The results obtained show the performance levels that can be reached with 10 kW fiber lasers, using which it is possible to obtain narrower kerfs than those found in published results obtained with other lasers. Nonetheless, fiber lasers appear to show the same effects as those of CO2 and ND:YAG lasers. Thus, the main factor that affects the kerf width is the focal position, which means that minimum laser spot diameters are advised for smaller kerf widths.

  5. High-power fiber laser cutting parameter optimization for nuclear decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, Ana Beatriz; Assuncao, Eurico; Quintino, Luisa [IDMEC, Instituto Superior Tecnico, Universidade de Lisboa, Lisboa (Portugal); Khan, Ali; Blackbun, Jonathan [TWI Ltd., Cambridge (United States)

    2017-06-15

    For more than 10 years, the laser process has been studied for dismantling work; however, relatively few research works have addressed the effect of high-power fiber laser cutting for thick sections. Since in the nuclear sector, a significant quantity of thick material is required to be cut, this study aims to improve the reliability of laser cutting for such work and indicates guidelines to optimize the cutting procedure, in particular, nozzle combinations (standoff distance and focus position), to minimize waste material. The results obtained show the performance levels that can be reached with 10 kW fiber lasers, using which it is possible to obtain narrower kerfs than those found in published results obtained with other lasers. Nonetheless, fiber lasers appear to show the same effects as those of CO{sub 2} and ND:YAG lasers. Thus, the main factor that affects the kerf width is the focal position, which means that minimum laser spot diameters are advised for smaller kerf widths.

  6. Study on the applicability of structural and morphological parameters of selected uranium compounds for nuclear forensic purposes

    Energy Technology Data Exchange (ETDEWEB)

    Ho Mer Lin, Doris

    2015-03-13

    Nuclear forensic science or nuclear forensics, is a relatively young discipline which evolved due to the need of analysing interdicted nuclear or radioactive material, necessary for determining its origin. Fundamentally, nuclear forensic science makes use of measurable material properties, referred to as ''signatures'', which provide hints on the history of the material. As part of the advancement in this multi-faceted field, new signatures are constantly sought after and as well as analytical techniques to efficiently and accurately determine the signatures. The work carried out in this study is part of this fulfilment to investigate new structural and morphological parameters as possible new nuclear forensic signatures for selected uranium compounds. The scientific goals have been oriented into three parts for investigations in this study. Firstly, five different compositions of uranium ore concentrates (UOCs) were prepared in the laboratory under well-defined conditions. These materials were subsequently characterized by several techniques such as X-ray diffraction, thermogravimetry/differential thermal analysis, Infrared and Raman spectroscopy, mass spectrometry, scanning electron microscopy etc. Such materials were pivotal for comparison with the industrial samples. Secondly, several uranium compounds, mainly UOCs were measured using Raman spectroscopy. At least three different Raman spectrometers were used and a comparison made in their performance and suitability for nuclear forensics. Raman spectra of industrial uranium materials were interpreted with regard to compound identification and to determination of (anionic) impurities. Anionic impurities that were present were identified and they could provide clues to the processing history of the samples. Statistical techniques such as principal component analysis (PCA) and partial least square-discriminant analysis (PLS-DA) were applied to several Raman spectra. The analysis showed that

  7. A new method of evaluating tight gas sands pore structure from nuclear magnetic resonance (NMR) logs

    Science.gov (United States)

    Xiao, Liang; Mao, Zhi-qiang; Xie, Xiu-hong

    2016-04-01

    Tight gas sands always display such characteristics of ultra-low porosity, permeability, high irreducible water, low resistivity contrast, complicated pore structure and strong heterogeneity, these make that the conventional methods are invalid. Many effective gas bearing formations are considered as dry zones or water saturated layers, and cannot be identified and exploited. To improve tight gas sands evaluation, the best method is quantitative characterizing rock pore structure. The mercury injection capillary pressure (MICP) curves are advantageous in predicting formation pore structure. However, the MICP experimental measurements are limited due to the environment and economy factors, this leads formation pore structure cannot be consecutively evaluated. Nuclear magnetic resonance (NMR) logs are considered to be promising in evaluating rock pore structure. Generally, to consecutively quantitatively evaluate tight gas sands pore structure, the best method is constructing pseudo Pc curves from NMR logs. In this paper, based on the analysis of lab experimental results for 20 core samples, which were drilled from tight gas sandstone reservoirs of Sichuan basin, and simultaneously applied for lab MICP and NMR measurements, the relationships of piecewise power function between nuclear magnetic resonance (NMR) transverse relaxation T2 time and pore-throat radius Rc are established. A novel method, which is used to transform NMR reverse cumulative curve as pseudo capillary pressure (Pc) curve is proposed, and the corresponding model is established based on formation classification. By using this model, formation pseudo Pc curves can be consecutively synthesized. The pore throat radius distribution, and pore structure evaluation parameters, such as the average pore throat radius (Rm), the threshold pressure (Pd), the maximum pore throat radius (Rmax) and so on, can also be precisely extracted. After this method is extended into field applications, several tight gas

  8. Evaluation of severe accident risks: Quantification of major input parameters

    Energy Technology Data Exchange (ETDEWEB)

    Harper, F.T.; Payne, A.C.; Breeding, R.J.; Gorham, E.D.; Brown, T.D.; Rightley, G.S.; Gregory, J.J. (Sandia National Labs., Albuquerque, NM (USA)); Murfin, W. (Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA)); Amos, C.N. (Science Applications International Corp., Albuquerque, NM (USA))

    1991-04-01

    This report records part of the vast amount of information received during the expert judgment elicitation process that took place in support of the NUREG-1150 effort sponsored by the U.S. Nuclear Regulatory Commission. The results of the Containment Loads and Molten Core/Containment Interaction Expert Panel Elicitation are presented in this part of Volume 2 of NUREG/CR-4551. The Containment Loads Expert Panel considered seven issues: (1) hydrogen phenomena at Grand Gulf; (2) hydrogen burn at vessel breach at Sequoyah; (3) BWR reactor building failure due to hydrogen; (4) Grand Gulf containment loads at vessel breach; (5) pressure increment in the Sequoyah containment at vessel breach; (6) loads at vessel breach: Surry; and (7) pressure increment in the Zion containment at vessel breach. The report begins with a brief discussion of the methods used to elicit the information from the experts. The information for each issue is then presented in five sections: (1) a brief definition of the issue, (2) a brief summary of the technical rationale supporting the distributions developed by each of the experts, (3) a brief description of the operations that the project staff performed on the raw elicitation results in order to aggregate the distributions, (4) the aggregated distributions, and (5) the individual expert elicitation summaries. The Molten Core/Containment Interaction Panel considered three issues. The results of the following two of these issues are presented in this document: (1) Peach Bottom drywell shell meltthrough; and (2) Grand Gulf pedestal erosion. 89 figs., 154 tabs.

  9. Nuclear cardiology, Part II: Scintigraphic evaluation of cardiac function.

    Science.gov (United States)

    Hambÿe, A S; Everaert, H; Maes, A; Mesotten, L; Vandevivere, J; Mortelmans, L; Franken, P R

    1998-06-01

    Different methods are currently available to assess cardiac function, especially left ventricular ejection fraction, using either planar or tomographic imaging, first-pass or equilibrium techniques, and blood-pool or myocardial perfusion agents. This is the second article of a four-part series on nuclear cardiology. In this article the authors review the most widely used radiopharmaceuticals and methodologies.

  10. Evaluation of thorium based nuclear fuel. Chemical aspects

    Energy Technology Data Exchange (ETDEWEB)

    Konings, R.J.M.; Blankenvoorde, P.J.A.M.; Cordfunke, E.H.P.; Bakker, K.

    1995-07-01

    This report describes the chemical aspects of a thorium-based fuel cycle. It is part of a series devoted to the study of thorium-based fuel as a means to achieve a considerable reduction of the radiotoxicity of the waste from nuclear power production. Therefore special emphasis is placed on fuel (re-)fabrication and fuel reprocessing in the present work. (orig.).

  11. PARAMETERS OF NUCLEAR MAGNETIC RESONANCE IN PATIENTS WITH CONGENITAL NARROWING OF THE LUMBAR SPINAL CANAL

    Directory of Open Access Journals (Sweden)

    ELIU HAZAEL MORALES-RANGEL

    Full Text Available ABSTRACT Objective: To compare the morphological parameters of magnetic resonance in patients with congenital narrowing of the lumbar spinal canal with patients with low back pain. Methods: A descriptive, retrospective, observational study was conducted with measurements in the axial and sagittal magnetic resonance sections of the vertebral body and canal of the lumbar spine of 64 patients with diagnosis of low back pain, which were compared with resonance images taken from 31 Mexican patients with congenital narrowing of the lumbar spinal canal. Results: The results show that patients with congenital narrowing of the lumbar spinal canal in the axial sections have a difference in diameters, being L2<13.9 mm, L3<13.3 mm, L4<12.9 mm, L5<13.1 mm, compared with controls L2<20.5 mm, L3<20.5 mm, L4<19.3 mm, L5<18.1 mm with p = 0.000. Conclusions: We found different measurements in the Mexican population compared to those found by similar studies. With the parameters obtained, it would be possible to make the proper diagnosis, surgical planning, and treatment.

  12. Anomalous solute transport in saturated porous media: Relating transport model parameters to electrical and nuclear magnetic resonance properties

    Science.gov (United States)

    Swanson, Ryan D; Binley, Andrew; Keating, Kristina; France, Samantha; Osterman, Gordon; Day-Lewis, Frederick D.; Singha, Kamini

    2015-01-01

    The advection-dispersion equation (ADE) fails to describe commonly observed non-Fickian solute transport in saturated porous media, necessitating the use of other models such as the dual-domain mass-transfer (DDMT) model. DDMT model parameters are commonly calibrated via curve fitting, providing little insight into the relation between effective parameters and physical properties of the medium. There is a clear need for material characterization techniques that can provide insight into the geometry and connectedness of pore spaces related to transport model parameters. Here, we consider proton nuclear magnetic resonance (NMR), direct-current (DC) resistivity, and complex conductivity (CC) measurements for this purpose, and assess these methods using glass beads as a control and two different samples of the zeolite clinoptilolite, a material that demonstrates non-Fickian transport due to intragranular porosity. We estimate DDMT parameters via calibration of a transport model to column-scale solute tracer tests, and compare NMR, DC resistivity, CC results, which reveal that grain size alone does not control transport properties and measured geophysical parameters; rather, volume and arrangement of the pore space play important roles. NMR cannot provide estimates of more-mobile and less-mobile pore volumes in the absence of tracer tests because these estimates depend critically on the selection of a material-dependent and flow-dependent cutoff time. Increased electrical connectedness from DC resistivity measurements are associated with greater mobile pore space determined from transport model calibration. CC was hypothesized to be related to length scales of mass transfer, but the CC response is unrelated to DDMT.

  13. Reasons for 2011 Release of the Evaluated Nuclear Data Library (ENDL2011.0)

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Escher, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hoffman, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Luu, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ormand, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Summers, N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-22

    LLNL's Computational Nuclear Physics Group and Nuclear Theory and Modeling Group have collaborated to create the 2011 release of the Evaluated Nuclear Data Library (ENDL2011). ENDL2011 is designed to sup- port LLNL's current and future nuclear data needs. This database is currently the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles, surpassing ENDL2009.0 [1]. The ENDL2011 release [2] contains 918 transport-ready eval- uations in the neutron sub-library alone. ENDL2011 was assembled with strong support from the ASC program, leveraged with support from NNSA science campaigns and the DOE/Offce of Science US Nuclear Data Pro- gram.

  14. 77 FR 6564 - Decision To Evaluate a Petition To Designate a Class of Employees From Nuclear Metals, Inc., West...

    Science.gov (United States)

    2012-02-08

    ... HUMAN SERVICES Decision To Evaluate a Petition To Designate a Class of Employees From Nuclear Metals... to evaluate a petition to designate a class of employees from Nuclear Metals, Inc., West Concord... revision as warranted by the evaluation, is as follows: Facility: Nuclear Metals, Inc. Location: West...

  15. Nuclear Fuel Cycle Options Evaluation to Inform R&D Planning

    Energy Technology Data Exchange (ETDEWEB)

    R. Wigeland; T. Taiwo; M. Todosow; H. Ludewig; W. Halsey; J. Gehin; R. Jubin; J. Buelt; S. Stockinger; K. Jenni; B. Oakley

    2014-04-01

    An Evaluation and Screening (E&S) of nuclear fuel cycle options has been conducted in fulfilment of a Charter specified for the study by the U.S. Department of Energy (DOE) Office of Nuclear Energy. The E&S study used an objective and independently reviewed evaluation process to provide information about the potential benefits and challenges that could strengthen the basis and provide guidance for the research and development(R&D) activities undertaken by the DOE Fuel Cycle Technologies Program Office. Using the nine evaluation criteria specified in the Charter and associated evaluation metrics and processes developed during the E&S study, a screening was conducted of 40 nuclear fuel cycle evaluation groups to provide answers to the questions: (1) Which nuclear fuel cycle system options have the potential for substantial beneficial improvements in nuclear fuel cycle performance, and what aspects of the options make these improvements possible? (2)Which nuclear material management approaches can favorably impact the performance of fuel cycle options? (3)Where would R&D investment be needed to support the set of promising fuel cycle system options and nuclear material management approaches identified above, and what are the technical objectives of associated technologies?

  16. On the use of Bayesian Monte-Carlo in evaluation of nuclear data

    Directory of Open Access Journals (Sweden)

    De Saint Jean Cyrille

    2017-01-01

    Full Text Available As model parameters, necessary ingredients of theoretical models, are not always predicted by theory, a formal mathematical framework associated to the evaluation work is needed to obtain the best set of parameters (resonance parameters, optical models, fission barrier, average width, multigroup cross sections with Bayesian statistical inference by comparing theory to experiment. The formal rule related to this methodology is to estimate the posterior density probability function of a set of parameters by solving an equation of the following type: pdf(posterior ∼ pdf(prior × a likelihood function. A fitting procedure can be seen as an estimation of the posterior density probability of a set of parameters (referred as x→ knowing a prior information on these parameters and a likelihood which gives the probability density function of observing a data set knowing x→. To solve this problem, two major paths could be taken: add approximations and hypothesis and obtain an equation to be solved numerically (minimum of a cost function or Generalized least Square method, referred as GLS or use Monte-Carlo sampling of all prior distributions and estimate the final posterior distribution. Monte Carlo methods are natural solution for Bayesian inference problems. They avoid approximations (existing in traditional adjustment procedure based on chi-square minimization and propose alternative in the choice of probability density distribution for priors and likelihoods. This paper will propose the use of what we are calling Bayesian Monte Carlo (referred as BMC in the rest of the manuscript in the whole energy range from thermal, resonance and continuum range for all nuclear reaction models at these energies. Algorithms will be presented based on Monte-Carlo sampling and Markov chain. The objectives of BMC are to propose a reference calculation for validating the GLS calculations and approximations, to test probability density distributions effects and to

  17. On the use of Bayesian Monte-Carlo in evaluation of nuclear data

    Science.gov (United States)

    De Saint Jean, Cyrille; Archier, Pascal; Privas, Edwin; Noguere, Gilles

    2017-09-01

    As model parameters, necessary ingredients of theoretical models, are not always predicted by theory, a formal mathematical framework associated to the evaluation work is needed to obtain the best set of parameters (resonance parameters, optical models, fission barrier, average width, multigroup cross sections) with Bayesian statistical inference by comparing theory to experiment. The formal rule related to this methodology is to estimate the posterior density probability function of a set of parameters by solving an equation of the following type: pdf(posterior) ˜ pdf(prior) × a likelihood function. A fitting procedure can be seen as an estimation of the posterior density probability of a set of parameters (referred as x→?) knowing a prior information on these parameters and a likelihood which gives the probability density function of observing a data set knowing x→?. To solve this problem, two major paths could be taken: add approximations and hypothesis and obtain an equation to be solved numerically (minimum of a cost function or Generalized least Square method, referred as GLS) or use Monte-Carlo sampling of all prior distributions and estimate the final posterior distribution. Monte Carlo methods are natural solution for Bayesian inference problems. They avoid approximations (existing in traditional adjustment procedure based on chi-square minimization) and propose alternative in the choice of probability density distribution for priors and likelihoods. This paper will propose the use of what we are calling Bayesian Monte Carlo (referred as BMC in the rest of the manuscript) in the whole energy range from thermal, resonance and continuum range for all nuclear reaction models at these energies. Algorithms will be presented based on Monte-Carlo sampling and Markov chain. The objectives of BMC are to propose a reference calculation for validating the GLS calculations and approximations, to test probability density distributions effects and to provide the

  18. An Evaluation of Energy Storage Options for Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, Justin L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bragg-Sitton, Shannon M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Dufek, Eric J. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-06-01

    Energy supply, distribution, and demand are continuing to evolve as new generation sources come online and new appliances are installed. A larger percentage of the United States (U.S.) energy mix is provided by variable energy sources such as wind and solar each year, and distributed generation is becoming more common. In parallel, an evolution in consumer products such as electrical vehicles, information technology devices for residential and industrial applications, and appliances is changing how energy is consumed. As a result of these trends, nuclear power plants (NPPs) are being called upon to operate more flexibly than ever before. Furthermore, advanced nuclear power plants (A-NPPs) might operate as part of an electricity system that looks very different than when the current NPP fleet was constructed. A-NPPs face the possibility that they will need to operate in an environment where flexibility (e.g., fast ramping) is more highly valued than stability (e.g., baseload generation for conventional demand curves). The current fleet of NPPs is struggling to remain economical in competitive markets in an era of historically low natural gas prices and renewable sources with very low marginal costs. These factors, overlaid with an ambiguous national policy related to nuclear energy and a decision-making context that struggles with multi-decade capital investments, raise key questions and present significant challenges to the economics of nuclear power in the evolving grid. Multiple factors could improve the economics of A-NPPs, including: (1) minimizing the need for active safety systems, (2) minimizing adoption of one-off reactor designs, (3) establishing policies that credit low carbon emitting technologies, and (4) integrating energy storage technologies that increase revenue and reduce costs through a combination of ancillary services, market hedging, and reduced costs via stable operation. This report focuses on Item (4), containing an overview, synthesis, and

  19. Instrumentation Requirements for the Engineering Evaluation of Nuclear-Electric Spacecraft

    Science.gov (United States)

    Apel, W. C.

    1961-01-01

    Spacecraft employing nuclear-electric propulsion are being proposed for missions to Venus and distances beyond. These spacecraft utilize a nuclear reactor to provide thermal energy to a turboalternator which generates electric power for an ion motor and the other spacecraft systems. This Report discusses the instrumentation and communications system needed to evaluate a nuclear-electric spacecraft in flight, along with the problems expected. A representative spacecraft design is presented, which leads to a discussion of the instrumentation needed to evaluate such a spacecraft. A basic communications system is considered for transmitting the spacecraft data to Earth. The instrumentation and communications system, as well as all electronic systems on a nuclear-electric spacecraft, will be operating in high temperature and nuclear-radiation environments. The problems caused by these environments are discussed, and possible solutions are offered.

  20. A Methodology for Evaluating System Performance for Radiological/Nuclear Counterterrorism Systems - Full Paper

    Energy Technology Data Exchange (ETDEWEB)

    Bredt, Ofelia P.; Holter, Gregory M.; Wood, Thomas W.

    2005-04-28

    Various countermeasure systems could be deployed against radiological/nuclear terrorism. The need to compare various systems and configurations has resulted in development of a method for estimating performance of such systems. This paper presents one such performance evaluation method.

  1. EVALUATION OF FERMENTATION PARAMETERS DURING HIGH-GRAVITY BEER PRODUCTION

    Directory of Open Access Journals (Sweden)

    R.B. Almeida

    2001-12-01

    Full Text Available A large number of advantages are obtained from the use of highly concentrated worts during the production of beer in a process referred to as "high-gravity". However, problems related to slow or stuck fermentations, which cause the lower productivity and possibility of contamination, are encountered. This study examines the influence of factors pH, percentage of corn syrup, initial wort concentration and fermentation temperature on the fermentation parameters, namely productivity, wort attenuation and the yield coefficient for sugar-to-ethanol conversion. The results show that productivity increased when the higher temperature, the higher wort concentration and the lower syrup percentage were used, while wort attenuation increased when lower wort concentration and no syrup were used. The yield coefficient for sugar-to-ethanol conversion was not influenced by any of the factors studied.

  2. Evaluating System Parameters on a Dragonfly using Simulation and Visualization

    Energy Technology Data Exchange (ETDEWEB)

    Bhatele, Abhinav [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jain, Nikhil [Univ. of Illinois, Urbana-Champaign, IL (United States); Livnat, Yarden [Univ. of Utah, Salt Lake City, UT (United States); Pascucci, Valerio [Univ. of Utah, Salt Lake City, UT (United States); Bremer, Peer-Timo [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Univ. of Utah, Salt Lake City, UT (United States)

    2015-04-24

    The dragon y topology is becoming a popular choice for build- ing high-radix, low-diameter networks with high-bandwidth links. Even with a powerful network, preliminary experi- ments on Edison at NERSC have shown that for communica- tion heavy applications, job interference and thus presumably job placement remains an important factor. In this paper, we explore the e ects of job placement, job sizes, parallel workloads and network con gurations on network through- put to better understand inter-job interference. We use a simulation tool called Damsel y to model the network be- havior of Edison and study the impact of various system parameters on network throughput. Parallel workloads based on ve representative communication patters are used and the simulation studies on up to 131,072 cores are aided by a new visualization of the dragon y network.

  3. Mean nuclear volume

    DEFF Research Database (Denmark)

    Mogensen, O.; Sørensen, Flemming Brandt; Bichel, P.

    1999-01-01

    We evaluated the following nine parameters with respect to their prognostic value in females with endometrial cancer: four stereologic parameters [mean nuclear volume (MNV), nuclear volume fraction, nuclear index and mitotic index], the immunohistochemical expression of cancer antigen (CA125...... (range 5.0-8.4 years). Cox regression analysis (automatic forward selection) showed the MNV to be the most significant prognostic parameter followed by the P-stage. Patients who had localized tumors or tumors with small nuclei had a better probability of surviving than did women with advanced tumors...

  4. Parameters Derived from Integrated Nuclear Fluorescence, Syntactic Structure Analysis, and Vascularization in Human Lung Carcinomas

    Directory of Open Access Journals (Sweden)

    Klaus Kayser

    1997-01-01

    Full Text Available Combined measurements of integrated nuclear fluorescence (INF and vascularization were performed on surgical specimens of human lung carcinomas. Histological slides of formalin‐fixed, paraffin‐embedded tissue samples were treated with Texas Red‐labeled antibody to factor VIII and the fluorochrome DAPI. The resulting images were analyzed with an epi‐illumination fluorescence microscope and two different filter blocks. The first image displayed the vessels, and the second the DAPI‐stained nuclei of surrounding cells. The extent of vascularization was assessed by calculating the volume fraction (Vv, the surface fraction (Sv, the area, and the minimum diameter of the vessels. The INF was measured in tumour cells and lymphocytes, and was grouped according to the distance from the nearest vascular boundary into the intervals of 0–20, 21–40, 41–60, 61–80, and >80 μ. The numerical densities (Nv as well as the percentages of S‐phase‐related tumour cell fraction (SPRF and of tumour cells with an INF > 5C were computed. A minimum of 50 vessels and 300 tumour cells were examined. The material included 100 cases with primary lung carcinoma (39 epidermoid carcinomas, 39 adenocarcinomas, 13 large cell carcinomas, three small cell anaplastic carcinomas, and 6 carcinoid tumours. On the average, the volume density of the stroma amounts to 16.7%, and that of the vessels (Vv to 12.8%. The minimum diameter of the intratumoral vessels is 13 μ and the measured circumference 138 μ. The numerical densities of tumour cells (lymphocytes decrease with increasing distance from the vascular boundary from 6.3 (1.7 to 1.0 (0.1. A reduction is also seen in the percentage of the SPRF from 10.7 to 8.1%. The percentage of tumour cells with an INF > 5C, however, is positively correlated to the distance from the vascular surfaces from 34.2 to 38.2%. The measurements reveal that tumour cells are densely positioned and have an increased proportion of

  5. Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul

    2013-04-30

    The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.

  6. Thermal power evaluation of the TRIGA nuclear reactor at CDTN in operations of long duration

    Energy Technology Data Exchange (ETDEWEB)

    Mesquita, Amir Zacarias; Ferreira, Andrea Vidal; Rezende, Hugo Cesar, E-mail: amir@cdtn.b, E-mail: avf@cdtn.b, E-mail: hcr@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2010-07-01

    The standard operations of nuclear research reactor IPR-R1 TRIGA located at CDTN (Belo Horizonte) usually have duration of not more than 8h. However in 2009 two operations for samples irradiations lasted about 12 hours each at a power of 100 kW. These long lasting operations started in the evening and most of them were carried out at night, when there are only small fluctuations in atmosphere temperature. Therefore the conditions were ideal for evaluating the thermal balance of the power dissipated by the reactor core through the forced cooling system. Heat balance is the standard methodology for power calibration of the IPR-R1 reactor. As in any reactor operation, the main operating parameters were monitored and stored by the Data Acquisition System developed for the reactor. These data have been used for the analysis and calculation of the evolution of several neutronic and thermalhydraulic parameters involved in the reactor operation. This paper analyzes the two long lasting operations of the IPR-R1 TRIGA and compares the recorded results for the power dissipated through the primary cooling loop with the results of the power calibration conducted in March 2009. The results corresponded to those of the thermal power calibration within the uncertainty of this methodology, indicating system stability over a period of six months. (author)

  7. Development of technology for next generation reactor - Research of evaluation technology for nuclear power plant -

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong Kyun; Chang, Moon Heuy; Hwang, Yung Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)] [and others

    1993-09-01

    For development of next generation reactor, a project for evaluation technology for nuclear power plant is performed. Evaluation technology is essential to next generation reactor for reactor safety and system analysis. For design concept, detailed evaluation technologies are studied as follows: evaluation of safety margin, evaluation of safety facilities, evaluation of measurement and control technology; man-machine interface. Especially for thermal efficiency, thermal properties and chemical composition of inconel 690 tube, instead of inconel 600 tube, are measured for steam generator. (Author).

  8. Evaluation of the prompt alerting systems at four nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Towers, D.A.; Anderson, G.S.; Keast, D.N.; Kenoyer, J.L.; Desrosiers, A.E.

    1982-09-01

    This report presents evaluations of the prompt notification siren systems at the following four US nuclear power facilities: Trojan, Three Mile Island, Indian Point, and Zion. The objective of these evaluations was to provide examples of an analytical procedure for predicting siren-system effectiveness under specific conditions in the 10-mile emergency planning zone (EPZ) surrounding nuclear power plants. This analytical procedure is discussed in report No. PNL-4227.

  9. Detecting nuclear materials smuggling: performance evaluation of container inspection policies.

    Science.gov (United States)

    Gaukler, Gary M; Li, Chenhua; Ding, Yu; Chirayath, Sunil S

    2012-03-01

    In recent years, the United States, along with many other countries, has significantly increased its detection and defense mechanisms against terrorist attacks. A potential attack with a nuclear weapon, using nuclear materials smuggled into the country, has been identified as a particularly grave threat. The system for detecting illicit nuclear materials that is currently in place at U.S. ports of entry relies heavily on passive radiation detectors and a risk-scoring approach using the automated targeting system (ATS). In this article we analyze this existing inspection system and demonstrate its performance for several smuggling scenarios. We provide evidence that the current inspection system is inherently incapable of reliably detecting sophisticated smuggling attempts that use small quantities of well-shielded nuclear material. To counter the weaknesses of the current ATS-based inspection system, we propose two new inspection systems: the hardness control system (HCS) and the hybrid inspection system (HYB). The HCS uses radiography information to classify incoming containers based on their cargo content into "hard" or "soft" containers, which then go through different inspection treatment. The HYB combines the radiography information with the intelligence information from the ATS. We compare and contrast the relative performance of these two new inspection systems with the existing ATS-based system. Our studies indicate that the HCS and HYB policies outperform the ATS-based policy for a wide range of realistic smuggling scenarios. We also examine the impact of changes in adversary behavior on the new inspection systems and find that they effectively preclude strategic gaming behavior of the adversary. © 2011 Society for Risk Analysis.

  10. Evaluation of nuclear-reactor-produced iodine-123

    Science.gov (United States)

    Blue, J. W.; Sodd, V. J.

    1976-01-01

    Iodine-123 has such great potential for nuclear medicine that all possible production methods should be considered. In this report, an experimental study related to I-123 production at a high-intensity fast-flux reactor using the reaction Xe-124(n,2n)Xe-123 is considered. The conclusion is that I-123 could be made in small quantities and the cost would be higher than the cyclotron methods presently used.

  11. Flavored whey drinks: preparation and evaluation of selected parameters

    Directory of Open Access Journals (Sweden)

    Alica Bobková

    2016-10-01

    Full Text Available The aim of our work was the preparation of fermented flavored whey beverages using whey, probiotic cultures and suitable flavors. Whey fermentation by lactic acid bacteria appears to be an interesting alternative to improve the properties of whey and thus to offer its exceptional nutritional value, not only because of whey protein contained, but also due to the valuable products produced by microorganisms. Pasteurized whey was enriched by the addition of sheep culture ZS-25, which was isolated from sheep cheese and contains more varieties of species Lactococcus lactis, and also by the probiotic culture containing the microorganisms of Bifidobacterium sp., Lactobacillus acidophilus, Streptococcus thermophilus. We focused our attention to select the appropriate type and concentration of flavor as well. Sensory evaluation was performed by the committee consisting of five intentionally selected professionally qualified persons. Taste of fermented whey drink was main observed property. Assessment of prepared whey drinks was repeated four times, each group consisted of 5 samples according to the following structure: sample A - whey drink with culture without flavoring, sample B - whey drink with culture and exotic flavor, sample C - whey drink with the culture and flavor of cranberry-grape-strawberry, sample D - whey drink with the culture and peach-orange flavor, sample E - whey drink with the culture and strawberry flavor. Flavored fermented whey beverages were sensorially evaluated. The order of individual samples determined by the evaluators was statistically processed by the Friedman test. Table value for this test for five evaluators and 5 samples is 8.99. The calculated values for all four sensory evaluations we performed, were higher than 8.99, so we rejected the null hypothesis and proved that among the different flavored whey drinks it is statistically significant difference. Overall, the worst evaluated was whey drink without flavoring. As

  12. Annual report of nuclear code evaluation committee for fiscal 2000 year

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-03-01

    In this report, research results discussed in fiscal 2000 year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. In 2000, papers mainly on the three topics of (1) present status of burnup credit evaluation methods, (2) issues concerning convergence of criticality calculation and (3) estimation methods for errors associated with criticality calculation based on nuclear data covariance file, are presented and discussed. These results are sorted to grasp the present status of related technology and described in this report. (author)

  13. Co-ordination of the International Network of Nuclear Structure and Decay Data Evaluators

    Energy Technology Data Exchange (ETDEWEB)

    Ricard-McCutchan, E. [Brookhaven National Lab. (BNL), Upton, NY (United States); Dimitriou, P. [Intl Atomic Energy Agency (IAEA), Vienna (Austria); Nichols, A. L. [Univ. of Surrey, Guildford (United Kingdom)

    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.

  14. Evaluation of parameters affecting emitter discharge of some low ...

    African Journals Online (AJOL)

    Four tapes, sold as Chapin, Dream, T-tape, and Typhoon 25, were evaluated. Slopes were varied from 0% to 4%; lateral lengths varied from 5.0m to 20.0m; and water supply heads varied from 0.5m to 2.0m. The results showed that emitter discharges for Chapin were between 0.43 and 0.51 l/hr for 0-2% slopes with standard ...

  15. Performance improvement of artificial neural networks designed for safety key parameters prediction in nuclear research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Mazrou, Hakim [Division de Physique Radiologique, Centre de Recherche Nucleaire d' Alger (CRNA), 02 Boulevard Frantz, Fanon, B.P. 399, 16000 Alger (Algeria)], E-mail: mazrou_h@crna.dz

    2009-10-15

    The present work explores, through a comprehensive sensitivity study, a new methodology to find a suitable artificial neural network architecture which improves its performances capabilities in predicting two significant parameters in safety assessment i.e. the multiplication factor k{sub eff} and the fuel powers peaks P{sub max} of the benchmark 10 MW IAEA LEU core research reactor. The performances under consideration were the improvement of network predictions during the validation process and the speed up of computational time during the training phase. To reach this objective, we took benefit from Neural Network MATLAB Toolbox to carry out a widespread sensitivity study. Consequently, the speed up of several popular algorithms has been assessed during the training process. The comprehensive neural system was subsequently trained on different transfer functions, number of hidden neurons, levels of error and size of generalization corpus. Thus, using a personal computer with data created from preceding work, the final results obtained for the treated benchmark were improved in both network generalization phase and much more in computational time during the training process in comparison to the results obtained previously.

  16. [Evaluation of new technologies PET/CT nuclear imaging].

    Science.gov (United States)

    Giraldes, Maria Rosário

    2010-01-01

    Nuclear imaging has used initially anatomic and volumetric technologies as CT or MRI. In recent years new dimensions of non invasive studies, as PET, have shown a higher utility in the effectiveness of the treatment. The evaluation of need must be done according to a principle of Horizontal Equity, equal treatment for equal need and of a principle of Vertical Equity, Different treatment, at regional level, according to each hospital level. The evaluation of need has been made according to the Potential Demand by Potential User Groups: diabetes, type 2, (50 years and more); screening colorectal (50 years and more); morbidity by cancer; surgery of lung cancer; cardiology; heart surgery; acute chest pain in the emergency department. In a Macro Perspective need has been evaluated using the Population Estimations for 2007, at municipality level. Relatively to Lisbon and Porto data at locality level has been used, from the 2001 Census. According to Campos, J.R. (2007), in 2006, it existed 1 PET by 1 million inhabitants and after that date 2 more were created (Quadrantes and Hospital ad Luz), belonging to the private sector. Mores 15 PET are needed in the NHS, 1 PET for about 504128 inhabitants. According to The Potential Demand perspective 18 new PET are needed, 15 from the public sector. The private sector will cover progressively the demand. Dorado and Albertino (2002), in Spain, mention that the introduction of this new technique in our Health System must be done slowly due to the cost and complexity. In Portugal exists already 6 PET and this applies also. As a first priority the intervention in Oncology in the IPO (Coimbra). A priority must be given to the University Hospitals of Santa Maria and São João. The Central Hospitals of Viseu and VilaReal/Régua must have also 1 PET. A priority must be given to the interior in order to avoid transports of patients and families. In fourth place the HC Central Lisbon must have also 1 PET, which will go to the New Hospital

  17. Impact of intermediate and high energy nuclear data on the neutronic safety parameters of MYRRHA accelerator driven system

    Science.gov (United States)

    Stankovskiy, Alexey; Çelik, Yurdunaz; Eynde, Gert Van den

    2017-09-01

    Perturbation of external neutron source can cause significant local power changes transformed into undesired safety-related events in an accelerator driven system. Therefore for the accurate design of MYRRHA sub-critical core it is important to evaluate the uncertainty of power responses caused by the uncertainties in nuclear reaction models describing the particle transport from primary proton energy down to the evaluated nuclear data table range. The calculations with a set of models resulted in quite low uncertainty on the local power caused by significant perturbation of primary neutron yield from proton interactions with lead and bismuth isotopes. The considered accidental event of prescribed proton beam shape loss causes drastic increase in local power but does not practically change the total core thermal power making this effect difficult to detect. In the same time the results demonstrate a correlation between perturbed local power responses in normal operation and misaligned beam conditions indicating that generation of covariance data for proton and neutron induced neutron multiplicities for lead and bismuth isotopes is needed to obtain reliable uncertainties for local power responses.

  18. Evaluation of ground stiffness parameters using continuous surface wave geophysics

    DEFF Research Database (Denmark)

    Gordon, Anne; Foged, Niels

    2000-01-01

    Present day knowledge of the magnitude of the strain levels in the ground associated with geotechnical structures, together with an increasing number of projects requiring the best estimates of ground movements around excavations, has led to, inter alia, increased interest in measuring the very-small-strain...... stiffness of the ground Gmax. Continuous surface wave geophysics offers a quick, non-intrusive and economical way of making such measurements. This paper reviews the continuous surface wave techniques and evaluates, in engineering terms, the applicability of the method to the site investigation industry....

  19. Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

    Science.gov (United States)

    Lingga, Marwan Mossa

    A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.

  20. System model for evaluation of an emergency response plan for a nuclear power plant based on an assessment of nuclear emergency exercises

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Marcos Vinicius C.; Medeiros, Jose A.C.C. [Universidade Federal do Rio de Janeiro (PEN/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Engenharia Nuclear

    2011-07-01

    Nuclear power plants are designed and built with systems dedicated to provide a high degree of protection to its workers, the population living in their neighborhoods and the environment. Among the requirements for ensuring safety there are the existence of the nuclear emergency plan. Due to the relationship between the actions contemplated in the emergency plan and the nuclear emergency exercise, it becomes possible to assess the quality of the nuclear emergency plan, by means of emergency exercise evaluation, The techniques used in this work aim at improving the evaluation method of a nuclear emergency exercise through the use of performance indicators in the evaluation of the structures, actions and procedures involved. The proposed model enables comparisons between different moments of an emergency plan directed to a nuclear power plant as well as comparisons between plans dedicated to different facilities. (author)

  1. Parameter study of dual-mode space nuclear fission solid core power and propulsion systems, NUROC3A. AMS report No. 1239c

    Energy Technology Data Exchange (ETDEWEB)

    Smith, W.W.; Layton, J.P.

    1976-09-13

    The three-volume report describes a dual-mode nuclear space power and propulsion system concept that employs an advanced solid-core nuclear fission reactor coupled via heat pipes to one of several electric power conversion systems. The NUROC3A systems analysis code was designed to provide the user with performance characteristics of the dual-mode system. Volume 3 describes utilization of the NUROC3A code to produce a detailed parameter study of the system.

  2. Significance of Site-Specific Hydrogeologic Parameters in the Analysis of Radionuclide Transport at New Nuclear Reactor Sites

    Science.gov (United States)

    Tiruneh, N. D.; Nicholson, T. J.; Raione, R.; Ahn, H.; Giacinto, J.; Barnhurst, D.; McBride, M.

    2009-12-01

    The analysis of radionuclide transport at new nuclear reactor sites is currently performed by considering the release of liquid radioactive effluents under three scenarios; accidental release scenarios, normal release scenarios, and inadvertent release scenarios. Accidental release and transport scenarios are analyzed by considering alternate pathways, Conceptual Site Models (CSM), and a postulated accident to determine the highest radionuclide concentration at a receptor location. This is the current compliance requirement with regard to NRC review procedures for assessing public health and safety, and the environment. Bounding analyses are sometimes performed using conservative values for parameters such as coefficient of distribution Kd if site-specific values have not been determined. Uncertainties associated with bounding analyses and generic parameter distributions impacts concentrations and doses to receptors. Assumptions in the bounding analyses need to be tested using site-specific information. These site-specific values provide a realistic analysis option when considering a specified accident. Optimizing the process of, subsurface characterization, data gathering, filtering, quality assurance and quality control is undertaken to analyze the CSM, alternate scenarios and uncertainties. This information is systematically reduced and confirmed to determine the most conservative of all plausible CSMs and understand the features, events and processes significant to radionuclide release and transport.

  3. Evaluation of new multiaxial damage parameters on low carbon steel

    Directory of Open Access Journals (Sweden)

    A. S. Cruces

    2017-07-01

    Full Text Available Most mechanical components are subjected to the complex fatigue loading conditions, where both amplitude and direction of loading cycles change over the time. The estimation of damage caused by these complex loading scenarios are often done by simplified uniaxial fatigue theories, which ultimately leads to higher factor of safety during the final design considerations. Critical plane-based fatigue theories have been considered more accurate for computing the fatigue damage for multiaxial loading conditions in comparison to energy-based and equivalent stress-based theories. Two recently developed fatigue theories have been evaluated in this work for the available test data. Test data includes significant amount of biaxial load paths.

  4. 2011 Release of the Evaluated Nuclear Data Library (ENDL2011.0)

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalles, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Escher, J. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hoffman, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Navratil, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Nobre, G. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ormand, W. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Summers, N. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Vogt, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Barnowski, R. [Univ. of California, Berkeley, CA (United States)

    2015-05-12

    LLNL’s Computational Nuclear Physics Group and Nuclear Theory and Modeling Group have collaborated to produce the last of three major releases of LLNL’s evaluated nuclear database, ENDL2011. ENDL2011 is designed to support LLNL’s current and future nuclear data needs by providing the best nuclear data available to our programmatic customers. This library contains many new evaluations for radiochemical diagnostics, structural materials, and thermonuclear reactions. We have made an effort to eliminate all holes in reaction networks, allowing in-line isotopic creation and depletion calculations. We have striven to keep ENDL2011 at the leading edge of nuclear data library development by reviewing and incorporating new evaluations as they are made available to the nuclear data community. Finally, this release is our most highly tested release as we have strengthened our already rigorous testing regime by adding tests against IPPE Activation Ratio Measurements, many more new critical assemblies and a more complete set of classified testing (to be detailed separately).

  5. Evaluation of the nuclear cross section variance-covariance matrices issued from the nuclear optical model; Evaluation des matrices de variance-covariance des sections efficaces nucleaires issues du modele optique

    Energy Technology Data Exchange (ETDEWEB)

    Brassart, M. [Ecole Nationale Superieure Ingenieurs de Bourges, 18 - Bourges (France); Mounier, C. [CEA Saclay, Dir. de l' Energie Nucleaire DEN, Service d' Etudes des Reacteurs et de Modelisation Avancee, 91 - Gif sur Yvette (France); Dossantos-Uzarralde, P. [CEA Bruyeres le Chatel, 91 (France). Dept. de Physique Theorique et Appliquee

    2004-07-01

    Nuclear reaction models play an important role in today's nuclear data evaluations. There are, however, difficulties associated with evaluating data uncertainties, both while performing the experimental measurements as well as constructing them by nuclear models. In this general context, our interest is particularly targeted towards the study of the propagation uncertainties within nuclear models. In this report we discuss two distinct ways of calculating the nuclear cross section variance-covariance matrices and then show these can be applied to the nuclear spherical optical model. (authors)

  6. Stereological estimates of nuclear volume and other quantitative variables in supratentorial brain tumors. Practical technique and use in prognostic evaluation

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Braendgaard, H; Chistiansen, A O

    1991-01-01

    the practical technique. The continuous variables were correlated with the subjective, qualitative WHO classification of brain tumors, and the prognostic value of the parameters was assessed. Well differentiated astrocytomas (n = 14) had smaller estimates of the volume-weighted mean nuclear volume and mean...... was significantly increased in glioblastomas (2p = 0.01). Three-dimensional, shape-independent estimates of macroscopical tumor volume were not different in anaplastic astrocytomas and glioblastomas (2p = 0.39). Histological type of tumor and mitotic index were of significant prognostic value (2p = 8.2.10(-6) and 2...... techniques in the prognostic evaluation of primary brain tumors....

  7. Generation of CR mammographic image for evaluation quality parameters

    Energy Technology Data Exchange (ETDEWEB)

    Flores, Mabel B.; Mourao, Arnaldo P., E-mail: mbustos@ufmg.br, E-mail: apratabhz@gmail.com [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Centro Federal de Educacao Tecnologica de Minas Gerais (CEFET-MG), Belo Horizonte, MG (Brazil). Centro de Engenharia Politecnica

    2017-11-01

    Currently, among the diseases most feared by women, breast cancer ranks first in the world with an incidence of more than 1.6 million cases and a mortality of more than 521.9 thousand cases by year, which makes this disease the type of cancer with higher incidence and mortality compared to the other types of cancer that mainly affect the female gender, without considering non-melanoma skin cancer. In Brazil, more than 14.4 thousand deaths were registered in 2013 and more than 57 thousand new cases were estimated for 2016. The use of computerized radiography (CR) for the generation of mammographic digital images is widely used in Brazil for the screening of breast cancer. The aim of this investigation is to study the variation of CR plate response to exposure to X-ray beams in a mammography unit. Two CR plates from different manufacturers and a compressed breast phantom containing calcium carbonate structures of different sizes simulating calcifications were used for this study. An X-ray beam generated by 30 kV was selected to realize successive exposures of each plate by performing a time variation of 0.5 to 3.5 s, obtaining the raw images. The acquired images were evaluated with the ImageJ software to determine the saturation time of the plates when exposed to X-ray beams and the qualitative resolution of each plate. The plates were found to saturate at different times when exposed under the same conditions to X-ray beams. By means of the images acquired with the breast phantom, it was possible to observe only structures of calcium carbonate with sizes greater than 177 μm. (author)

  8. Evaluation of Anthropometric and Metabolic Parameters in Obstructive Sleep Apnea

    Directory of Open Access Journals (Sweden)

    Yaşar Yildirim

    2015-01-01

    Full Text Available Aims. Sleep disorders have recently become a significant public health problem worldwide and have deleterious health consequences. Obstructive sleep apnea (OSA is the most common type of sleep-related breathing disorders. We aimed to evaluate anthropometric measurements, glucose metabolism, and cortisol levels in patients with obstructive sleep apnea (OSA. Materials and Methods. A total of 50 patients with a body mass index ≥30 and major OSA symptoms were included in this study. Anthropometric measurements of the patients were recorded and blood samples were drawn for laboratory analysis. A 24-hour urine sample was also collected from each subject for measurement of 24-hour cortisol excretion. Patients were divided equally into 2 groups according to polysomnography results: control group with an apnea-hypopnea index (AHI <5 (n=25 and OSA group with an AHI ≥5 (n=25. Results. Neck and waist circumference, fasting plasma glucose, HbA1c, late-night serum cortisol, morning serum cortisol after 1 mg dexamethasone suppression test, and 24-hour urinary cortisol levels were significantly higher in OSA patients compared to control subjects. Newly diagnosed DM was more frequent in patients with OSA than control subjects (32% versus 8%, p=0.034. There was a significant positive correlation between AHI and neck circumference, glucose, and late-night serum cortisol. Conclusions. Our study indicates that increased waist and neck circumferences constitute a risk for OSA regardless of obesity status. In addition, OSA has adverse effects on endocrine function and glucose metabolism.

  9. Computer program TRACK_TEST for calculating parameters and plotting profiles for etch pits in nuclear track materials

    Science.gov (United States)

    Nikezic, D.; Yu, K. N.

    2006-01-01

    A computer program called TRACK_TEST for calculating parameters (lengths of the major and minor axes) and plotting profiles in nuclear track materials resulted from light-ion irradiation and subsequent chemical etching is described. The programming steps are outlined, including calculations of alpha-particle ranges, determination of the distance along the particle trajectory penetrated by the chemical etchant, calculations of track coordinates, determination of the lengths of the major and minor axes and determination of the contour of the track opening. Descriptions of the program are given, including the built-in V functions for the two commonly employed nuclear track materials commercially known as LR 115 (cellulose nitrate) and CR-39 (poly allyl diglycol carbonate) irradiated by alpha particles. Program summaryTitle of the program:TRACK_TEST Catalogue identifier:ADWT Program obtainable from:CPC Program Library, Queen's University of Belfast, N. Ireland Program summary URL:http://cpc.cs.qub.ac.uk/summaries/ADWT Computer:Pentium PC Operating systems:Windows 95+ Programming language:Fortran 90 Memory required to execute with typical data:256 MB No. of lines in distributed program, including test data, etc.: 2739 No. of bytes in distributed program, including test data, etc.:204 526 Distribution format:tar.gz External subprograms used:The entire code must be linked with the MSFLIB library Nature of problem: Fast heavy charged particles (like alpha particles and other light ions etc.) create latent tracks in some dielectric materials. After chemical etching in aqueous NaOH or KOH solutions, these tracks become visible under an optical microscope. The growth of a track is based on the simultaneous actions of the etchant on undamaged regions (with the bulk etch rate V) and along the particle track (with the track etch rate V). Growth of the track is described satisfactorily by these two parameters ( V and V). Several models have been presented in the past describing

  10. White LED compared with other light sources: age-dependent photobiological effects and parameters for evaluation.

    Science.gov (United States)

    Rebec, Katja Malovrh; Klanjšek-Gunde, Marta; Bizjak, Grega; Kobav, Matej B

    2015-01-01

    Ergonomic science at work and living places should appraise human factors concerning the photobiological effects of lighting. Thorough knowledge on this subject has been gained in the past; however, few attempts have been made to propose suitable evaluation parameters. The blue light hazard and its influence on melatonin secretion in age-dependent observers is considered in this paper and parameters for its evaluation are proposed. New parameters were applied to analyse the effects of white light-emitting diode (LED) light sources and to compare them with the currently applied light sources. The photobiological effects of light sources with the same illuminance but different spectral power distribution were determined for healthy 4-76-year-old observers. The suitability of new parameters is discussed. Correlated colour temperature, the only parameter currently used to assess photobiological effects, is evaluated and compared to new parameters.

  11. Evaluation of Platelet Parameters in Patients With Pulmonary Hydatid Cyst

    Directory of Open Access Journals (Sweden)

    Abdulkadir Küçükbayrak

    2010-02-01

    Full Text Available

    Background: Echinococcosis is a near-cosmopolitan zoonosis caused by adult or larval stages of tapeworms (cestodes into the genus Echinococcus (family Taeniidae. It was demonstrated that platelets were capable of killing parasites independent from leukocytes. Purpose: The aim of our study was to examine mean platelet volume (MPV, platelet mass (PM and platelet count (PC, which are practical indicators of platelet activity in preoperative and postoperative periods of the patients with hydatid cyst.

    Methods: In this retrospective study we evaluated 72 patients admitted to clinic of chest surgery with a diagnosis of pulmonary hydatid cyst in our hospital between January, 2006, and October, 2008. The MPV, PC, and PM were evaluated by complete blood count. PM was calculated by multiplying MPV and PLT.

    Results: Preoperative

  12. Implementing a Nuclear Power Plant Model for Evaluating Load-Following Capability on a Small Grid

    Science.gov (United States)

    Arda, Samet Egemen

    A pressurized water reactor (PWR) nuclear power plant (NPP) model is introduced into Positive Sequence Load Flow (PSLF) software by General Electric in order to evaluate the load-following capability of NPPs. The nuclear steam supply system (NSSS) consists of a reactor core, hot and cold legs, plenums, and a U-tube steam generator. The physical systems listed above are represented by mathematical models utilizing a state variable lumped parameter approach. A steady-state control program for the reactor, and simple turbine and governor models are also developed. Adequacy of the isolated reactor core, the isolated steam generator, and the complete PWR models are tested in Matlab/Simulink and dynamic responses are compared with the test results obtained from the H. B. Robinson NPP. Test results illustrate that the developed models represents the dynamic features of real-physical systems and are capable of predicting responses due to small perturbations of external reactivity and steam valve opening. Subsequently, the NSSS representation is incorporated into PSLF and coupled with built-in excitation system and generator models. Different simulation cases are run when sudden loss of generation occurs in a small power system which includes hydroelectric and natural gas power plants besides the developed PWR NPP. The conclusion is that the NPP can respond to a disturbance in the power system without exceeding any design and safety limits if appropriate operational conditions, such as achieving the NPP turbine control by adjusting the speed of the steam valve, are met. In other words, the NPP can participate in the control of system frequency and improve the overall power system performance.

  13. 2011.2 Revision of the Evaluated Nuclear Data Library (ENDL2011.2)

    Energy Technology Data Exchange (ETDEWEB)

    Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalles, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jurgenson, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-22

    LLNL's Computational Nuclear Physics Group and Nuclear Theory and Modeling Group have col- laborated to create the 2011.2 revised release of the Evaluated Nuclear Data Library (ENDL2011.2). ENDL2011.2 is designed to support LLNL's current and future nuclear data needs and will be em- ployed in nuclear reactor, nuclear security and stockpile stewardship simulations with ASC codes. This database is currently the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles. This library was assembled with strong support from the ASC PEM and Attribution programs, leveraged with support from Campaign 4 and the DOE/O ce of Science's US Nuclear Data Program. This document lists the revisions made in ENDL2011.2 compared with the data existing in the original ENDL2011.0 release and the ENDL2011.1-rc4 re- lease candidate of April 2015. These changes are made in parallel with some similar revisions for ENDL2009.2.

  14. Evaluation of High Energy Nuclear Data of Importance for Use in Accelerator and Space Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Ouk

    2005-10-15

    New evaluation were performed for neutron- and proton-induced reactions for energies up to 250 400 MeV on C-12, N-14, O-16, Al-27, Si-28, Ca-40, Ar-40, Fe-54,58, Ni-64, Cu-63,65, Zr-90, Pb-208, Th-232, U-233,234,236, and Cm-243246. The evaluated results are then applied to the accelerator and space technology. A set of optical model parameters were optimized by searching a number of adjustable coefficients with the Simulated Annealing(SA) method for the spherical nuclei. A parameterization of the empirical formula was proposed to describe the proton-nucleus non-elastic cross sections of high-priority elements for space shielding purpose for proton energies from reaction threshold up to 400 MeV, which was then implemented into the fast scoping space shielding code CHARGE, based on the results of the optical model analysis utilizing up-to-date measurements. For proton energies up to 400 MeV covering most of the incident spectrum for trapped protons and solar energetic particle events, energy-angle spectra of secondary neutrons produced from the proton-induced neutron production reaction were prepared. The evaluated cross section set was applied to the thick target yield (TTY) and promp radiation benchmarks for the accelerator shielding. As for the assessment of the radiological impact of the accelerator to the environment, relevant nuclear reaction cross sections for the activation of the air were recommended among the author's evaluations and existing library based on the available measurements.

  15. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Hoopingarner, K.R.; Vause, J.W.

    1987-08-01

    Pacific Northwest Laboratory (PNL) evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume II, reports the results of an industry-wide workshop held on May 28 and 29, 1986, to discuss the technical issues associated with aging of nuclear service emergency diesel generators. The technical issues discussed most extensively were: man/machine interfaces, component interfaces, thermal gradients of startup and cooldown and the need for an accurate industry database for trend analysis of the diesel generator system.

  16. Development of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2004-02-15

    The objective of this research is to develop on efficient integrity evaluation technology and to investigate the applicability of the newly-developed technology such as internet-based cyber platform etc. to Nuclear Power Plant(NPP) components. The development of an efficient structural integrity evaluation system is necessary for safe operation of NPP as the increase of operating periods. Moreover, material test data as well as emerging structural integrity assessment technology are also needed for the evaluation of aged components. The following five topics are covered in this project: development of the wall-thinning evaluation program for nuclear piping; development of structural integrity evaluation criteria for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for major components of NPP; ingegration of internet-based cyber platform and integrity evaluation program for primary components of NPP; effects of aging on strength of dissimilar welds.

  17. Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Abbott, L [ed.

    1985-09-01

    An evaluation of the risk to the Calvert Cliffs Unit 1 nuclear power plant due to pressurized thermal shock (PTS) has been completed by Oak Ridge National Laboratory (ORNL) with the assistance of several other organizations. This evaluation was part of a Nuclear Regulatory Commission program designed to study the PTS risk to three nuclear plants, the other two plants being Oconee Unit 1 and H.B. Robinson Unit 2. The specific objectives of the program were to (1) provide a best estimate of the frequency of a through-the-wall crack in the pressure vessel at each of the three plants, together with the uncertainty in the estimated frequency and its sensitivity to the variables used in the evaluation; (2) determine the dominant overcooling sequences contributing to the estimated frequency and the associated failures in the plant systems or in operator actions; and (3) evaluate the effectiveness of potential corrective measures.

  18. Cross-checking of Large Evaluated and Experimental Nuclear Reaction Databases

    Energy Technology Data Exchange (ETDEWEB)

    Zeydina, O. [Société de Calcul Mathématique, Paris (France); Koning, A.J. [Nuclear Research and Consultancy Group, Petten (Netherlands); Soppera, N. [OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux (France); Raffanel, D. [Société de Calcul Mathématique, Paris (France); Bossant, M. [OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux (France); Dupont, E., E-mail: data@oecd-nea.org [OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux (France); Beauzamy, B. [Société de Calcul Mathématique, Paris (France)

    2014-06-15

    Automated methods are presented for the verification of large experimental and evaluated nuclear reaction databases (e.g. EXFOR, JEFF, TENDL). These methods allow an assessment of the overall consistency of the data and detect aberrant values in both evaluated and experimental databases.

  19. Cross-checking of Large Evaluated and Experimental Nuclear Reaction Databases

    Science.gov (United States)

    Zeydina, O.; Koning, A. J.; Soppera, N.; Raffanel, D.; Bossant, M.; Dupont, E.; Beauzamy, B.

    2014-06-01

    Automated methods are presented for the verification of large experimental and evaluated nuclear reaction databases (e.g. EXFOR, JEFF, TENDL). These methods allow an assessment of the overall consistency of the data and detect aberrant values in both evaluated and experimental databases.

  20. Review of recent benchmark experiments on integral test for high energy nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Nakashima, Hiroshi; Tanaka, Susumu; Konno, Chikara; Fukahori, Tokio; Hayashi, Katsumi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-11-01

    A survey work of recent benchmark experiments on an integral test for high energy nuclear data evaluation was carried out as one of the work of the Task Force on JENDL High Energy File Integral Evaluation (JHEFIE). In this paper the results are compiled and the status of recent benchmark experiments is described. (author)

  1. Developments of integrity evaluation technology for pressurized components in nuclear power plant and IT based integrity evaluation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Choi, Jae Boong; Shim, Do Jun [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2003-03-15

    The objective of this research is to develop an efficient evaluation technology and to investigate applicability of newly-developed technology, such as internet-based cyber platform, to operating power plants. Development of efficient evaluation systems for Nuclear Power Plant components, based on structural integrity assessment techniques, are increasingly demanded for safe operation with the increasing operating period of Nuclear Power Plants. The following five topics are covered in this project: development of assessment method for wall-thinned nuclear piping based on pipe test; development of structural integrity program for steam generator tubes with cracks of various shape; development of fatigue life evaluation system for mam components of NPP; development of internet-based cyber platform and integrity program for primary components of NPP; effect of aging on strength of dissimilar welds.

  2. Effects of the Chernobyl and Fukushima nuclear accidents on atmospheric electricity parameters recorded at Polish observation stations

    Science.gov (United States)

    Kubicki, Marek; Baranski, Piotr; Odzimek, Anna; Michnowski, Stanislaw; Myslek-Laurikainen, Bogna

    2013-04-01

    We analyse the atmospheric electricity parameters, measured at Polish geophysical stations in Swider, Poland, and Hornsund, Spitsbergen, in connection with the radioactive incident in Fukushima, Japan, beginning on 11 March 2011, following the 9.0 earthquake and tsunami. We compare our results with the situation during and after the Chernobyl disaster on April 26, 1986, when the radioactive fallout detected at Swider increased in the last week of April 1986, from 4.111 to 238.7 Bq/m2 and up to 967.0 Bq/m2 in the second week of May 1986 - what was more than 235 times greater than the values measured prior to that accident. Besides the electric field especially the electric conductivity is very sensitive to the radioactive contamination of the air. Thus we postulate that these two measurements should be run at geophysical stations over the world and used as a relatively simple and low-cost tool for continuous monitoring of possible hazard caused by nuclear power plant accidents.

  3. Nuclear magnetic resonance T 2 spectrum: multifractal characteristics and pore structure evaluation

    Science.gov (United States)

    Yan, Jian-Ping; He, Xu; Geng, Bin; Hu, Qin-Hong; Feng, Chun-Zhen; Kou, Xiao-Pan; Li, Xing-Wen

    2017-06-01

    Pore structure characteristics are important to oil and gas exploration in complex low-permeability reservoirs. Using multifractal theory and nuclear magnetic resonance (NMR), we studied the pore structure of low-permeability sandstone rocks from the 4th Member (ES4) of the Shahejie Formation in the south slope of the Dongying Sag. We used the existing pore structure data from petrophysics, core slices, and mercury injection tests to classify the pore structure into three categories and five subcategories. Then, the T 2 spectra of samples with different pore structures were interpolated, and the one- and three-dimensional fractal dimensions and the multifractal spectrum were obtained. Parameters α (intensity of singularity) and f (α) (density of distribution) were extracted from the multifractal spectra. The differences in the three fractal dimensions suggest that the pore structure types correlate with α and f (α). The results calculated based on the multifractal spectrum is consistent with that of the core slices and mercury injection. Finally, the proposed method was applied to an actual logging profile to evaluate the pore structure of low-permeability sandstone reservoirs.

  4. 2009.3 Revision of the Evaluated Nuclear Data Library (ENDL2009.3)

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, I. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalle, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jurgenson, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-11-06

    LLNL's Computational Nuclear Data and Theory Group have created a 2009.3 revised release of the Evaluated Nuclear Data Library (ENDL2009.3). This library is designed to support LLNL's current and future nuclear data needs and will be employed in nuclear reactor, nuclear security and stockpile stewardship simulations with ASC codes. The ENDL2009 database was the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles. It was assembled with strong support from the ASC PEM and Attribution programs, leveraged with support from Campaign 4 and the DOE/Office of Science's US Nuclear Data Program. This document lists the revisions and fixes made in a new release called ENDL2009.3, by com- paring with the existing data in the previous release ENDL2009.2. These changes are made in conjunction with the revisions for ENDL2011.3, so that both the .3 releases are as free as possible of known defects.

  5. 2009.1 Revision of the Evaluated Nuclear Data Library (ENDL2009.1)

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, I. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalles, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Summers, N. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-05-11

    LLNL’s Computational Nuclear Data and Theory Group have created a 2009.1 revised release of the Evaluated Nuclear Data Library (ENDL2009.1). This library is designed to support LLNL’s current and future nuclear data needs and will be employed in nuclear reactor, nuclear security and stockpile stewardship simulations with ASC codes. The ENDL2009 database was the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles. It was assembled with strong support from the ASC PEM and Attribution programs, leveraged with support from Campaign 4 and the DOE/Office of Science’s US Nuclear Data Program. This document lists the revisions and fixes made in a new release called ENDL2009.1, by comparing with the existing data in the original release which is now called ENDL2009.0. These changes are made in conjunction with the revisions for ENDL2011.1, so that both the .1 releases are as free as possible of known defects.

  6. Evaluating safety-critical organizations - emphasis on the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, Teemu; Oedewald, Pia (VTT, Technical Research Centre of Finland (Finland))

    2009-04-15

    An organizational evaluation plays a key role in the monitoring, as well as controlling and steering, of the organizational safety culture. If left unattended, organizations have a tendency to gradually drift into a condition where they have trouble identifying their vulnerabilities and mechanisms or practices that create or maintain these vulnerabilities. The aim of an organizational evaluation should be to promote increased understanding of the sociotechnical system and its changing vulnerabilities. Evaluation contributes to organizational development and management. Evaluations are used in various situations, but when the aim is to learn about possible new vulnerabilities, identify organizational reasons for problems, or prepare for future challenges, the organization is most open to genuine surprises and new findings. It is recommended that organizational evaluations should be conducted when - there are changes in the organizational structures - new tools are implemented - when the people report increased workplace stress or a decreased working climate - when incidents and near-misses increase - when work starts to become routine - when weak signals (such as employees voicing safety concerns or other worries, the organization 'feels' different, organizational climate has changed) are perceived. In organizations that already have a high safety level, safety managers work for their successors. This means that they seldom see the results of their successful efforts to improve safety. This is due to the fact that it takes time for the improvement to become noticeable in terms of increased measurable safety levels. The most challenging issue in an organizational evaluation is the definition of criteria for safety. We have adopted a system safety perspective and we state that an organization has a high potential for safety when - safety is genuinely valued and the members of the organization are motivated to put effort on achieving high levels of safety

  7. The CCONE Code System and its Application to Nuclear Data Evaluation for Fission and Other Reactions

    Science.gov (United States)

    Iwamoto, O.; Iwamoto, N.; Kunieda, S.; Minato, F.; Shibata, K.

    2016-01-01

    A computer code system, CCONE, was developed for nuclear data evaluation within the JENDL project. The CCONE code system integrates various nuclear reaction models needed to describe nucleon, light charged nuclei up to alpha-particle and photon induced reactions. The code is written in the C++ programming language using an object-oriented technology. At first, it was applied to neutron-induced reaction data on actinides, which were compiled into JENDL Actinide File 2008 and JENDL-4.0. It has been extensively used in various nuclear data evaluations for both actinide and non-actinide nuclei. The CCONE code has been upgraded to nuclear data evaluation at higher incident energies for neutron-, proton-, and photon-induced reactions. It was also used for estimating β-delayed neutron emission. This paper describes the CCONE code system indicating the concept and design of coding and inputs. Details of the formulation for modelings of the direct, pre-equilibrium and compound reactions are presented. Applications to the nuclear data evaluations such as neutron-induced reactions on actinides and medium-heavy nuclei, high-energy nucleon-induced reactions, photonuclear reaction and β-delayed neutron emission are mentioned.

  8. Significance of combined nutritional and morphological precaecal parameters for feed evaluations in non-ruminants

    NARCIS (Netherlands)

    Leeuwen, van P.

    2002-01-01

    In this thesis the hypothesis is tested that the nutritional evaluation of dietary formulations in non-ruminants requires both functional-nutritional and functional-morphological parameters. The functional-nutritional parameters provide data on the outcome of the

  9. Semen parameters evaluation in men with normal sperm concentration and polyzoospermic men

    Directory of Open Access Journals (Sweden)

    S. Sh. Khayat

    2014-12-01

    Full Text Available We analyzed 10 178 semen samples from men in infertile couples within a retrospective clinical study (2007–2012. Basic semen parameters at different sperm concentrations were evaluated, immature germ cells in polyzoospermic men were estimated.

  10. BUILDING MODEL ANALYSIS APPLICATIONS WITH THE JOINT UNIVERSAL PARAMETER IDENTIFICATION AND EVALUATION OF RELIABILITY (JUPITER) API

    Science.gov (United States)

    The open-source, public domain JUPITER (Joint Universal Parameter IdenTification and Evaluation of Reliability) API (Application Programming Interface) provides conventions and Fortran-90 modules to develop applications (computer programs) for analyzing process models. The input ...

  11. Evaluation of the analysis models in the ASTRA nuclear design code system

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Nam Jin; Park, Chang Jea; Kim, Do Sam; Lee, Kyeong Taek; Kim, Jong Woon [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2000-11-15

    In the field of nuclear reactor design, main practice was the application of the improved design code systems. During the process, a lot of basis and knowledge were accumulated in processing input data, nuclear fuel reload design, production and analysis of design data, et al. However less efforts were done in the analysis of the methodology and in the development or improvement of those code systems. Recently, KEPO Nuclear Fuel Company (KNFC) developed the ASTRA (Advanced Static and Transient Reactor Analyzer) code system for the purpose of nuclear reactor design and analysis. In the code system, two group constants were generated from the CASMO-3 code system. The objective of this research is to analyze the analysis models used in the ASTRA/CASMO-3 code system. This evaluation requires indepth comprehension of the models, which is important so much as the development of the code system itself. Currently, most of the code systems used in domestic Nuclear Power Plant were imported, so it is very difficult to maintain and treat the change of the situation in the system. Therefore, the evaluation of analysis models in the ASTRA nuclear reactor design code system in very important.

  12. Ergonomics in the licensing and evaluation of nuclear reactors control room; A ergonomia no licenciamento e na avaliacao de salas de controle de reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Isaac Jose Antonio Luquetti dos [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Vidal, Mario Cesar Rodriguez [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia de Producao

    2002-07-01

    A nuclear control room is a complex system that controls a thermodynamic process used to produce electrical energy. The operators interact with the control room through interfaces that have significant implications to nuclear plant safety and influence the operator activity. The TMI (Three Mile Island) accident demonstrated that only the anthropometric aspects were not enough for an adequate nuclear control room design. The studies showed that the accident was aggravated because the designers had not considered adequately human factor aspects. After TMI accident, the designers introduce in the nuclear control room development only human factors standards and human factors guidelines. The ergonomics approaches was not considered. Our objective is introduce in nuclear control room design and nuclear control room evaluation, a methodology that. includes human factors standards, human factors guidelines and ergonomic approaches, the operator activity analysis. (author)

  13. Synthesis and evaluation of potential ligands for nuclear waste processing

    NARCIS (Netherlands)

    Iqbal, M.

    2012-01-01

    The research presented in this thesis deals with the synthesis and evaluation of new potential ligands for the complexation of actinide and lanthanide ions either for their extraction from bulk radioactive waste or their stripping from an extracted organic phase for final processing of the waste. In

  14. Evaluation of nuclear reaction cross section of some isotopes of ...

    African Journals Online (AJOL)

    Coupled-channels optical model code OPTMAN is used as an alternative to experimental approach to evaluate the total reaction cross section for four different isotopes of Plutonium as an example of heavy rotational nuclei of the transuranium elements over an energy range of 10 to 20 MeV. The selected isotopes are the ...

  15. Sustainable Forward Operating Base Nuclear Power Evaluation (Relationship Mapping System) Users’ Manual

    Energy Technology Data Exchange (ETDEWEB)

    Not Listed

    2012-01-01

    The Sustainable Forward Operating Base (FOB) Nuclear Power Evaluation was developed by the Idaho National Laboratory Systems Engineering Department to support the Defense Advanced Research Projects Agency (DARPA) in assessing and demonstrating the viability of deploying small-scale reactors in support of military operations in theatre. This document provides a brief explanation of how to access and use the Sustainable FOB Nuclear Power Evaluation utility to view assessment results as input into developing and integrating the program elements needed to create a successful demonstration.

  16. Evaluation of fatigue damage in nuclear power plants: evolution and new tools of analysis; Evaluacion del dano a fatiga en centrales nucleares: evolucion y nuevas herramientas de analisis

    Energy Technology Data Exchange (ETDEWEB)

    Cicero, R.; Corchon, F.

    2011-07-01

    This paper presents new fatigue mechanisms requiring analysis, tools developed for evaluation and the latest trends and studies that are currently working in the nuclear field, and allow proper management referring facilities the said degradation mechanism.

  17. Preclinical evaluation of nuclear morphometry and tissue topology for breast carcinoma detection and margin assessment.

    Science.gov (United States)

    Nyirenda, Ndeke; Farkas, Daniel L; Ramanujan, V Krishnan

    2011-04-01

    Prevention and early detection of breast cancer are the major prophylactic measures taken to reduce the breast cancer related mortality and morbidity. Clinical management of breast cancer largely relies on the efficacy of the breast-conserving surgeries and the subsequent radiation therapy. A key problem that limits the success of these surgeries is the lack of accurate, real-time knowledge about the positive tumor margins in the surgically excised tumors in the operating room. This leads to tumor recurrence and, hence, the need for repeated surgeries. Current intraoperative techniques such as frozen section pathology or touch imprint cytology severely suffer from poor sampling and non-optimal detection sensitivity. Even though histopathology analysis can provide information on positive tumor margins post-operatively (~2-3 days), this information is of no immediate utility in the operating rooms. In this article, we propose a novel image analysis method for tumor margin assessment based on nuclear morphometry and tissue topology and demonstrate its high sensitivity/specificity in preclinical animal model of breast carcinoma. The method relies on imaging nuclear-specific fluorescence in the excised surgical specimen and on extracting nuclear morphometric parameters (size, number, and area fraction) from the spatial distribution of the observed fluorescence in the tissue. We also report the utility of tissue topology in tumor margin assessment by measuring the fractal dimension in the same set of images. By a systematic analysis of multiple breast tissues specimens, we show here that the proposed method is not only accurate (~97% sensitivity and 96% specificity) in thin sections, but also in three-dimensional (3D) thick tissues that mimic the realistic lumpectomy specimens. Our data clearly precludes the utility of nuclear size as a reliable diagnostic criterion for tumor margin assessment. On the other hand, nuclear area fraction addresses this issue very

  18. Cyber security risk evaluation of a nuclear I and C using BN and ET

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jin Soo; Heo, Gyun Young [Dept. of Nuclear Engineering, Kyung Hee University, Yongin (Korea, Republic of); Son, Han Seong [Computer and Game Science, Joongbu University, Geumsan (Korea, Republic of)

    2017-04-15

    Cyber security is an important issue in the field of nuclear engineering because nuclear facilities use digital equipment and digital systems that can lead to serious hazards in the event of an accident. Regulatory agencies worldwide have announced guidelines for cyber security related to nuclear issues, including U.S. NRC Regulatory Guide 5.71. It is important to evaluate cyber security risk in accordance with these regulatory guides. In this study, we propose a cyber security risk evaluation model for nuclear instrumentation and control systems using a Bayesian network and event trees. As it is difficult to perform penetration tests on the systems, the evaluation model can inform research on cyber threats to cyber security systems for nuclear facilities through the use of prior and posterior information and backpropagation calculations. Furthermore, we suggest a methodology for the application of analytical results from the Bayesian network model to an event tree model, which is a probabilistic safety assessment method. The proposed method will provide insight into safety and cyber security risks.

  19. Cyber Security Risk Evaluation of a Nuclear I&C Using BN and ET

    Directory of Open Access Journals (Sweden)

    Jinsoo Shin

    2017-04-01

    Full Text Available Cyber security is an important issue in the field of nuclear engineering because nuclear facilities use digital equipment and digital systems that can lead to serious hazards in the event of an accident. Regulatory agencies worldwide have announced guidelines for cyber security related to nuclear issues, including U.S. NRC Regulatory Guide 5.71. It is important to evaluate cyber security risk in accordance with these regulatory guides. In this study, we propose a cyber security risk evaluation model for nuclear instrumentation and control systems using a Bayesian network and event trees. As it is difficult to perform penetration tests on the systems, the evaluation model can inform research on cyber threats to cyber security systems for nuclear facilities through the use of prior and posterior information and backpropagation calculations. Furthermore, we suggest a methodology for the application of analytical results from the Bayesian network model to an event tree model, which is a probabilistic safety assessment method. The proposed method will provide insight into safety and cyber security risks.

  20. A Study on the Measurement of Ultrasound Velocity to Evaluate Degradation of Low Voltage Cables for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyung Cho; Kang, Suk Chull; Goo, Cheol Soo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Kim, Jin Ho; Park, Jae Seok; Joo, Geum Jong; Park, Chi Seung [KAITEC, Seoul (Korea, Republic of)

    2004-08-15

    Several kinds of low voltage cables have been used in nuclear power plants for the supply of electric power, supervision, and the propagation of control signals. These low voltage tables must be inspected for safe and stable operation of nuclear power plants. In particular, the degradation diagnosis to estimate the integrity of low voltage rabies has recently been emphasized according to the long use of nuclear power plants. In order to evaluate their degradation, the surrounding temperature, hardness of insulation material, elongation at breaking point (EAB), etc. have been used. However, the measurement of temperature or hardness is not useful because of the absence of quantitative criteria; the inspection of a sample requires turning off of the power plant power; and, the electrical inspection method is not sufficiently sensitive from the initial through the middle stage of degradation. In this research, based on the theory that the ultrasonic velocity changes with relation to the degradation of the material, we measured the ultrasonic velocity as low voltage cables were degraded. To this end, an ultrasonic degradation diagnosis device was developed and used to measure the ultrasonic velocity with the clothing on the cable, and it was confirmed that the ultrasonic velocity changes according to the degradation of low voltage cables. The low voltage cables used in nuclear power plants were degraded at an accelerated rate, and EAB was measured in a tensile test conducted after the measurement of ultrasonic velocity. With the increasing degradation degree, the ultrasonic velocity decreased, whose potential as a useful parameter for the quantitative degradation evaluation was thus confirmed

  1. Summary Report of a Specialized Workshop on Nuclear Structure and Decay Data (NSDD) Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, Alan L. [Univ. of Surrey, Guildford (United Kingdom); Dimitrious, P. [IAEA Nuclear Data Section, Vienna (Austria); Kondev, F. G. [Argonne National Lab. (ANL), Argonne, IL (United States); Ricard-McCutchan, E. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-04-27

    A three-day specialised workshop on Nuclear Structure and Decay Data Evaluations was organised and held at the headquarters of the International Atomic Energy Agency in Vienna, Austria, from 27 to 29 April 2015. This workshop covered a wide range of important topics and issues addressed when evaluating and maintaining the Evaluated Nuclear Structure Data File (ENSDF). The primary aim was to improve evaluators’ abilities to identify and understand the most appropriate evaluation processes to adopt in the formulation of individual ENSDF data sets. Participants assessed and reviewed existing policies, procedures and codes, and round-table discussions included the debate and resolution of specific difficulties experienced by ENSDF evaluators (i.e., all workshop participants). The contents of this report constitute a record of this workshop, based on the presentations and subsequent discussions.

  2. Summary documentation of LASL nuclear data evaluations for ENDF/B-V

    Energy Technology Data Exchange (ETDEWEB)

    Young, P.G. (comp.)

    1979-01-01

    Summaries are presented of nuclear data evaluations performed at Los Alamos Scientific Laboratory (LASL) that will comprise part of Version V of the Evaluated Nuclear Data File, ENDF/B. A total of 18 general purpose evaluations of neutron-induced data are summarized, together with 6 summaries directed specifically at covariance data evaluations. The general purpose evaluation summaries cover the following isotopes: /sup 1 -3/H, /sup 3/ /sup 4/He, /sup 6/ /sup 7/Li, /sup 10/B, /sup 14/ /sup 15/N, /sup 16/O, /sup 27/Al, /sup 182/ /sup 183/ /sup 184/ /sup 186/W, /sup 233/U, and /sup 242/Pu. The covariance data summaries are given for /sup 1/H, /sup 6/Li, /sup 10/B, /sup 14/N, /sup 16/O, and /sup 27/Al. 28 figures.

  3. Introduction of Integrity Evaluation Criteria Developing during and after fire for Nuclear Power Plant Buildings

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jin Woo [KEPCo, Gimcheon (Korea, Republic of)

    2016-05-15

    The first project for nuclear power plant built in Korea to taking account the engineering based approach was started on October 2015 including the whole process such as fire hazard analysis, standard fire modeling, cable tray fire with multi spurious operation, structural fire integrity evaluation, and large area fire induced air craft crash. This paper covers the brief developing scheme and roadmap focusing on structural fire evaluation criteria. The meaningful first step for developing the structural fire integrity in nuclear power plant building is started with the series of fire related sub sections mentioned in earlier section. The recognition and sufficient effort of fire research leads to set up the safe and reliable design of nuclear power plant.

  4. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study

    Energy Technology Data Exchange (ETDEWEB)

    Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

    1987-08-01

    Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators.

  5. Development of the advanced nuclear materials -Materials performance evaluation-

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woo Chul; Noh, Kye Hoh; Han, Jung Hoh; Jung, Han Sub; Kim, Hong Pyo; Lee, Duk Hyun; Lee, Eun Heui; Hwang, Sung Sik; Huh, Doh Haeng [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    The software for ACPD was modified to use multi-specimens and multi-frequency. The stress corrosion cracking resistance test of Alloy 600 in Pb contained water was performed by slow strain rate tester. The corrosion fatigue test machine was installed, and an autoclave for this test was purchased. The fatigue test was conducted in air. The stability for the long term test in DCPD was evaluated, and the improvement of current source and the revision of potential drop difference according to temperature variation increased the detection accuracy. A Ag/AgCl reference electrode and electrode support were assembled and the performance test was carried out at high temperature under high pressure. The zirconia pH electrode was assembled. The specimens with SUS304, Zr-2.5Nb were machined for irradiation assisted degradation test. The erosion/corrosion for the selected secondary side piping of Kori-1 was evaluated by CHECKMATE code. The chemical analysis and metallurgical inspection of the secondary piping of Kori-1 were conducted, and the erosion/corrosion test loop was made. 29 figs, 12 tabs, 11 refs. (Author).

  6. Evolution of a visual impact model to evaluate nuclear plant siting and design option

    Science.gov (United States)

    Brian A. Gray; John Ady; Grant R. Jones

    1979-01-01

    The development of a visual impact method- elegy is reviewed from first concepts (1973) to application.3/ The method can be used to train evaluators to use explicit criteria (vividness, intactness and unity) to assess change in a setting's visual quality as the result of construction of a nuclear facility, or any other visible alteration. Slides of "before...

  7. Proceedings of the 1st conference on nuclear structure data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Firestone, R.B.; Shirley, V.S.; Dairiki, J.M. (eds.)

    1982-04-01

    The 1st Conference on Nuclear Structure Data Evaluation was organized by the Isotopes Project of the Lawrence Berkeley Laboratory in order to encourage the open discussion of the scientific aspects of ENSDF production and usage. Summaries of the roundtable discussion sessions, abstracts of the presented papers, and additional contributed papers are contained in these Proceedings.

  8. Installation and evaluation of a nuclear power plant operator advisor based on artificial intelligence technology

    Energy Technology Data Exchange (ETDEWEB)

    Hajek, B.K.; Miller, D.W.

    1989-06-20

    This report discusses the following topics on a Nuclear Power Plant operator advisor based on artificial Intelligence Technology; Workstation conversion; Software Conversion; V V Program Development Development; Simulator Interface Development; Knowledge Base Expansion; Dynamic Testing; Database Conversion; Installation at the Perry Simulator; Evaluation of Operator Interaction; Design of Man-Machine Interface; and Design of Maintenance Facility.

  9. Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This Department of Energy (DOE) is approved for use by all components of DOE. It contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE Non-Reactor Nuclear Facilities. Adherence with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs.

  10. Improvement of the Nuclear Radiation Protection Training for the Simulator and on sharing method of the Safety Parameter with the Emergency Organization

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Sungjin; Park, Daeseung [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Radiation Emergency alert will be announced when the radiological impact is limited within the NPP or radiological impact to go out of the NPP. Radiation Protection Training is scheduled and proceeded to prevent for the radiation accidents, possibility of the radiation accidents, or radiation accident expansion, the training is to reduce the damage to property and health for the nuclear power plant worker and the people near the nuclear power plant. This paper shows the improvement of the nuclear radiation protection training for the simulator and on sharing method of the safety parameter with the emergency organization. Accident shall be correctly and quickly prevented when the NPP accident is inevitable. Therefore the radiation protection training for the operator and the emergency organization will be effective when the accident happens if the simulator has the same environment as the NPP.

  11. Evaluation of eutrophication of Ostravice river depending on the chemical and physical parameters

    Science.gov (United States)

    Hlavac, A.; Melcakova, I.; Novakova, J.; Svehlakova, H.; Slavikova, L.; Klimsa, L.; Bartkova, M.

    2017-10-01

    The main objective of this study was to evaluate which selected environmental parameters in rivers affect the concentration of chlorophyll a and the distribution of macrozoobenthos. The data were collected on selected profiles of the Ostravice mountain river in the Moravian-Silesian Region. The examined chemical and physical parameters include dissolved oxygen (DO), flow rate, oxidation-reduction potential (ORP), conductivity, temperature, pH, total nitrogen and phosphorus concentration.

  12. Evaluating MC&A effectiveness to verify the presence of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Dawson, P. G. (Pamela G.); Morzinski, J. A. (Jerome A.); Ostenak, Carl A.; Longmire, V. L. (Victoria L.); Jewell, D. (Don); Williams, J. D. (Joel D.)

    2001-06-01

    Traditional materials accounting is focused exclusively on the material balance area (MBA), and involves periodically closing a material balance based on accountability measurements conducted during a physical inventory. In contrast, the physical inventory for Los Alamos National Laboratory's near-real-time accounting system is established around processes and looks more like an item inventory. That is, the intent is not to measure material for accounting purposes, since materials have already been measured in the normal course of daily operations. A given unit process operates many times over the course of a material balance period. The product of a given unit process may move for processing within another unit process in the same MBA or may be transferred out of the MBA. Since few materials are unmeasured the physical inventory for a near-real-time process area looks more like an item inventory. Thus, the intent of the physical inventory is to locate the materials on the books and verify information about the materials contained in the books. Closing a materials balance for such an area is a matter of summing all the individual mass balances for the batches processed by all unit processes in the MBA. Additionally, performance parameters are established to measure the program's effectiveness. Program effectiveness for verifying the presence of nuclear material is required to be equal to or greater than a prescribed performance level, process measurements must be within established precision and accuracy values, physical inventory results meet or exceed performance requirements, and inventory differences are less than a target/goal quantity. This approach exceeds DOE established accounting and physical inventory program requirements. Hence, LANL is committed to this approach and to seeking opportunities for further improvement through integrated technologies. This paper will provide a detailed description of this evaluation process.

  13. Programs for the work with ENSDF format files: Evaluator's editor EVE, Viewer for the nuclear level schemes

    CERN Document Server

    Shulyak, G I

    2010-01-01

    Tools for the regular work of the nuclear data evaluator are presented: the context-dependent editor EVE and the viewer for the level schemes of nuclei from ENSDF datasets. These programs may be used by everybody who works with the Evaluated Nuclear Structure Data File and for the educational purposed.

  14. Report to the US Nuclear Regulatory Commission on Analysis and Evaluation of Operational Data, 1986

    Energy Technology Data Exchange (ETDEWEB)

    None

    1987-05-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during calendar year 1986. Comments and observations are provided on operating experience at nuclear power plants and other NRC licensees, including results from selected AEOD studies; summaries of abnormal occurrences involving US nuclear plants; reviews of licensee event reports and their quality, reactor scram experience from 1984 to 1986, engineered safety features actuations, and the trends and patterns analysis program; and assessments of nonreactor and medical misadministration events. In addition, the report provides the year-end status of all recommendations included in AEOD studies, and listings of all AEOD reports issued from 1980 through 1986.

  15. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    Energy Technology Data Exchange (ETDEWEB)

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  16. Evaluation of spectral domain optical coherence tomography parameters in ocular hypertension, preperimetric, and early glaucoma.

    Science.gov (United States)

    Aydogan, Tuğba; Akçay, BetÜl İlkay Sezgin; Kardeş, Esra; Ergin, Ahmet

    2017-11-01

    The objective of this study is to evaluate the diagnostic ability of retinal nerve fiber layer (RNFL), macular, optic nerve head (ONH) parameters in healthy subjects, ocular hypertension (OHT), preperimetric glaucoma (PPG), and early glaucoma (EG) patients, to reveal factors affecting the diagnostic ability of spectral domain-optical coherence tomography (SD-OCT) parameters and risk factors for glaucoma. Three hundred and twenty-six eyes (89 healthy, 77 OHT, 94 PPG, and 66 EG eyes) were analyzed. RNFL, macular, and ONH parameters were measured with SD-OCT. The area under the receiver operating characteristic curve (AUC) and sensitivity at 95% specificity was calculated. Logistic regression analysis was used to determine the glaucoma risk factors. Receiver operating characteristic regression analysis was used to evaluate the influence of covariates on the diagnostic ability of parameters. In PPG patients, parameters that had the largest AUC value were average RNFL thickness (0.83) and rim volume (0.83). In EG patients, parameter that had the largest AUC value was average RNFL thickness (0.98). The logistic regression analysis showed average RNFL thickness was a risk factor for both PPG and EG. Diagnostic ability of average RNFL and average ganglion cell complex thickness increased as disease severity increased. Signal strength index did not affect diagnostic abilities. Diagnostic ability of average RNFL and rim area increased as disc area increased. When evaluating patients with glaucoma, patients at risk for glaucoma, and healthy controls RNFL parameters deserve more attention in clinical practice. Further studies are needed to fully understand the influence of covariates on the diagnostic ability of OCT parameters.

  17. Petrophysical evaluation of low-resistivity sandstone reservoirs with nuclear magnetic resonance log

    Energy Technology Data Exchange (ETDEWEB)

    Hamada, G.M.; Al-Blehed, M.S.; Al-Awad, M.N.; Al-Saddique, M.A. [Petroleum Engineering Department, College of Engineering, King Saud University, P.O. Box 800, 11421 Riyadh (Saudi Arabia)

    2001-04-01

    The combination of conventional logs, such as density, neutron and resistivity logs, is proven to be very effective in the evaluation of normal reservoirs. For low-resistivity reservoirs, however, an accurate determination of the petrophysical parameters with the conventional log reservoirs is very difficult. This paper presents two cases of low-resistivity reservoirs and low-contrast resistivity reservoirs, where conventional logs fail to determine the petrophysical properties of reservoirs, mainly, low-resistivity and low-contrast resistivity reservoirs. The problems of these reservoirs are that conventional logging interpretation shows high water saturation zones, but water-free hydrocarbon would be produced. In the case of low-resistivity contrast reservoirs, it is very hard to determine water hydrocarbon contact with resistivity logs. Nuclear magnetic resonance (NMR) has only been available as a supplementary tool to provide additional information on the producibility of the reservoir. The main limitations of NMR have been the cost and time of acquiring data. This paper shows that in the case of low-resistivity reservoirs, NMR is a very cost-effective tool and is of help in accurately determining the reservoir rock petrophysical properties. In the analysis of NMR data, several aspects of NMR technique have been used: (1) T1/T2 ratio for fluid identification, (2) the difference between NMR-derived porosity and total porosity to determine the types of clay minerals, (3) NMR relaxation properties to identify fluids composition and rock properties. This paper presents four examples of low-resistivity reservoirs. Analysis of the NMR data of low-resistivity reservoirs has helped identify the producibility of these zones, determine lithology-independent porosity and distinguish between bound and free water. For the case of low-contrast resistivity reservoir, where there was little resistivity contrast between water-bearing formation and oil-bearing formation, NMR has

  18. [Molecular biological evaluation of prognostic parameters in GIST. Development of an integrative model of tumor progression].

    Science.gov (United States)

    Haller, F

    2010-10-01

    Prognosis evaluation in gastrointestinal stromal tumors (GIST) is currently based on tumor diameter, mitotic counts and anatomic localisation. There are two risk classifications as well as the first ever TNM classification for GISTs, whereby the risk classification according to the Armed Forces Institute of Pathology (AFIP) has the best correlation with clinical follow-up according to own experiences. "Very low/low risk" GISTs are almost benign, while the majority of "high risk" GISTs metastasize and benefit from adjuvant therapy. Careful evaluation of mitotic counts in 50 high-power fields is of particular relevance for correct risk classification. Apart from these classical prognostic factors, many molecular genetic parameters with correlation to follow-up have been evaluated and may help to improve prognosis evaluation of GISTs in the future. Since most of the molecular genetic parameters are associated or even determined by the clinico-pathological parameters, an integrated model for tumor progression of GISTs is helpful to interpret the different factors in correlation to one another. In particular for "intermediate risk" GISTs, additional parameters are needed for improved prognosis evaluation.

  19. DIRECT EVALUATION OF OXIDATIVE STRESS AND ANTIOXIDANT DEFENSE PARAMETERS IN EXPERIMENT WITH THE AXIAL PUMP

    Directory of Open Access Journals (Sweden)

    N. V. Kuncevich

    2011-01-01

    Full Text Available It is established that increased parameters of oxidative stress result from an imbalance between reactive oxygen molecules and endogenous antioxidants. Oxidative stress parameters may be considered to be biomarkers of heart failure. The aim of our study was to asses oxidative stress and antioxidant system parameters in experi- mental model with the axial pump. Our study included 7 calves (the mean age 120.33 days, the mean weight 99.17 kg. We used «FORM Plus CR3000» analyzer (Callegary, Italy and heparinized venous blood samples for the evaluation of the oxidative status (FORT test and the total antioxidant capacity (FORD test. In healthy animals oxidative system parameters differ from those in humans (FORT – 0.42 ± 0.11 versus 1.74 ± 0.32 mmol/l H2O2; FORD/FORT – 3.92 ± 1.30 versus 1.33 ± 0.27, p < 0.05 what should be taken into consideration when interpreting the results of clinical and experimental studies. In three calves with experimental assisted circulation maximal oxidative stress values were observed on 1–3 days after the axial pump connection with the subsequent normalization of these parameters. Direct evaluation of oxidative stress parameters may be used as monitoring tool for estimation of assisted circulation adequacy in experiment (animal model. 

  20. Air contamination measurements for the evaluation of internal dose to workers in nuclear medicine departments

    Science.gov (United States)

    De Massimi, B.; Bianchini, D.; Sarnelli, A.; D'Errico, V.; Marcocci, F.; Mezzenga, E.; Mostacci, D.

    2017-11-01

    Radionuclides handled in nuclear medicine departments are often characterized by high volatility and short half-life. It is generally difficult to monitor directly the intake of these short-lived radionuclides in hospital staff: this makes measuring air contamination of utmost interest. The aim of the present work is to provide a method for the evaluation of internal doses to workers in nuclear medicine, by means of an air activity sampling detector, to ensure that the limits prescribed by the relevant legislation are respected. A continuous air sampling system measures isotope concentration with a Nal(TI) detector. Energy efficiency of the system was assessed with GEANT4 and with known activities of 18F. Air is sampled in a number of areas of the nuclear medicine department of the IRST-IRCCS hospital (Meldola- Italy). To evaluate committed doses to hospital staff involved (doctors, technicians, nurses) different exposure situations (rooms, times, radionuclides etc) were considered. After estimating the intake, the committed effective dose has been evaluated, for the different radionuclides, using the dose coefficients mandated by the Italian legislation. Error propagation for the estimated intake and personal dose has been evaluated, starting from measurement statistics.

  1. Inter-comparison of JEF-2.2 and JEFF-3.1 evaluated nuclear data through Monte Carlo analysis of VVER-1000 MOX Core Computational Benchmark

    Energy Technology Data Exchange (ETDEWEB)

    Thilagam, L., E-mail: thilagam@igcar.gov.i [AERB-Safety Research Institute, Kalpakkam, Tamilnadu 603 102 (India); Karthikeyan, R., E-mail: rkarthi@barc.gov.i [Light Water Reactors Physics Section, Reactor Physics Design Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India); Jagannathan, V., E-mail: v_jagan1952@rediffmail.co [Light Water Reactors Physics Section, Reactor Physics Design Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India); Subbaiah, K.V.; Lee, S.M. [AERB-Safety Research Institute, Kalpakkam, Tamilnadu 603 102 (India)

    2010-02-15

    The nuclear data forms a vital component in reactor core physics computations. The nuclear data is evaluated and modified on a continuous basis by different nuclear data centres and laboratories worldwide. The work on upgradation of the nuclear data is being carried out using new evaluations obtained through experiments and theoretical models to enhance their accuracy. Use of different sets of cross-section data in the analysis of a benchmark problem is a source of strong feedback for further improvements in data by mutual comparison of results. These comparisons also help to find out the best evaluated cross-section data released. Towards this objective, an attempt has been made to inter-compare JEF-2.2 and JEFF-3.1 evaluated nuclear data through the Monte Carlo simulation of 'VVER-1000 MOX Core Computational Benchmark'. This study deals with the calculation and inter-comparison of reactor parameters such as multiplication factors, cell average and assembly average fission reaction rate distributions estimated for various reactor state descriptions specified in the benchmark. Point-wise cross-section libraries processed from the JEF-2.2 and JEFF-3.1 evaluated data are used in the analysis. Concerning the multiplication factors and fission rate distributions, considerable differences are observed between the two libraries. While performing the MCNP calculations with JEFF-3.1 data, it is observed that the deviations of effective neutron multiplication factors (k{sub eff}) from those of benchmark standard MCU results are lower by about approx0.100% for the most of the states than those computed using JEF-2.2. Fission rate distributions using JEFF-3.1 data are also found to have significant deviations up to +-9.2% compared to calculations with its earlier version JEF-2.2 data. Some interesting trends on the used nuclear data are identified from the discrepancies of the individual results. The cause for considerable changes in the calculated parameters are

  2. Performance Evaluation and Parameter Optimization of Wavelength Division Multiplexing Networks with Importance Sampling Techniques

    NARCIS (Netherlands)

    Remondo Bueno, D.; Srinivasan, R.; Nicola, V.F.; van Etten, Wim; Tattje, H.E.P.

    1998-01-01

    In this paper new adaptive importance sampling techniques are applied to the performance evaluation and parameter optimization of wavelength division multiplexing (WDM) network impaired by crosstalk in an optical cross-connect. Worst-case analysis is carried out including all the beat noise terms

  3. Evaluation of selected postural parameters in children who practice kyokushin karate

    Directory of Open Access Journals (Sweden)

    Drzał-Grabiec Justyna

    2014-10-01

    Full Text Available Study aim: martial arts can be traced back thousands of years. Karate is one of the most common martial arts, and both children and adults practice it. The aim of the study was to evaluate selected body posture parameters in children aged 7–10 years who regularly practice karate.

  4. Evaluating Nuclear Membrane Irregularity for the Classification of Cervical Squamous Epithelial Cells.

    Directory of Open Access Journals (Sweden)

    Jing Rui Tang

    Full Text Available Pap test involves searching of morphological changes in cervical squamous epithelial cells by pathologists or cytotechnologists to identify potential cancerous cells in the cervix. Nuclear membrane irregularity is one of the morphological changes of malignancy. This paper proposes two novel techniques for the evaluation of nuclear membrane irregularity. The first technique, namely, penalty-driven smoothing analysis, introduces different penalty values for nuclear membrane contour with different degrees of irregularity. The second technique, which can be subdivided into mean- or median-type residual-based analysis, computes the number of points of nuclear membrane contour that deviates from the mean or median of the nuclear membrane contour. Performance of the proposed techniques was compared to three state-of-the-art techniques, namely, radial asymmetric, shape factor, and rim difference. Friedman and post hoc tests using Holm, Shaffer, and Bergmann procedures returned significant differences for all the three classes, i.e., negative for intraepithelial lesion or malignancy (NILM versus low grade squamous intraepithelial lesion (LSIL, NILM versus high grade squamous intraepithelial lesion (HSIL, and LSIL versus HSIL when the span value equaled 3 was employed with linear penalty function. When span values equaled 5, 7, and 9, NILM versus LSIL and HSIL showed significant differences regardless of the penalty functions. In addition, the results of penalty-driven smoothing analysis were comparable with those of other state-of-the-art techniques. Residual-based analysis returned significant differences for the comparison among the three diagnostic classes. Findings of this study proved the significance of nuclear membrane irregularity as one of the features to differentiate the different diagnostic classes of cervical squamous epithelial cells.

  5. Physical training is associated with changes in Nuclear magnetic resonance and morphometrical parameters of the skeletal muscle in senescent mice

    Directory of Open Access Journals (Sweden)

    C Zancanaro

    2009-08-01

    Full Text Available The effect of a three-month training period on T2 relaxation time as well as on myofibre size and type was investigated in the lower limbs of senescent mice. After training, T2 (which is a magnetic resonance imaging parameter known to increase during acute exercise was significantly higher in trained mice (36.37±1.27 vs 37.76±2.06 ms, p=0.003, n=8, whereas no change was found in non-trained animals (36.35±1.02 vs 36.24±1.15 ms, p=0.278, n=8. The percentage of muscle limb area evaluated in vivo on magnetic resonance images before and after the experimental period was unchanged in trained mice (69.84±2.50 vs 70.29±2.29, p=0.896, n=3 and decreased in non-trained animals (72.98±1.68 vs 64.62±2.34, p=0.006, n=3. Cross-sectional area of fast and slow myofibres, evaluated on paraffin-embedded samples after immunolabelling for skeletal fast fibre myosin, was lower in non-trained than in trained mice in both gastrocnemius and quadriceps muscle, but no change in slow/fast fibre ratio nor in apoptotic rate was found. These data show that training can prevent sarcopenia in senescent mice by affecting muscle status and inducing myofibre hypertrophy in the absence of significant muscle damage.

  6. Evaluation and Optimization of a Supercritical Carbon Dioxide Power Conversion Cycle for Nuclear Applications

    Energy Technology Data Exchange (ETDEWEB)

    Edwin A. Harvego; Michael G. McKellar

    2011-05-01

    There have been a number of studies involving the use of gases operating in the supercritical mode for power production and process heat applications. Supercritical carbon dioxide (CO2) is particularly attractive because it is capable of achieving relatively high power conversion cycle efficiencies in the temperature range between 550°C and 750°C. Therefore, it has the potential for use with any type of high-temperature nuclear reactor concept, assuming reactor core outlet temperatures of at least 550°C. The particular power cycle investigated in this paper is a supercritical CO2 Recompression Brayton Cycle. The CO2 Recompression Brayton Cycle can be used as either a direct or indirect power conversion cycle, depending on the reactor type and reactor outlet temperature. The advantage of this cycle when compared to the helium Brayton Cycle is the lower required operating temperature; 550°C versus 850°C. However, the supercritical CO2 Recompression Brayton Cycle requires an operating pressure in the range of 20 MPa, which is considerably higher than the required helium Brayton cycle operating pressure of 8 MPa. This paper presents results of analyses performed using the UniSim process analyses software to evaluate the performance of the supercritical CO2 Brayton Recompression Cycle for different reactor outlet temperatures. The UniSim model assumed a 600 MWt reactor power source, which provides heat to the power cycle at a maximum temperature of between 550°C and 750°C. The UniSim model used realistic component parameters and operating conditions to model the complete power conversion system. CO2 properties were evaluated, and the operating range for the cycle was adjusted to take advantage of the rapidly changing conditions near the critical point. The UniSim model was then optimized to maximize the power cycle thermal efficiency at the different maximum power cycle operating temperatures. The results of the analyses showed that power cycle thermal

  7. Evaluation of the emergency warning system at the Fort St. Vrain nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Sorensen, J.H.

    1982-11-01

    The Fort St. Vrain power plant is the only high-temperature gas-cooled reactor (HTGR) in commercial operation in the United States. All commercial reactors, regardless of technology, must conform to Nuclear Regulatory Commission emergency planning regulations developed in light of Clarification of TMI Action Plan Requirements (NUREG-0737). This report analyzes the applicability of warning-related planning requirements to HTGRs and evaluates the strengths and weaknesses of warning procedures at Fort St. Vrain.

  8. Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs

    Energy Technology Data Exchange (ETDEWEB)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1977-02-01

    This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis.

  9. Release of the ENDF/B-VII.1 Evaluated Nuclear Data File

    Energy Technology Data Exchange (ETDEWEB)

    Brown, David

    2012-06-30

    The Cross Section Evaluation Working Group (CSEWG) released the ENDF/B-VII.1 library on December 22, 2011. The ENDF/B-VII.1 library is CSEWG's latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0, including: many new evaluation in the neutron sublibrary (423 in all and over 190 of these contain covariances), new fission product yields and a greatly improved decay data sublibrary. This summary barely touches on the five years worth of advances present in the ENDF/B-VII.1 library. We expect that these changes will lead to improved integral performance in reactors and other applications. Furthermore, the expansion of covariance data in this release will allow for better uncertainty quantification, reducing design margins and costs. The ENDF library is an ongoing and evolving effort. Currently, the ENDF data community embarking on several parallel efforts to improve library management: (1) The adoption of a continuous integration system to provide evaluators 'instant' feedback on the quality of their evaluations and to provide data users with working 'beta' quality libraries in between major releases. (2) The transition to new hierarchical data format - the Generalized Nuclear Data (GND) format. We expect GND to enable new kinds of evaluated data which cannot be accommodated in the legacy ENDF format. (3) The development of data assimilation and uncertainty propagation techniques to enable the consistent use of integral experimental data in the evaluation process.

  10. Evaluation of severe accident risks: Quantification of major input parameters: MAACS (MELCOR Accident Consequence Code System) input

    Energy Technology Data Exchange (ETDEWEB)

    Sprung, J.L.; Jow, H-N (Sandia National Labs., Albuquerque, NM (USA)); Rollstin, J.A. (GRAM, Inc., Albuquerque, NM (USA)); Helton, J.C. (Arizona State Univ., Tempe, AZ (USA))

    1990-12-01

    Estimation of offsite accident consequences is the customary final step in a probabilistic assessment of the risks of severe nuclear reactor accidents. Recently, the Nuclear Regulatory Commission reassessed the risks of severe accidents at five US power reactors (NUREG-1150). Offsite accident consequences for NUREG-1150 source terms were estimated using the MELCOR Accident Consequence Code System (MACCS). Before these calculations were performed, most MACCS input parameters were reviewed, and for each parameter reviewed, a best-estimate value was recommended. This report presents the results of these reviews. Specifically, recommended values and the basis for their selection are presented for MACCS atmospheric and biospheric transport, emergency response, food pathway, and economic input parameters. Dose conversion factors and health effect parameters are not reviewed in this report. 134 refs., 15 figs., 110 tabs.

  11. Development of a web-based monitoring system using operation parameters for the main component in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; An, Kung Il; Hong, Suk Young; Lee, Jeong Soo; Jung, Duk Jin; Shin, Sun Hee; Son, So Hee [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2004-02-15

    The frequency of the damage is increasing, which is caused by the fatigue, according to the increase of running of nuclear power plants. So we need to acquire the reliance of design data to estimate the fatigue and damage of major machinery that might happen as time-dependent crack growth characterization. The research is focused on keeping operating record of nuclear power plants about major machinery which consists of a nuclear reactor pressure boarder on each excessive operating condition including normal operating and extraordinary operating by estimating fracture mechanical movements on real time and fatigue about major nuclear power plants machinery, which are acquired the pressure and temperature data. For further details about the scope and contents of R and D are following. Development of H/W that is necessary to acquire operating real time data of heating and hydraulic power. Selection of a safety variable about major system by each type (the four NPP, all unit). Communication protocol development for connecting between CARE system data base server and fatigue monitoring system data base server. Development of connecting database for controlling and storing of heating and hydraulic power operating data. Real time monitoring system development based on Web using JAVA.

  12. [Evaluation of imaging parameters for T1 dynamic contrast enhanced MRI with fast spin-echo].

    Science.gov (United States)

    Kanazawa, Yuuki; Miyati, Tosiaki; Inoue, Yusuke; Sato, Osamu

    2007-10-20

    For the purpose of continual measurement of the T1 value using the FSE (fast spin-echo) sequence and evaluation of the hemodynamics, we assessed T1 values when the imaging parameters were changed. Moreover, with the imaging parameters derived from this study, dynamic contrast-enhanced MR imaging (MRI) was examined in prostatic disease. First, the T1 value before contrast agent injection was measured with imaging parameters that had different TR and fixed TE. Next, dynamic contrast-enhanced imaging data were acquired for the imaging parameters using TE and TR in the same way as before contrast agent injection, and the T1 value of the tissue at contrast enhancement was measured. In the phantom studies, the TSE imaging parameters with short TE, long TR, and few ETL were connected with the mixed sequence. In dynamic study of the prostate, the difference between normal prostate and prostate cancer became clearer with the time-relaxation rate curve than the time-signal curve. This method using TSE is able to evaluate in greater detail information on hemodynamics and to perform dynamic study with the spin-echo sequence in extensive tissues.

  13. Evaluation of Hydraulic Parameters Obtained by Different Measurement Methods for Heterogeneous Gravel Soil

    Directory of Open Access Journals (Sweden)

    Chen Zeng

    2012-01-01

    Full Text Available Knowledge of soil hydraulic parameters for the van Genuchten function is important to characterize soil water movement for watershed management. Accurate and rapid prediction of soil water flow in heterogeneous gravel soil has become a hot topic in recent years. However, it is difficult to precisely estimate hydraulic parameters in a heterogeneous soil with rock fragments. In this study, the HYDRUS-2D numerical model was used to evaluate hydraulic parameters for heterogeneous gravel soil that was irregularly embedded with rock fragments in a grape production base. The centrifugal method (CM, tensiometer method (TM and inverse solution method (ISM were compared for various parameters in the van Genuchten function. The soil core method (SCM, disc infiltration method (DIM and inverse solution method (ISM were also investigated for measuring saturated hydraulic conductivity. Simulation with the DIM approach revealed a problem of overestimating soil water infiltration whereas simulation with the SCM approach revealed a problem of underestimating water movement as compared to actual field observation. The ISM approach produced the best simulation result even though this approach slightly overestimated soil moisture by ignoring the impact of rock fragments. This study provides useful information on the overall evaluation of soil hydraulic parameters attained with different measurement methods for simulating soil water movement and distribution in heterogeneous gravel soil.

  14. A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Lahti, Erik A.; Richmond, David J.

    2012-08-01

    This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

  15. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-02-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative—intended to catalog final products—rather than formative—intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  16. Determination of a quantitative parameter to evaluate swimming technique based on the maximal tethered swimming test.

    Science.gov (United States)

    Soncin, Rafael; Mezêncio, Bruno; Ferreira, Jacielle Carolina; Rodrigues, Sara Andrade; Huebner, Rudolf; Serrão, Julio Cerca; Szmuchrowski, Leszek

    2017-06-01

    The aim of this study was to propose a new force parameter, associated with swimmers' technique and performance. Twelve swimmers performed five repetitions of 25 m sprint crawl and a tethered swimming test with maximal effort. The parameters calculated were: the mean swimming velocity for crawl sprint, the mean propulsive force of the tethered swimming test as well as an oscillation parameter calculated from force fluctuation. The oscillation parameter evaluates the force variation around the mean force during the tethered test as a measure of swimming technique. Two parameters showed significant correlations with swimming velocity: the mean force during the tethered swimming (r = 0.85) and the product of the mean force square root and the oscillation (r = 0.86). However, the intercept coefficient was significantly different from zero only for the mean force, suggesting that although the correlation coefficient of the parameters was similar, part of the mean velocity magnitude that was not associated with the mean force was associated with the product of the mean force square root and the oscillation. Thus, force fluctuation during tethered swimming can be used as a quantitative index of swimmers' technique.

  17. Installation and evaluation of a nuclear power plant Operator Advisor based on artificial intelligence technology

    Energy Technology Data Exchange (ETDEWEB)

    Hajek, B.K.; Miller, D.W.

    1993-02-01

    The Artificial Intelligence Group in the Nuclear Engineering Program has designed and built an Operator Advisor (OA), an AI system to monitor nuclear power plant parameters, detect component and system malfunctions, dispose their causes, and provide the plant operators with the correct procedures for mitigating the consequences of the malfunctions. It then monitors performance of the procedures, and provides backup steps when specific operator actions fail. The OA has been implemented on Sun 4 workstations in Common Lisp, and has been interfaced to run in real time on the Perry Nuclear Power Plant full-function simulator in the plant training department. The eventual goal for a fully functioning Operator Advisor would be to have reactor operators receive direction for all plant operations. Such a goal requires considerable testing of the system within limited malfunction boundaries, an extensive Verification Validation (V V) effort, a large knowledge base development effort, and development of tools as part of the system to automate its maintenance. Clearly, these efforts are beyond the scope of the feasibility effort expended during this project period. However, as a result of this project, we have an AI based platform upon which a complete system can be built.

  18. Aging and service wear of auxiliary feedwater pumps for PWR nuclear plants: Volume 2, Aging assessments and monitoring method evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Kitch, D.M.; Schlonski, J.S.; Sowatskey, P.J.; Cesarski, W.V.

    1988-06-01

    This report was produced under the Detection of Defects and Degradation Monitoring Element of the Nuclear Plant Aging Research Program. It addresses aging assessments and monitoring method evaluations for auxiliary feedwater pumps (AUXFPs). The report contains four major sections: failure causes; review of inspection, surveillance, and condition monitoring (ISCM) methods; evaluation of ISCM methods; and role of maintenance in alleviating aging and service wear. Failure causes attributable to aging and service wear are given and ranked in terms of importance. Cause identifications are made on the bases of experience, postservice examinations, and in situ assessments. Measurable parameters related to failure causes are identified. ISCM methods are also identified, evaluations are made based on Westinghouse (W) experience, and recommendations are given. The methods are intended to yield required capabilities for establishing operational readiness, as well as for detecting and tracking degradation. The role of maintenance in mitigating aging and service wear effects is discussed, and the relationship of maintenance to ISCM methods is identified. Predictive, preventive, and corrective maintenance practices are discussed and evaluated.

  19. The evaluation of the 1001.03 keV gamma emission absolute intensity using fundamental parameter method.

    Science.gov (United States)

    Khater, A E M; Ebaid, Y Y

    2017-12-01

    The accurate evaluation of the absolute intensity of the gamma-ray transition 1001.03 keV of 234m Pa is crucial for accurate determination of 238 U in nuclear material and environmental samples. Over the last decades, a wide range of 1001.03 keV absolute intensity values were published by different researchers and ranged from 0.59 to 1.12%. Nowadays, one of the most commonly used values is 0.847 ± 0.008% that seems not accurate and would eventually lead to an overestimation of 238 U activity concentration. The absolute intensity of 1001.03 keV gamma transition was re-evaluated using different fundamental parameter method (FPM) modes, uranium ore and granite samples, samples' geometries, sample-to-detectors' geometries and gamma ray spectrometers. The mean ± standard deviation of newly optimized absolute intensity value is 1.067 ± 0.084% with an average relative bias of - 20% from the commonly used value. Copyright © 2017 Elsevier Ltd. All rights reserved.

  20. Evaluating the Performance of Polynomial Regression Method with Different Parameters during Color Characterization

    Directory of Open Access Journals (Sweden)

    Bangyong Sun

    2014-01-01

    Full Text Available The polynomial regression method is employed to calculate the relationship of device color space and CIE color space for color characterization, and the performance of different expressions with specific parameters is evaluated. Firstly, the polynomial equation for color conversion is established and the computation of polynomial coefficients is analysed. And then different forms of polynomial equations are used to calculate the RGB and CMYK’s CIE color values, while the corresponding color errors are compared. At last, an optimal polynomial expression is obtained by analysing several related parameters during color conversion, including polynomial numbers, the degree of polynomial terms, the selection of CIE visual spaces, and the linearization.

  1. Evaluation of cellular and biochemical parameters of blood and peritoneal fluid following enterectomy in the goat.

    Science.gov (United States)

    Nazifi; Dehghani; Barzegar

    2000-07-01

    To evaluate the effects of enterectomy on cellular and biochemical parameters of blood and peritoneal fluid, an experiment was conducted using 10 Iranian crossbred male goats. Ten milliliter of blood and 1-1.5ml of peritoneal fluid were sampled from all animals prior to operation for the estimation of control values. Enterectomy was performed under local anesthesia. Blood and peritoneal fluid samples were collected at 24, 48, 72 and 96h after enterectomy. The results revealed that after enterectomy, the number of WBCs, neutrophils, monocytes and band neutrophils in the blood significantly increased (penterectomy can have profound effects on blood and peritoneal fluid parameters.

  2. A review of methods for evaluating the quantitative parameters of sagittal pelvic alignment.

    Science.gov (United States)

    Vrtovec, Tomaž; Janssen, Michiel M A; Likar, Boštjan; Castelein, René M; Viergever, Max A; Pernuš, Franjo

    2012-05-01

    The sagittal alignment of the pelvis represents the basic mechanism for maintaining postural equilibrium, and a number of methods were developed to assess normal and pathologic pelvic alignments from two-dimensional sagittal radiographs in terms of positional and anatomic parameters. To provide a complete overview of the existing methods for quantitative evaluation of sagittal pelvic alignment and summarize the relevant publications. Review article. An Internet search for terms related to sagittal pelvic alignment was performed to obtain relevant publications, which were further supplemented by selected publications found in their lists of references. By summarizing the obtained publications, the positional and anatomic parameters of sagittal pelvic alignment were described, and their values and relationships to other parameters and features were reported. Positional pelvic parameters relate to the position and orientation of the observed subject and are represented by the sacral slope, pelvic tilt, pelvic overhang, sacral inclination, sacrofemoral angle, sacrofemoral distance, pelvic femoral angle, pelvic angle, and sacropelvic translation. Anatomic pelvic parameters relate to the anatomy of the observed subject and are represented by the pelvisacral angle (PSA), pelvic incidence (PI), pelvic thickness (PTH), sacropelvic angle (PRS1), pelvic radius (PR), femorosacral posterior angle (FSPA), sacral table angle (STA), and sacral anatomic orientation (SAO). The review was mainly focused on the evaluation of anatomic pelvic parameters, as they can be compared among subjects and therefore among different studies. However, ambiguous results were yielded for normal and pathologic subjects, as the reported values show a relatively high variability in terms of standard deviation for every anatomic parameter, which amounts to around 10 mm for PTH and PR; 10° for PSA, PI, and SAO; 9° for PRS1 and FSPA; and 5° for STA in the case of normal subjects and is usually even

  3. NEAMS Nuclear Waste Management IPSC : evaluation and selection of tools for the quality environment.

    Energy Technology Data Exchange (ETDEWEB)

    Bouchard, Julie F.; Stubblefield, William Anthony; Vigil, Dena M.; Edwards, Harold Carter (Org. 1444 : Multiphysics Simulation Technology)

    2011-05-01

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Nuclear Waste Management Integrated Performance and Safety Codes (NEAMS Nuclear Waste Management IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. These M&S capabilities are to be managed, verified, and validated within the NEAMS Nuclear Waste Management IPSC quality environment. M&S capabilities and the supporting analysis workflow and simulation data management tools will be distributed to end-users from this same quality environment. The same analysis workflow and simulation data management tools that are to be distributed to end-users will be used for verification and validation (V&V) activities within the quality environment. This strategic decision reduces the number of tools to be supported, and increases the quality of tools distributed to end users due to rigorous use by V&V activities. This report documents an evaluation of the needs, options, and tools selected for the NEAMS Nuclear Waste Management IPSC quality environment. The objective of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation Nuclear Waste Management Integrated Performance and Safety Codes (NEAMS Nuclear Waste Management IPSC) program element is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to assess quantitatively the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. This objective will be fulfilled by acquiring and developing M&S capabilities, and establishing a defensible level of confidence in these M&S capabilities. The foundation for assessing the level of confidence is based upon

  4. Evaluation of Methods for Estimation of Cyclic Stress-Strain Parameters from Monotonic Properties of Steels

    Directory of Open Access Journals (Sweden)

    Tea Marohnić

    2017-01-01

    Full Text Available Most existing methods for estimation of cyclic yield stress and cyclic Ramberg-Osgood stress-strain parameters of steels from their monotonic properties were developed on relatively modest number of material datasets and without considerations of the particularities of different steel subgroups formed according to their chemical composition (unalloyed, low-alloy, and high-alloy steels or delivery, i.e., testing condition. Furthermore, some methods were evaluated using the same datasets that were used for their development. In this paper, a comprehensive statistical analysis and evaluation of existing estimation methods were performed using an independent set of experimental material data compriseding 116 steels. Results of performed statistical analyses reveal that statistically significant differences exist among unalloyed, low-alloy, and high-alloy steels regarding their cyclic yield stress and cyclic Ramberg-Osgood stress-strain parameters. Therefore, estimation methods were evaluated separately for mentioned steel subgroups in order to more precisely determine their applicability for the estimation of cyclic behavior of steels belonging to individual subgroups. Evaluations revealed that considering all steels as a single group results in averaging and that subgroups should be treated independently. Based on results of performed statistical analysis, guidelines are provided for identification and selection of suitable methods to be applied for the estimation of cyclic stress-strain parameters of steels.

  5. Evaluation of isotopic composition of fast reactor core in closed nuclear fuel cycle

    Science.gov (United States)

    Tikhomirov, Georgy; Ternovykh, Mikhail; Saldikov, Ivan; Fomichenko, Peter; Gerasimov, Alexander

    2017-09-01

    The strategy of the development of nuclear power in Russia provides for use of fast power reactors in closed nuclear fuel cycle. The PRORYV (i.e. «Breakthrough» in Russian) project is currently under development. Within the framework of this project, fast reactors BN-1200 and BREST-OD-300 should be built to, inter alia, demonstrate possibility of the closed nuclear fuel cycle technologies with plutonium as a main source of energy. Russia has a large inventory of plutonium which was accumulated in the result of reprocessing of spent fuel of thermal power reactors and conversion of nuclear weapons. This kind of plutonium will be used for development of initial fuel assemblies for fast reactors. The closed nuclear fuel cycle concept of the PRORYV assumes self-supplied mode of operation with fuel regeneration by neutron capture reaction in non-enriched uranium, which is used as a raw material. Operating modes of reactors and its characteristics should be chosen so as to provide the self-sufficient mode by using of fissile isotopes while refueling by depleted uranium and to support this state during the entire period of reactor operation. Thus, the actual issue is modeling fuel handling processes. To solve these problems, the code REPRORYV (Recycle for PRORYV) has been developed. It simulates nuclide streams in non-reactor stages of the closed fuel cycle. At the same time various verified codes can be used to evaluate in-core characteristics of a reactor. By using this approach various options for nuclide streams and assess the impact of different plutonium content in the fuel, fuel processing conditions, losses during fuel processing, as well as the impact of initial uncertainties on neutron-physical characteristics of reactor are considered in this study.

  6. Evaluation of barriers and resilience to improve organizational performance in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, P. F.; Martin del Campo, C., E-mail: pnelson_007@yahoo.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, Jiutepec 62550, Morelos (Mexico)

    2014-10-15

    In this study, several models are built from the information contained in the Condition Reports from the Corrective Action Program ar a nuclear power plant. Condition Reports are seen as indications of organizational stress levels with consequential Condition Reports being further evidence of organizational resilience being exceeded. Also contained in this paper is an examination of methods used to assess organizational resilience thresholds to preclude consequential events, based on examination of the number and severity of the Condition Reports. In combination with PSA risk insights, it is possible to identify risk significant procedures and their corresponding risk significant steps. Leading indicators can be used to identify the need for installing a barrier or defense to reduce human errors in a nuclear power plant. These indicators are developed from the Corrective Action Program data by detecting increases in events. Organizational barriers can then be identified to improve performance. The resulting identified barriers are evaluated to rank the value of each possible barrier, and determine the best barrier(s) to implement. The tool described in this paper is designed to provide a systematic approach to identify areas where improvements in organizational effectiveness best reduce the likelihood of consequential events. Due to the uncertainty of many of the factors that influence the performance of humans in nuclear power plant activities, we propose using Bayesian networks to identify sources of organizational errors leading to consequential events. This study, using actual nuclear power plant data, includes a method for data processing and highlights some potential uses of Bayesian networks for improving organizational effectiveness in the nuclear power industry. (Author)

  7. Examination of various roles for covariance matrices in the development, evaluation, and application of nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.L.

    1988-01-01

    The last decade has been a period of rapid development in the implementation of covariance-matrix methodology in nuclear data research. This paper offers some perspective on the progress which has been made, on some of the unresolved problems, and on the potential yet to be realized. These discussions address a variety of issues related to the development of nuclear data. Topics examined are: the importance of designing and conducting experiments so that error information is conveniently generated; the procedures for identifying error sources and quantifying their magnitudes and correlations; the combination of errors; the importance of consistent and well-characterized measurement standards; the role of covariances in data parameterization (fitting); the estimation of covariances for values calculated from mathematical models; the identification of abnormalities in covariance matrices and the analysis of their consequences; the problems encountered in representing covariance information in evaluated files; the role of covariances in the weighting of diverse data sets; the comparison of various evaluations; the influence of primary-data covariance in the analysis of covariances for derived quantities (sensitivity); and the role of covariances in the merging of the diverse nuclear data information. 226 refs., 2 tabs.

  8. Combining Total Monte Carlo and Benchmarks for Nuclear Data Uncertainty Propagation on a Lead Fast Reactor's Safety Parameters

    Science.gov (United States)

    Alhassan, E.; Sjöstrand, H.; Duan, J.; Gustavsson, C.; Koning, A. J.; Pomp, S.; Rochman, D.; Österlund, M.

    2014-04-01

    Analyses are carried out to assess the impact of nuclear data uncertainties on keff for the European Lead Cooled Training Reactor (ELECTRA) using the Total Monte Carlo method. A large number of 239Pu random ENDF-formatted libraries generated using the TALYS based system were processed into ACE format with NJOY-99.336 code and used as input into the Serpent Monte Carlo neutron transport code to obtain distribution in keff. The mean of the keff distribution obtained was compared with the major nuclear data libraries, JEFF-3.1.1, ENDF/B-VII.1 and JENDL-4.0. A method is proposed for the selection of benchmarks for specific applications using the Total Monte Carlo approach. Finally, an accept/reject criterion was investigated based on χ2 values obtained using the 239Pu Jezebel criticality benchmark. It was observed that nuclear data uncertainties in keff were reduced considerably from 748 to 443 pcm by applying a more rigid acceptance criteria for accepting random files.

  9. Use of nuclear techniques and hydrochemical analysis to evaluate the impact of tailings dams

    Energy Technology Data Exchange (ETDEWEB)

    Fernandes, Flaviane M.; Fleming, Peter M.; Fonseca, Flávio H. da R.; Pimenta, Rafael C.; Moreira, Rubens M., E-mail: flaviane@cdtn.br, E-mail: pmf@cdtn.br, E-mail: flavio.fonseca@cdtn.br, E-mail: colombopimenta@gmail.com, E-mail: rubens@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-11-01

    The mining industry is a most important productive segment to country's economy. However, it is important to recognize and monitor the environmental impacts caused by mining, such as dams. They are structures built to store the waste produced by the beneficiation of ores, through chemical and mechanical processes classified as concentrate, crude ore or tailings. Tailings dams are associated with a potential risk of disruption and can therefore cause various images to the environment and population. Seepage flows and transport mechanisms are parameters to indicate the structural integrity. Nuclear technology can be used as a tool to trace these parameters. The objective of this work is to use isotopic techniques and hydrochemical characterization to detect leaks in dams belonging to a mining company. The isotopic techniques are used to measure the concentration of environmental isotopes in dam waters and their mediations, among which deuterium ({sup 2}H) and oxygen-18 ({sup 18}O) are measured. These isotopes will be used as environmental tracers to investigate the presence of infiltrations through the displacement of the water in its flow in the aquifer, since they are constituent of the molecule of water. In parallel, the basic physical chemical parameters and water quality parameters will be measured in-situ to aid in the interpretation of the results of the isotopic analyzes. Thus, it is intended to provide data that can help the environmental agencies to make decisions regarding the decommissioning of the mine. (author)

  10. A Fuzzy method for the usability evaluation of nuclear medical equipment

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Cláudio H.S.; Santos, Isaac J.A.L.; Farias, Marcos S.; Farias, Larissa P.; Filho, Alfredo M.V., E-mail: grecco@ien.gov.br, E-mail: luquetti@ien.gov.br, E-mail: msantana@ien.gov.br, E-mail: larissapfarias@ymail.com, E-mail: marques@ien.gov.br [Instituto de Engenharia Nuclear (DENN/IEN/CNEN/RJ), Rio de Janeiro, RJ (Brazil). Departamento de Engenharia Nuclear

    2017-11-01

    To avoid errors when handling nuclear medical equipment, it is important to develop products with a high degree of usability. This can be achieved by performing usability evaluations in the product development process to detect and mitigate potential usability problems. Usability evaluation focuses on how well users can learn and use a product to achieve their goals. Thus, the usability evaluation has become recognized as a valuable complement to the established approaches to design good user interfaces, to reduce incidents and accidents as well the time required to learn how to use the equipment. To gather information about usability, practitioners use a variety of methods that gather feedback from users about an existing interface or plans related to a new interface. A wide range of usability evaluation methods have been proposed, but few methods focus on developing an objective and practical evaluation method for usability. Moreover, the usability evaluations are based on human judgments and most methods cannot fully solve the subjectivity of these evaluations. In order to remedy this deficiency, the purpose of this work is to adopt a Fuzzy Set Theory (FST) approach to establish a method for the usability evaluation of nuclear medical equipment based on usability heuristics for user interface design and international standards for ergonomics of human-system interaction. To exemplify the method we performed a usability evaluating of the Digital Spectrometer ESP 13004 by testing it with representative users. The results showed that the method is a proactive tool to provide a basis for checking usability of medical device interfaces. (author)

  11. Monte Carlo tools evaluation for nuclear analyses of the European DEMO

    Energy Technology Data Exchange (ETDEWEB)

    Jaboulay, Jean-Charles, E-mail: jean-charles.jaboulay@cea.fr [CEA-Saclay, DEN, DM2S, SERMA, LPEC, F-91191 Gif-sur-Yvette (France); Damian, Frédéric [CEA-Saclay, DEN, DM2S, SERMA, LPEC, F-91191 Gif-sur-Yvette (France); Aiello, Giacomo [CEA-Saclay, DEN, DM2S, SEMT, LISN, F-91191 Gif-sur-Yvette (France); Taylor, David; Zheng, Shanliang [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Bienkowska, Barbara; Drozdowicz, Krzysztof; Tracz, Grzegorz [IPPLM, Warsaw/IFJ Krakow (Poland); Fischer, Ulrich [KIT – Karlsruhe Institute of Technology, Karlsruhe (Germany); Bachmann, Christian [EFDA – European Fusion Development Agreement, Garching (Germany)

    2015-10-15

    This paper presents the status of different Monte Carlo (MC) particle transport codes regarding their capabilities to model the European fusion power demonstration reactor (DEMO). This work was carried out, via a collaboration between CEA, CCFE, IPPLM and KIT to evaluate MC codes which could replace MCNP for nuclear analysis on DEMO. Each association has participated using a different MC code: CEA with TRIPOLI-4, CCFE with Serpent, and IPPLM with FLUKA. The common DEMO model studied has been developed by KIT with MCNP. Considerable effort was required to translate the MCNP input deck into the syntax of Serpent and FLUKA codes; so no real nuclear analysis has been performed in the frame of this work. Regarding TRIPOLI-4, a benchmark has been successfully conducted; the results obtained are statistically similar to those of MCNP with comparable computation times.

  12. Nuclear medicine imaging technique in the erectile dysfunction evaluation: a mini-review

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Camila Godinho; Moura, Regina; Neves, Rosane de Figueiredo [Universidade do Estado do Rio de Janeiro (UERJ), RJ (Brazil). Inst. de Biologia Roberto Alcantara Gomes. Lab. de Radiofarmacia Experimental]. E-mail: cacagr@yahoo.com.br; Spinosa, Jean Pierre [Hopital de Zone, Morges (Switzerland). Dept. of Gynecology and Obstetrics; Bernardo-Filho, Mario [Instituto Nacional do Cancer, Rio de Janeiro, RJ (Brazil). Coordenadoria de Pesquisa

    2007-09-15

    Functional imaging with positron emission tomography and single photon emission computed tomography is capable of visualizing subtle changes in physiological function in vivo. Erectile dysfunction (ED) diminishes quality of life for affected men and their partners. Identification of neural substrates may provide information regarding the pathophysiology of types of sexual dysfunction originating in the brain. The aim of this work is to verify the approaches of the nuclear medicine techniques in the evaluation of the erectile function/dysfunction. A search using the words ED and nuclear medicine, ED and scintigraphy, ED and SPECT and ED and PET was done in the PubMed. The number of citations in each subject was determined. Neuroimaging techniques offer insight into brain regions involved in sexual arousal and inhibition. To tackle problems such as hyposexual disorders or ED caused by brain disorders, it is crucial to understand how the human brain controls sexual arousal and penile erection. (author)

  13. New parameters for a better evaluation of vegetative bioremediation, leaching, and phytodesalination.

    Science.gov (United States)

    Rabhi, Mokded; Atia, Abdallah; Abdelly, Chedly; Smaoui, Abderrazak

    2015-10-21

    Vegetative bioremediation of calcareous sodic and saline-sodic soils is a biological approach for soil desalination by plants. It is based on three main processes: (i) sodium release from cation exchange sites, (ii) its leaching, and/or (iii) phytodesalination (Na(+) uptake by plant roots and its accumulation in shoots). Leaching needs sufficient rainfall and/or adequate irrigation. Thus, under non-leaching conditions, phytodesalination is the only existing process in terms of sodium removal. Several works tried to evaluate these processes; used plants were grown in field, in lysimeters, or in non-perforated pots. The evaluation of vegetative bioremediation, leaching, and phytodesalination was mainly based on plant analyses (including biomass production, sodium accumulation, test culture, and co-culture) and soil analyses (porosity, salinity, sodicity...). Nevertheless, used parameters are not enough to ensure comparisons between results found in different investigations. The present study introduces new parameters like phytodesalination efficiency, yield, and rate as well as vegetative bioremediation and leaching yields and rates. Our study is also illustrated by an estimation of all parameters for several previously-published data from our own works and those of other authors. Obtained results showed usefulness of these parameters and some of them can be extended to heavy metal phytoexraction. Copyright © 2015 Elsevier Ltd. All rights reserved.

  14. Design of wearable and wireless multi-parameter monitoring system for evaluating cardiopulmonary function.

    Science.gov (United States)

    Li, Shih-Hong; Lin, Bor-Shing; Wang, Chen-An; Yang, Cheng-Ta; Lin, Bor-Shyh

    2017-09-01

    The 6-minute walking test (6MWT) is the test most commonly used to evaluate cardiopulmonary function in patients with respiratory or heart disease. However, there was previously no integrated monitoring system available to simultaneously record both the real-time cardiopulmonary physiological parameters and the walking information (i.e., walking distance, speed, and acceleration) during the 6MWT. In this study, then, a wearable and wireless multi-parameter monitoring system was proposed to simultaneously monitor oxygen saturation (SpO2), heart rhythm, and the walking information during the 6MWT. A multi-parameter detection algorithm was also designed to estimate the heart rate effectively. The results of the study indicate that this system was able to reveal the dynamic changes and differences in walking speed and acceleration during the 6MWT. As such, the system has the potential to provide a more integrated approach to monitoring cardiopulmonary parameters and walking information simultaneously during the 6MWT. The proposed system warrants further investigation as an assistive assessment tool in evaluating cardiopulmonary function and may be widely applied in cardiopulmonary-related and sports medicine applications in the future. Copyright © 2017 IPEM. Published by Elsevier Ltd. All rights reserved.

  15. Quantitative evaluation methods of skin condition based on texture feature parameters

    Directory of Open Access Journals (Sweden)

    Hui Pang

    2017-03-01

    Full Text Available In order to quantitatively evaluate the improvement of the skin condition after using skin care products and beauty, a quantitative evaluation method for skin surface state and texture is presented, which is convenient, fast and non-destructive. Human skin images were collected by image sensors. Firstly, the median filter of the 3 × 3 window is used and then the location of the hairy pixels on the skin is accurately detected according to the gray mean value and color information. The bilinear interpolation is used to modify the gray value of the hairy pixels in order to eliminate the negative effect of noise and tiny hairs on the texture. After the above pretreatment, the gray level co-occurrence matrix (GLCM is calculated. On the basis of this, the four characteristic parameters, including the second moment, contrast, entropy and correlation, and their mean value are calculated at 45 ° intervals. The quantitative evaluation model of skin texture based on GLCM is established, which can calculate the comprehensive parameters of skin condition. Experiments show that using this method evaluates the skin condition, both based on biochemical indicators of skin evaluation methods in line, but also fully consistent with the human visual experience. This method overcomes the shortcomings of the biochemical evaluation method of skin damage and long waiting time, also the subjectivity and fuzziness of the visual evaluation, which achieves the non-destructive, rapid and quantitative evaluation of skin condition. It can be used for health assessment or classification of the skin condition, also can quantitatively evaluate the subtle improvement of skin condition after using skin care products or stage beauty.

  16. Quantitative evaluation methods of skin condition based on texture feature parameters.

    Science.gov (United States)

    Pang, Hui; Chen, Tianhua; Wang, Xiaoyi; Chang, Zhineng; Shao, Siqi; Zhao, Jing

    2017-03-01

    In order to quantitatively evaluate the improvement of the skin condition after using skin care products and beauty, a quantitative evaluation method for skin surface state and texture is presented, which is convenient, fast and non-destructive. Human skin images were collected by image sensors. Firstly, the median filter of the 3 × 3 window is used and then the location of the hairy pixels on the skin is accurately detected according to the gray mean value and color information. The bilinear interpolation is used to modify the gray value of the hairy pixels in order to eliminate the negative effect of noise and tiny hairs on the texture. After the above pretreatment, the gray level co-occurrence matrix (GLCM) is calculated. On the basis of this, the four characteristic parameters, including the second moment, contrast, entropy and correlation, and their mean value are calculated at 45 ° intervals. The quantitative evaluation model of skin texture based on GLCM is established, which can calculate the comprehensive parameters of skin condition. Experiments show that using this method evaluates the skin condition, both based on biochemical indicators of skin evaluation methods in line, but also fully consistent with the human visual experience. This method overcomes the shortcomings of the biochemical evaluation method of skin damage and long waiting time, also the subjectivity and fuzziness of the visual evaluation, which achieves the non-destructive, rapid and quantitative evaluation of skin condition. It can be used for health assessment or classification of the skin condition, also can quantitatively evaluate the subtle improvement of skin condition after using skin care products or stage beauty.

  17. Evaluation of cyclone geometry and its influence on performance parameters by computational fluid dynamics (CFD

    Directory of Open Access Journals (Sweden)

    W. P. Martignoni

    2007-03-01

    Full Text Available Cyclone models have been used without relevant modifications for more than a century. Most of the attention has been focused on finding new methods to improve performance parameters. Recently, some studies were conducted to improve equipment performance by evaluating geometric effects on projects. In this work, the effect of cyclone geometry was studied through the creation of a symmetrical inlet and a volute scroll outlet section in an experimental cyclone and comparison to an ordinary single tangential inlet. The study was performed for gas-solid flow, based on an experimental study available in the literature, where a conventional cyclone model was used. Numerical experiments were performed by using CFX 5.7.1. The axial and tangential velocity components were evaluated using RSM and LES turbulence models. Results showed that these new designs can improve the cyclone performance parameters significantly and very interesting details were found on cyclone fluid dynamics properties using RSM and LES.

  18. Research of energy efficiency evaluation parameters for power quality control device based on IGBT module

    Science.gov (United States)

    Xu, Jieyan; Liu, Yang; Mao, Yongqiu; Chen, Zheng; Jia, Rongda; Zhao, Caiyi; Yang, Xi

    2017-01-01

    In this paper, the energy efficiency evaluation parameters for power quality control device based on IGBT modules have been discussed. First of all, energy consumption of the typical power quality control equipment, such as SVG, APF and MEC, under the rated conditions, have been analyzed to identify the main energy-consuming parts. Then, energy loss mechanism and energy saving path of IGBT module have been discussed. And the energy saving improvement direction of the power quality control equipment based on IGBT module is identified at the same time. At last, the applicable energy efficiency evaluation parameters for power quality control device have been selected, based on the research of the product performances for energy efficiency of power grid.

  19. Inter relationship between some routine semen evaluation parameters in Jersey X local hill cattle crossbred bulls

    Directory of Open Access Journals (Sweden)

    S. Kapoor

    2012-05-01

    Full Text Available The present study was conducted with an objective of establishing a relationship between various routine semen evaluation parameters. Work was conducted at Sperm Station Palampur, Himachal Pradesh, on the semen from five Jersey X local hill cattle crossbred breeding bulls. A total of 40 ejaculates (8 from each bull, were analysed at five different stages of processing namely post dilution, post equilibration, post thaw and after 1 and 2 hours incubation post thaw at 37°C for progressive motility, live dead count, reaction to hypo-osmotic solution, acrosomal integrity and gross morphological abnormalities. The results of the study revealed a highly significant (P<0.01 correlation between the various semen evaluation parameters except for the gross morphological abnormalities where there was a significant (P<0.05 negative correlation between the acrosomal integrity and gross morphological abnormalities.

  20. Evaluation of functional parameters in the occlusion of complete denture wearers before and after prosthetic treatment.

    Science.gov (United States)

    Joanna, Kuć; Teresa, Sierpińska; Maria, Gołębiewska

    2017-10-01

    The aim of the study was to evaluate functional parameters of the occlusion in complete denture wearers before and after prosthetic treatment. The sample used as the basis for the present study consisted of 50 healthy Caucasian patients (35 women and 15 men), aged from 44 to 86 years (mean=69.18±10), with a total deficiency of teeth. All patients received new complete dentures. Each patient underwent lateral radiograph with the presence of complete dentures, both before (initially existing dentures) and after the prosthetic treatment (new restorations). Cephalometric analysis was based on the Ricketts and McNamara criteria. In order to assess the functional parameters of the occlusion T-scan III analysis was conducted. The following parameters were measured: occlusion - and disclusion time. Statistically significant differences of functional parameters obtained before and 3 months after the treatment were noted in the whole study group. Both before and after therapy occlusion time was longer in women than in men. No statistically significant link was noted between functional parameters in occlusion and age of the patients, denture wearing time, and edentulous period. Some relationships were noted between occlusion time and cephalometric parameters associated with anterior facial height. Reconstruction of the surface of artificial teeth and vertical occlusal dimension affects the sustainability of parameters of occlusion and balance of forces in centric occlusion. The progressive shortening of occlusion time during the period of monitoring may be considered as a sign of progressive adaptation. Copyright © 2017 Japan Prosthodontic Society. Published by Elsevier Ltd. All rights reserved.

  1. Evaluation of uric acid levels, thyroid function, and anthropometric parameters in Japanese children with Down syndrome

    OpenAIRE

    Niegawa, Tomomi; Takitani, Kimitaka; Takaya, Ryuzo; Ishiro, Manabu; Kuroyanagi, Yuichi; Okasora, Keisuke; Minami, Yukako; Matsuda, Takuya; Tamai, Hiroshi

    2017-01-01

    Down syndrome, caused by trisomy 21, is characterized by congenital abnormalities as well as mental retardation. From the neonatal stage through adolescence, patients with Down syndrome often have several complications. Thus, it is important to attain knowledge of the prevalence of these comorbidities in children with Down syndrome. We, therefore, evaluated the biochemical data, thyroid function, and anthropometric parameters, and analyzed the association among them in Japanese children and e...

  2. Evaluation of parameters of color profile models of LCD and LED screens

    Science.gov (United States)

    Zharinov, I. O.; Zharinov, O. O.

    2017-12-01

    The purpose of the research relates to the problem of parametric identification of the color profile model of LCD (liquid crystal display) and LED (light emitting diode) screens. The color profile model of a screen is based on the Grassmann’s Law of additive color mixture. Mathematically the problem is to evaluate unknown parameters (numerical coefficients) of the matrix transformation between different color spaces. Several methods of evaluation of these screen profile coefficients were developed. These methods are based either on processing of some colorimetric measurements or on processing of technical documentation data.

  3. Determination and Evaluation of Climate Parameters Effecting Landscape Features of Bartin and its Environs

    Directory of Open Access Journals (Sweden)

    Bülent YILMAZ

    2006-01-01

    Full Text Available Landscape planning has aimed to protect the landscape and optimum use of its main components that are its natural and cultural features. Climate is a very important component to be identified natural landscape values. With done detailed analysis related to climate and evaluated these analysis using a measurable method can be produced optimum planning decisions. According to this study, Bartin, located in The West Black Sea Region, and its environs have been analyzed. Climate parameters related to study area such as rain, heat, humidity and wind was analyzed to have been used GIS software, ArcView 3.2. Obtained dataset have been evaluated used mathematical method.

  4. Evaluation of dosimetric parameters of a commercial semiconductor device in computed tomography

    Energy Technology Data Exchange (ETDEWEB)

    Magalhaes, C. M. S.; Sobrinho, M. C.; Souza, D. N. [Departmento de Fisica, Universidade Federale de Sergipe, Av. Marechal Rondon s/n, 49.100-000, Rosa Elze, Sao Cristovao-SE (Brazil); Santos, L. A. P. [Laboratorio de Instrumentacao Nuclear, Centro Regional de Ciencias Nucleares, Av. Professor Luiz Freire, 200, 50.740-540 Recife-PE (Brazil)

    2009-10-15

    Semiconductor devices have been widely used for dosimetry in radiotherapy and more recently in diagnostic radiology. In order to evaluate the performance of a phototransistor as a radiation detector in computed tomography (CT), some dosimetric parameters were evaluated, such as: repetitive, angular dependence, response for different tube potentials, dose and dose rate dependence. The irradiation was performed with the detector on the axis of rotation of a X-ray tube in CT scanner. The results showed that, making the necessary corrections, it is possible to use the phototransistor for dosimetry in tomography. (Author)

  5. Analysis and Experimental Evaluation of Power Line Transmission Parameters for Power Line Communication

    Science.gov (United States)

    Mlynek, P.; Misurec, J.; Koutny, M.; Fujdiak, R.; Jedlicka, T.

    2015-04-01

    The article describes a way of evaluating the power line channel frequency response and input impedance by means of the linear time-invariant (LTI) power line generator. Two possible methods are introduced for the calculation of primary parameters: the first method depends on the physical realization and physical dimension of the cable, and the second method is derived from the data provided by typical electrical cable manufacturers. Based on these methods, a comparison of transfer functions was made. This is followed by measurement evaluation and numerical verification on a simple topology

  6. Evaluation of ecological interface design for nuclear process control: situation awareness effects.

    Science.gov (United States)

    Burns, Catherine M; Skraaning, Gyrd; Jamieson, Greg A; Lau, Nathan; Kwok, Jordanna; Welch, Robin; Andresen, Gisle

    2008-08-01

    We determine whether an ecological interface display for nuclear power plant operations supports improved situation awareness over traditional and user-centered displays in a realistic environment. Ecological interface design (EID) has not yet been fully evaluated with real operators facing realistic scenarios. Ecological displays were evaluated alongside traditional and user-centered "advanced" displays in a full-scope nuclear power plant simulation. Licensed plant operators used the displays in realistic scenarios that either had procedural support or did not have procedural support. All three displays were evaluated for their ability to support operator situation awareness. A significant three-way interaction effect was observed on two independent measures of situation awareness. For both measures, ecological displays improved situation awareness in scenarios that did not have procedural support, primarily in the detection phases of those scenarios. No other pronounced effects appeared across both measures. The observed improvement was sufficiently large to suggest that EID could improve situation awareness in situations where procedures are unavailable. However, the EID displays did not lead to improved situation awareness in the other conditions of the evaluation, and participants using these displays occasionally underperformed on single measures of situation awareness. This suggests that the approach requires further development, particularly in integrating EID with procedural support. This research has important findings for the ongoing development of the EID approach, the design of industrial operator displays, and design to support situation awareness.

  7. Comparative Assessment of Nuclear and Nucleolar Cytochemical Parameters of Oral Epithelial Cells in Smokers and Non-Smokers by Methyl Green-Pyronin Staining

    Directory of Open Access Journals (Sweden)

    Shahrzad Adhami

    2012-09-01

    Full Text Available Introduction: A strong relationship exists between cigarette smoking and the development of oral squamous cell carcinoma. Smoking can significantly increase cellular proliferation. Nevertheless, there is little reference in literature to the cytological assessment of oral mucosa in this respect. Methods: Changes in nuclear and neucleolar cytomorphometric parameters such as diameter, surface, number and color intensity, in cytologic smears which were collected from normal buccal mucosa of 30 cigarette smokers and 30 non smokers, using methyl green-pyronin staining were studied. Results: Our findings attested to smoking as significant inductive factor in cytochemistry as well as morphologic changes. Conclusion: This technique is a valuable tool.

  8. The Contribution of Paleoseismology to Seismic Hazard Assessment in Site Evaluation for Nuclear Installations

    Science.gov (United States)

    Decker, Kurt; Guerrieri, Luca; Fukushima, Yoshimitsu

    2015-04-01

    In the framework of site evaluation/re-evaluation procedures for nuclear power plants (NPP), paleoseismology plays an essential role not only for Fault Displacement Hazard Assessment (FDHA) but also for Seismic Hazard Assessment (SHA). The relevance of paleoseismology is recommended in the reference IAEA Safety Guide (IAEA SSG-9) and has been dramatically confirmed in recent time especially after the accident at the Fukushima Daiichi NPP caused by the disastrous great Tohoku earthquake and tsunami occurred on 11 March 2011. After this event, the IAEA International Seismic Safety Center promoted a technical document aimed at encouraging and supporting Member States, especially from newcomer countries, to include paleoseismic investigations into the geologic database, highlighting the value of earthquake geology studies and paleoseismology for nuclear safety and providing standard methodologies to perform such investigations. In detail, paleoseismic investigations in the context of site evaluation of nuclear installations have the following main objectives: i) identification of seismogenic structures based on the recognition of effects of past earthquakes in the regional area; ii) improvement of the completeness of earthquake catalogs, through the identification and dating of ancient moderate to large earthquakes, whose trace has been preserved in the geologic records; iii) estimation of the maximum seismic potential associated with an identified seismogenic structure/source, typically on the basis of the amount of displacement per event (evaluable in paleoseismic trenches), as well as of the geomorphic and stratigraphic features interpretable as the cumulative effect of repeated large seismic events (concept of "seismic landscape"); iv) rough calibration of probabilistic seismic hazard assessment (PSHA), by using the recurrence interval of large earthquakes detectable by paleoseismic investigations, and providing a "reality check" based on direct observations of

  9. EVALUATION OF ANAEMIA USING RED CELL AND RETICULOCYTE PARAMETERS USING AUTOMATED HAEMATOLOGY ANALYSER

    Directory of Open Access Journals (Sweden)

    Vidyadhar Rao

    2016-06-01

    Full Text Available Use of current models of Automated Haematology Analysers help in calculating the haemoglobin contents of the mature Red cells, Reticulocytes and percentages of Microcytic and hypochromic Red cells. This has helped the clinician in reaching early diagnosis and management of Different haemopoietic disorders like Iron Deficiency Anaemia, Thalassaemia and anaemia of chronic diseases. AIM This study is conducted using an Automated Haematology Analyser to evaluate anaemia using the Red Cell and Reticulocyte parameters. Three types of anaemia were evaluated; iron deficiency anaemia, anaemia of long duration and anaemia associated with chronic disease and Iron deficiency. MATERIALS AND METHODS The blood samples were collected from 287 adult patients with anaemia differentiated depending upon their iron status, haemoglobinopathies and inflammatory activity. Iron deficiency anaemia (n=132, anaemia of long duration (ACD, (n=97 and anaemia associated with chronic disease with iron deficiency (ACD Combi, (n=58. Microcytic Red cells, hypochromic red cells percentage and levels of haemoglobin in reticulocytes and matured RBCs were calculated. The accuracy of the parameters was analysed using receiver operating characteristic analyser to differentiate between the types of anaemia. OBSERVATIONS AND RESULTS There was no difference in parameters between the iron deficiency group or anaemia associated with chronic disease and iron deficiency. The hypochromic red cells percentage was the best parameter in differentiating anaemia of chronic disease with or without absolute iron deficiency with a sensitivity of 72.7% and a specificity of 70.4%. CONCLUSIONS The parameters of red cells and reticulocytes were of reasonably good indicators in differentiating the absolute iron deficiency anaemia with chronic disease.

  10. INPRO Activities on Development of Advanced Tools to Support Judgment Aggregation for Comparative Evaluation of Nuclear Energy Systems

    Directory of Open Access Journals (Sweden)

    V. Kuznetsov

    2015-01-01

    Full Text Available This paper presents first results of the INPRO Collaborative Project on Key Indicators for Innovative Nuclear Energy Systems, which has the objective to develop guidance and tools for comparative evaluation of the status, prospects, benefits, and risks associated with development of innovative nuclear technologies for a more distant future. Presented results illustrate expedience of application of the multicriteria decision analysis methods, which are able to provide the added value to comparative assessment of nuclear energy systems. First, the paper presents a short review of the multicriteria decision analysis methods appropriate to support judgment aggregation within comparative evaluations of nuclear energy systems based on key indicators and highlights the methodology to perform such assessments. Second, a set of key indicators elaborated in the INPRO Collaborative Project on Global Architecture of Innovative Nuclear Energy Systems Based on Thermal and Fast Reactors Including a Closed Fuel Cycle (GAINS were evaluated for comparative evaluation of nuclear energy system evolution scenarios. Third, a numerical example is presented of application of the selected key indicators, methods, and tools for judgment aggregation in comparative assessment of the GAINS nuclear energy systems.

  11. Nuclear cosmo-chronology

    CERN Document Server

    Berkès, I

    2001-01-01

    The nuclear cosmo-chronology is based on radioactive dating which makes use of isotope or element pairs. In this paper we investigate the galaxy age estimations which can be deduced from meteorite analysis and solar or certain old stars light absorption spectra. These evaluations are based on theoretical models different then those implied in cosmology. They imply the calculation of heavy nuclei production in r process. The most significant difficulty of this calculation arises from the necessity of simultaneous evaluation of the production of a large number of nuclei what implies the difficult application of the microscopic nuclear models. Since the solar system is young as compared to the age of galaxy the evaluation based on element abundances (deduced from sun absorption spectra or meteorite analyses) requires a chemical evolution model of the galaxy. So far such an evaluation based on all the pairs of nuclear chronometers was not possible with a single set of parameters. Recent progress in estimating the...

  12. Dose equivalent evaluation in a nuclear medicine service; Avaliacao de doses equivalentes num servico de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Sales, C.P. de; Almeida, A. [Sao Paulo Univ., Ribeirao Preto, SP (Brazil). Faculdade de Filosofia, Ciencias e Letras. Dept. de Fisica e Matematica; Santos, M.C.P.S.; Ciocchi, N.F.; Brochi, M.A.C.; Souza, J.F. [Sao Paulo Univ. (USP-FMRP), Ribeirao Preto, SP (Brazil). Faculdade de Medicina. Centro de Ciencias das Imagens e Fisica Medica

    2004-07-01

    Nuclear Medicine occupational exposed workers equivalent doses, from official laboratories, were used in the dose analysis program developed using a Microsoft Excel program, in order to verify the Radiation Protection in the Nuclear Medicine Service of the Hospital das Clinicas da Faculdade de Medicina de Ribeirao Preto (HCFMRP-USP). From the results obtained, one can infer that: all the doses analyzed are lower than CNEN limit, the procedures to eluate 99m Tc and prepare radiopharmaceuticals deserve special attention from the Radioprotection, once higher doses belong to technicians and also, if a higher number of technicians and nursing auxiliaries could take turns, the equivalent doses would diminish. (author)

  13. Nuclear spectroscopy

    CERN Document Server

    Ajzenberg-Selove, Fay

    1960-01-01

    Nuclear Spectroscopy, Part B focuses on the ways in which experimental data may be analyzed to furnish information about nuclear parameters and nuclear models in terms of which the data are interpreted.This book discusses the elastic and inelastic potential scattering amplitudes, role of beta decay in nuclear physics, and general selection rules for electromagnetic transitions. The nuclear shell model, fundamental coupling procedure, vibrational spectra, and empirical determination of the complex potential are also covered. This publication is suitable for graduate students preparing for exper

  14. Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation

    Energy Technology Data Exchange (ETDEWEB)

    West, K.A.

    1988-11-01

    The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

  15. Nondestructive evaluation of plate type nuclear fuel elements during manufacturing stage using ultrasonic test method

    Energy Technology Data Exchange (ETDEWEB)

    Brito, Mucio Jose Drumond de; Ferraz, Wilmar Barbosa; Alencar, Donizete Anderson de; Silva Junior, Silverio Ferreira da [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Nucleo de Tecnologia do Combustivel], e-mail: mjdb@cdtn.br, e-mail: ferrazw@cdtn.br, e-mail: daa@cdtn.br, e-mail: silvasf@cdtn.br

    2009-07-01

    Structural discontinuities, such as cracks and bonding lacks at the core/cladding interface can be introduced in plate type nuclear fuel elements during the manufacturing stages, due to the mechanical and thermal processing conditions. They can reduce the performance of the nuclear fuel during its operational life or contribute to its premature failure. Plate type nuclear fuels (PTNF) consist of a core formed by a dispersion of UO{sub 2} into a metallic matrix, involved by a metallic cladding. Nondestructive testing methods such as eddy current, radiography and ultrasonic have been used to detect and monitoring discontinuities generated in the fuel's manufacturing stage, each one presenting advantages and limitations. The use of ultrasonic testing for this purpose presents two main difficulties: the small thickness of the plates as well as the presence of materials with different characteristics. The study described in this paper presents the methodology used in the evaluation of a prototype of PTNF by ultrasonic testing method, using different test techniques and transducers. The main results obtained and the next steps to be developed in this activity are discussed. (author)

  16. Concept evaluation of a nuclear design for electronuclear fuel production: evaluation of ORNL's proposed TMF--ENFP

    Energy Technology Data Exchange (ETDEWEB)

    Burns, T.J.; Bartine, D.E.; Renier, J.P.

    1979-05-01

    The use of an external neutron source, generated via an accelerator, represents a potential means for producing the fissile isotopes /sup 233/U and /sup 239/Pu. One promising accelerator-breeder concept employs a sodium-cooled ternary metal fertile blanket (/sup 239/Pu, /sup 238/U, and /sup 232/Th) surrounding a central column of sodium. A preliminary assessment of the neutronic characteristics and the relevant economic parameters for this system, designated the TMF--ENFP (Ternary Metal Fueled ElectroNuclear Fuel Producer) is described here. The rationale for selecting the particular configuration utilized was addressed from the standpoints of fissile production, heat generation, and target interaction. The basic assumption assumed a 300-mA beam of 1-GeV protons from the accelerator. A calculational model of the target blanket assembly was developed which met certain prespecified design limitations. A preliminary assessment of the nuclear performance, thermal-hydraulic, and economic parameters was made. For the latter, the use of the TMF--ENFP in conjunction with the denatured (/sup 233/U//sup 238/U) fuel cycle in both PWRs and CANDUs was considered. The basic accelerator-driven blanket concept requires a tradeoff between fissile production and the heat-removal capability. Moreover, the centrally located proton beam results in a significant gradient in the power density (Peak/Average approx. 2). Fissile production of the TMF--ENFP configuration considered was 5.8 kg/day of /sup 233/U. Such a production rate would support a maximum of 5.58 GW(e) of denatured PWR capacity (or alternatively 11.58 GW(e) of denatured CANDU capacity). The cost of the TMF--ENFP/thermal reactor system is judged to be competitive with current--generation LEU--PWRs operating from a > $80/lb U/sub 3/O/sub 8/ resource base.

  17. Predicting the long-term (137)Cs distribution in Fukushima after the Fukushima Dai-ichi nuclear power plant accident: a parameter sensitivity analysis.

    Science.gov (United States)

    Yamaguchi, Masaaki; Kitamura, Akihiro; Oda, Yoshihiro; Onishi, Yasuo

    2014-09-01

    Radioactive materials deposited on the land surface of Fukushima Prefecture from the Fukushima Dai-ichi Nuclear Power Plant explosion is a crucial issue for a number of reasons, including external and internal radiation exposure and impacts on agricultural environments and aquatic biota. Predicting the future distribution of radioactive materials and their fates is therefore indispensable for evaluation and comparison of the effectiveness of remediation options regarding human health and the environment. Cesium-137, the main radionuclide to be focused on, is well known to adsorb to clay-rich soils; therefore its primary transportation mechanism is in the form of soil erosion on the land surface and transport of sediment-sorbed contaminants in the water system. In this study, we applied the Soil and Cesium Transport model, which we have developed, to predict a long-term cesium distribution in the Fukushima area, based on the Universal Soil Loss Equation and simple sediment discharge formulas. The model consists of calculation schemes of soil erosion, transportation and deposition, as well as cesium transport and its future distribution. Since not all the actual data on parameters is available, a number of sensitivity analyses were conducted here to find the range of the output results due to the uncertainties of parameters. The preliminary calculation indicated that a large amount of total soil loss remained in slope, and the residual sediment was transported to rivers, deposited in rivers and lakes, or transported farther downstream to the river mouths. Most of the sediment deposited in rivers and lakes consists of sand. On the other hand, most of the silt and clay portions transported to river were transported downstream to the river mouths. The rate of sediment deposition in the Abukuma River basin was three times as high as those of the other 13 river basins. This may be due to the larger catchment area and more moderate channel slope of the Abukuma River basin

  18. A new tool for the search of nuclides with properties suitable for nuclear solid state physics based on the Evaluated Nuclear Structure Data Files

    Energy Technology Data Exchange (ETDEWEB)

    Nagl, M.A., E-mail: matthias@nagl.eu [II. Physikalisches Institut, Georg-August-Universität, Friedrich-Hund-Platz 1, 37077 Göttingen (Germany); Barbosa, M.B. [IFIMUP and IN-Institute of Nanoscience and Nanotechnology, Departamento de Física e Astronomia da Faculdade de Ciências da Universidade do Porto, Rua do Campo Alegre, 687, 4169-007 Porto (Portugal); CERN-EP, 1211 Geneva 23 (Switzerland); Vetter, U. [II. Physikalisches Institut, Georg-August-Universität, Friedrich-Hund-Platz 1, 37077 Göttingen (Germany); Correia, J.G. [CERN-EP, 1211 Geneva 23 (Switzerland); ITN, IST, Universidade Técnica de Lisboa, Estrada Nacional 10, 2686-953 Sacavém (Portugal); Centro de Física Nuclear da Universidade de Lisboa, Avenida Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Hofsäss, H.C. [II. Physikalisches Institut, Georg-August-Universität, Friedrich-Hund-Platz 1, 37077 Göttingen (Germany)

    2013-10-21

    A software tool for the displaying of nuclear decay schemes, the calculation of angular γ emission anisotropies, and the automated search for appropriate decay cascade properties based on the Evaluated Nuclear Structure Data Files (ENSDF) was created and published for free download. After a short introduction of this tool, candidate nuclides for time differential perturbed γ–γ angular correlation (TDPAC) measurements are presented. These candidates are grouped according to their parent nuclides’ half-life periods in groups for online, on-site, and off-site measurements. For all candidates angular correlation coefficients (also called anisotropy values) were computed and are shown alongside magnetic and quadrupole moments from the ENSDF database and other sources. An extension of the presented software for the search of nuclides for Mössbauer spectroscopy, Nuclear Resonant Scattering, and other methods is easily possible.

  19. A new tool for the search of nuclides with properties suitable for nuclear solid state physics based on the Evaluated Nuclear Structure Data Files

    Science.gov (United States)

    Nagl, M. A.; Barbosa, M. B.; Vetter, U.; Correia, J. G.; Hofsäss, H. C.

    2013-10-01

    A software tool for the displaying of nuclear decay schemes, the calculation of angular γ emission anisotropies, and the automated search for appropriate decay cascade properties based on the Evaluated Nuclear Structure Data Files (ENSDF) was created and published for free download. After a short introduction of this tool, candidate nuclides for time differential perturbed γ-γ angular correlation (TDPAC) measurements are presented. These candidates are grouped according to their parent nuclides’ half-life periods in groups for online, on-site, and off-site measurements. For all candidates angular correlation coefficients (also called anisotropy values) were computed and are shown alongside magnetic and quadrupole moments from the ENSDF database and other sources. An extension of the presented software for the search of nuclides for Mössbauer spectroscopy, Nuclear Resonant Scattering, and other methods is easily possible.

  20. Dacryocystorhinostomy ostium: parameters to evaluate and DCR ostium scoring

    Directory of Open Access Journals (Sweden)

    Ali MJ

    2014-12-01

    Full Text Available Mohammad Javed Ali,1 Alkis James Psaltis,2 Peter John Wormald2 1Dacryology Service, L V Prasad Eye Institute, Hyderabad, Telangana, India; 2Department of Surgery–Otorhinolaryngology, Head and Neck Surgery, The University of Adelaide, Adelaide, SA, Australia Aim: This study aims to provide a systematic protocol for the evaluation of a dacryocystorhinostomy (DCR ostium and to propose a scoring system to standardize the assessment.Methods: Retrospective evaluation of 125 consecutive lacrimal ostia post-DCR was performed. Medical records were screened, and photographs and videos were assessed to note the details of various ostial parameters. The major time points in evaluation were 4 weeks, 6 weeks, 3 months, and 6 months post-DCR. The ostia were defined and parameters like shape, size, location, and evolution of ostium were noted. Evaluation parameters were defined for internal common opening (ICO, ostium stents, and ostium granulomas. Ostium cicatrix and synechiae were graded based on their significance. Surgical success rates were computed and ostium characteristics in failed cases were studied.Results: A total of 125 ostia were evaluated on the aforementioned ostium parameters. Because five ostia showed a complete cicatricial closure with no recognizable features, the remaining 120 ostia were studied. The ostium location was anterior to the axilla of middle turbinate in 85.8% (103/120 of the cases. Moreover, 76.6% (92/120 of the ostia were circular to oval in shape, with a shallow base. The ostium size was >8×5 mm in 78.3% (94/120 of the cases. The ICO was found to be located in the central or paracentral basal area in 75.8% (91/120. The anatomical and functional success rates achieved were 96% and 93.6%, respectively. All the five cases with anatomical failures showed a complete cicatrization and the ICO movements were poor in all the three cases of functional failure.Conclusion: The article attempts to standardize the postoperative

  1. Applying Human Factors Evaluation and Design Guidance to a Nuclear Power Plant Digital Control System

    Energy Technology Data Exchange (ETDEWEB)

    Thomas Ulrich; Ronald Boring; William Phoenix; Emily Dehority; Tim Whiting; Jonathan Morrell; Rhett Backstrom

    2012-08-01

    The United States (U.S.) nuclear industry, like similar process control industries, has moved toward upgrading its control rooms. The upgraded control rooms typically feature digital control system (DCS) displays embedded in the panels. These displays gather information from the system and represent that information on a single display surface. In this manner, the DCS combines many previously separate analog indicators and controls into a single digital display, whereby the operators can toggle between multiple windows to monitor and control different aspects of the plant. The design of the DCS depends on the function of the system it monitors, but revolves around presenting the information most germane to an operator at any point in time. DCSs require a carefully designed human system interface. This report centers on redesigning existing DCS displays for an example chemical volume control system (CVCS) at a U.S. nuclear power plant. The crucial nature of the CVCS, which controls coolant levels and boration in the primary system, requires a thorough human factors evaluation of its supporting DCS. The initial digital controls being developed for the DCSs tend to directly mimic the former analog controls. There are, however, unique operator interactions with a digital vs. analog interface, and the differences have not always been carefully factored in the translation of an analog interface to a replacement DCS. To ensure safety, efficiency, and usability of the emerging DCSs, a human factors usability evaluation was conducted on a CVCS DCS currently being used and refined at an existing U.S. nuclear power plant. Subject matter experts from process control engineering, software development, and human factors evaluated the DCS displays to document potential usability issues and propose design recommendations. The evaluation yielded 167 potential usability issues with the DCS. These issues should not be considered operator performance problems but rather opportunities

  2. Methods of experimental settlement of contradicting data in evaluated nuclear data libraries

    Directory of Open Access Journals (Sweden)

    V. A. Libman

    2016-12-01

    Full Text Available The latest versions of the evaluated nuclear data libraries (ENDLs have contradictions concerning data about neutron cross sections. To resolve this contradiction we propose the method of experimental verification. This method is based on using of the filtered neutron beams and following measurement of appropriate samples. The basic idea of the method is to modify the suited filtered neutron beam so that the differences between the neutron cross sections in accordance with different ENDLs become measurable. Demonstration of the method is given by the example of cerium, which according to the latest versions of four ENDLs has significantly different total neutron cross section.

  3. Framework for evaluating the effectiveness of nuclear-safeguards systems. [Aggregated Systems Model (ASM)

    Energy Technology Data Exchange (ETDEWEB)

    Al-Ayat, R.A.; Judd, B.R.

    1981-10-20

    This paper describes an analytical tool for evaluating the effectiveness of safeguards that protect special nuclear material (SNM). The tool quantifies the effectiveness using several measures, including probabilities and expected times to detect and respond to malevolent attempts against the facility. These measures are computed for a spectrum of threats involving outsiders, insiders, collusion, falsification, and deceit. Overall system effectiveness is judged using performance indices aggregated over all threats. These indices can be used by designers and regulators when comparing costs and benefits of various safeguards. The framework is demonstrated with an example in which we assess vulnerabilities of a safeguards system and identify cost-effective design modifications.

  4. Evaluation of multivariate linear regression and artificial neural networks in prediction of water quality parameters.

    Science.gov (United States)

    Zare Abyaneh, Hamid

    2014-01-23

    This paper examined the efficiency of multivariate linear regression (MLR) and artificial neural network (ANN) models in prediction of two major water quality parameters in a wastewater treatment plant. Biochemical oxygen demand (BOD) and chemical oxygen demand (COD) as well as indirect indicators of organic matters are representative parameters for sewer water quality. Performance of the ANN models was evaluated using coefficient of correlation (r), root mean square error (RMSE) and bias values. The computed values of BOD and COD by model, ANN method and regression analysis were in close agreement with their respective measured values. Results showed that the ANN performance model was better than the MLR model. Comparative indices of the optimized ANN with input values of temperature (T), pH, total suspended solid (TSS) and total suspended (TS) for prediction of BOD was RMSE = 25.1 mg/L, r = 0.83 and for prediction of COD was RMSE = 49.4 mg/L, r = 0.81. It was found that the ANN model could be employed successfully in estimating the BOD and COD in the inlet of wastewater biochemical treatment plants. Moreover, sensitive examination results showed that pH parameter have more effect on BOD and COD predicting to another parameters. Also, both implemented models have predicted BOD better than COD.

  5. Evaluation of Durability Parameters of Concrete with Manufacture Sand and River Sand

    Science.gov (United States)

    Sangoju, Bhaskar; Ramesh, G.; Bharatkumar, B. H.; Ramanjaneyulu, K.

    2017-09-01

    Most of the states in our country have banned sand quarrying from the river beds, causing a scarcity of natural river sand for the construction sector. Manufacture sand (M-sand) is one of the alternate solutions to replace the river sand (R-sand) in concrete. The main aim of the present study is to evaluate the durability parameters of concrete with M-sand when compared to that of concrete with R-sand. Corrosion of reinforcement is one of the main deteriorating mechanisms of reinforced concrete due to the ingress of chloride ions or carbon-di-oxide. For comparative evaluation of durability parameters, accelerated tests such as Rapid Chloride Permeability Test, Rapid Chloride Migration Test and accelerated carbonation test were carried out on specimens of R-sand and M-sand. All tests were carried out after 90 days of casting. Test results reveal that the durability parameters of the concrete with M-sand in chloride induced environment is relatively better than that of concrete with R-sand and hence is recommended to use M-sand as a replacement to R-sand.

  6. Evaluation of Experimental Parameters in the Accelerated Aging of Closed-Cell Foam Insulation

    Energy Technology Data Exchange (ETDEWEB)

    Stovall, Therese K [ORNL; Vanderlan, Michael [ORNL; Atchley, Jerald Allen [ORNL

    2012-12-01

    The thermal conductivity of many closed-cell foam insulation products changes over time as production gases diffuse out of the cell matrix and atmospheric gases diffuse into the cells. Thin slicing has been shown to be an effective means of accelerating this process in such a way as to produce meaningful results. Efforts to produce a more prescriptive version of the ASTM C1303 standard test method led to the ruggedness test described here. This test program included the aging of full size insulation specimens for time periods of five years for direct comparison to the predicted results. Experimental parameters under investigation include: slice thickness, slice origin (at the surface or from the core of the slab), thin slice stack composition, product facings, original product thickness, product density, and product type. The test protocol has been completed and this report provides a detailed evaluation of the impact of the test parameters on the accuracy of the 5-year thermal conductivity prediction.

  7. Performance Evaluation and Parameter Optimization of SoftCast Wireless Video Broadcast

    Directory of Open Access Journals (Sweden)

    Dongxue Yang

    2015-08-01

    Full Text Available Wireless video broadcast plays an imp ortant role in multimedia communication with the emergence of mobile video applications. However, conventional video broadcast designs suffer from a cliff effect due to separated source and channel encoding. The newly prop osed SoftCast scheme employs a cross-layer design, whose reconstructed video quality is prop ortional to the channel condition. In this pap er, we provide the p erformance evaluation and the parameter optimization of the SoftCast system. Optimization principles on parameter selection are suggested to obtain a b etter video quality, o ccupy less bandwidth and/or utilize lower complexity. In addition, we compare SoftCast with H.264 in the LTE EPA scenario. The simulation results show that SoftCast provides a b etter p erformance in the scalability to channel conditions and the robustness to packet losses.

  8. Assessment of Some Immune Parameters in Occupationally Exposed Nuclear Power Plant Workers: Flow Cytometry Measurements of T Lymphocyte Subpopulations and Immunoglobulin Determination.

    Science.gov (United States)

    Gyuleva, Ilona Mihaylova; Penkova, Kalina Ivanova; Rupova, Ivanka Tankova; Panova, Delyana Yonkova; Djounova, Jana Nikolaeva

    2015-01-01

    A 10-year survey of immune status of nuclear power plant (NPP) workers was assessed by cellular and humoral immune parameters. The cumulative doses of NPP workers were in the range of 0.06 to 766.36 mSv. The results did not show significant deviations in the studied parameters of cellular and humoral immunity, but a tendency of elevated values in CD3+4+ helper inducers cells, especially its CD4+62L+ subpopulation, regulatory CD4+25+ cells, CD8+28+ cytotoxic subpopulation, and immunoglobulin M, was established. The observed trend of the above-mentioned parameters could be interpreted by assumption that while the adaptation processes are dominated with low prevalence of T-helper (Th) 1 immune response to cumulative doses less than 100 mSv, a switch to Th-2 response occurred at doses above 100 mSv. The impact of a number of other confounding factors on the immune system does not allow definitive conclusions about the direct radiation-induced changes in immune parameters.

  9. Evaluation of the Effect of Surgical Crown Lengthening on Periodontal Parameters

    Directory of Open Access Journals (Sweden)

    Farzane Vaziri

    2015-09-01

    Full Text Available Background: Surgical crown lengthening is needed for teeth with subgingival caries, fractured teeth, insufficient crown length, and deep subgingival margin of failed restorations. Since there is no agreement on the effects of crown lengthening surgery on gingival parameters, the purpose of this study was to evaluate periodontal parameters in patients who needed crown lengthening surgery. Methods: Twenty patients who had healthy periodontium and needed surgical crown lengthening were included in this study. After professional dental cleaning, gingival parameters including gingival index (GI, probing depth (PD, bone level (BL, and transsulcular probing (TSP were recorded in interproximal and keratinized gingiva (KG in mid buccal portion. The patients were evaluated one and three months after the surgery. Results: After one and three months of the surgery, the amount of PD reduced from 2.32 mm to 1.25 mm and 1.17 mm, respectively (P=0.001. The mean of BL reduction was 0.88 mm after one month (P=0.001, but there was no reduction between 1 month and 3 months. Amounts of KG at baseline andone month later were 4.2 mm and 2.9 mm, respectively (P=0.001, and remained at the same level up to three months. TSP significantly reduced (from 3.67 mm at baseline to 2.62 mm after 1 month, and to 2.27 mm after 3 months (P=0.001, P=0.005. Conclusion: The present  study suggests that in the presence of good oral hygiene, except BW (biological width, other parameters including PD, BL, KG, and TSP had significant changes after crown lengthening surgery in the period of 1 month and 3 months (P

  10. Effects of reduced food intake on the parameters of toxicity evaluation in dogs.

    Science.gov (United States)

    Morita, Junya; Izumi, Tomoko; Sunouchi, Mana; Arima, Kazunori; Tsutsumi, Shunsuke

    2015-08-01

    It is crucial to evaluate the variations in the toxicity parameters in experimental animals during the development of new drugs. Reduced food intake has been reported to have an impact on the toxicity parameters in rats; however, there are few reports of such studies in dogs. The aim of this study was to clarify the effects of reduced food intake on the general toxicity parameters and their reversibility in dogs. Male beagle dogs were fed 300 g/day of diet for 12 weeks in the control group, and 150 g/day for the first 8 weeks and 200 g/day for the subsequent 4 weeks in the low feeding group. During the following 4-week recovery period, the amount of feeding was set at 300 g/day. There were no clinical changes in any of the dogs. The low feeding group showed a body weight loss of 9.0%, 16.7% and 14.3% relative to the pre-test values at Week 4, 8 and 12, respectively. The following changes from the pre-test values and/or the control group in the examined parameters were observed in this group: decreased heart rate, prolonged PR interval on the ECG, decreased leukocyte count, and increased serum free fatty acid and γ-glutamyl transpeptidase levels. Significant changes of these parameters were not observed any more during the recovery period. This fact supports biological or physiological reaction to reduced food intake. These results are considered to represent useful information for toxicologists to distinguish between the direct effects of drugs and the changes attributable to reduced food intake.

  11. Evaluating the hematological and clinical-chemistry parameters of kratom (Mitragyna speciosa) users in Malaysia.

    Science.gov (United States)

    Singh, Darshan; Müller, Christian P; Murugaiyah, Vikneswaran; Hamid, Shahrul Bariyah Sahul; Vicknasingam, Balasingam K; Avery, Bonnie; Chear, Nelson Jeng Yeou; Mansor, Sharif Mahsufi

    2018-03-25

    Kratom (Mitragyna speciosa Korth.) from the Rubiaceae family is an indigenous tropical medicinal tree of Southeast Asia. Kratom leaves have been used for decades in Malaysia and Thailand in traditional context for its perceived vast medicinal value, and as a mild stimulant among manual labourers. Kratom consumption has been reported to cause side-effects in kratom users. To evaluate kratom's effects towards hematological and clinical-chemistry parameters among regular kratom users in Malaysia. A total of 77 subjects (n=58 regular kratom users, and n=19 healthy controls) participated in this cross-sectional study. All the surveys were conducted through face-to-face interview to elicit subject's socio-demographic characteristics and kratom use history. A full-blood test was also administered. Laboratory analysis was conducted using GC-MS to determine mitragynine content in the acquired kratom samples in order to relate mitragynine consumption with possible alterations in the blood parameters of kratom users. Findings showed that there were no significant differences in the hematological and clinical-chemistry parameters of traditional kratom users and healthy controls, except for HDL and LDL cholesterol values; these were found to be above the normal reference range for the former. Similarly, long-term kratom consumption (>5 years), and quantity of daily kratom use (≥3 ½ glasses; mitragynine content 76.3-114.8mg) did not appear to alter the hematological and biochemical parameters of kratom users. These data suggest that even long-term and heavy kratom consumption did not significantly alter the hematological and clinical-chemistry parameters of kratom users in a traditional setting. Copyright © 2017 Elsevier B.V. All rights reserved.

  12. Immediate diagnosis of ventriculits: evaluation of parameters independent of microbiological culture.

    Science.gov (United States)

    Boeer, Klas; Vogelsang, Heinz; Deufel, Thomas; Pfister, Wolfgang; Kiehntopf, Michael

    2011-09-01

    Generally accepted reference values in CSF diagnostics are not valid in cerebrospinal fluid (CSF) containing large amounts of blood. Residual blood may obscure ventriculitis as diagnostics largely depend on parameters such as cell count, lactic acid and total protein measurement. We sought to improve the diagnostics by evaluating a cytokine panel and soluble CD62L as markers of ventriculitis. In addition, we tested an algorithm of established parameters to predict ventriculitis in a specific patient collective. Analysis was performed on ventricular CSF samples from 50 consecutive patients. Gram staining, microbiological culture, total cell count, total protein and CD62L expression on neutrophil granulocytes were analysed immediately. Cytokines and soluble CD62L were measured by flow cytometry. Positive culture was detected in ten patients. Of all parameters tested only IL1-beta, IL8 and CD62L on neutrophils were significantly different between culture-positive and -negative patients. The highest predictive value was obtained when analysing IL1-beta. The predictive value of a parameter combination (IL6 in CSF, C-reactive protein and leukocytes in periphereal blood) was comparable to IL1-beta. Half of the patients in this analysis were identified as culture positive because of the lack of inflammatory response. IL1-beta and perhaps also IL8 provide very good analytical performance when looking for ventriculitis in patients with residual blood in CSF. Turn-around time is short, and results could be reported within 1 h for 24 h a day. In some patients application of glucocorticoids may result in restricted inflammatory response. Even in these patients IL1-beta provides a reliable parameter for the immediate diagnosis of ventriculitis.

  13. Evaluating Safeguards Benefits of Process Monitoring as compared with Nuclear Material Accountancy

    Energy Technology Data Exchange (ETDEWEB)

    Humberto Garcia; Wen-Chiao Lin; Reed Carlson

    2014-07-01

    This paper illustrates potential safeguards benefits that process monitoring (PM) may have as a diversion deterrent and as a complementary safeguards measure to nuclear material accountancy (NMA). This benefit is illustrated by quantifying the standard deviation associated with detecting a considered material diversion scenario using either an NMA-based method or a PM-based approach. To illustrate the benefits of PM for effective safeguards, we consider a reprocessing facility. We assume that the diversion of interest for detection manifests itself as a loss of Pu caused by abnormally operating a dissolver for an extended period to accomplish protracted diversion (or misdirection) of Pu to a retained (unconditioned) waste stream. For detecting the occurrence of this diversion (which involves anomalous operation of the dissolver), we consider two different data evaluation and integration (DEI) approaches, one based on NMA and the other based on PM. The approach based on PM does not directly do mass balance calculations, but rather monitors for the possible occurrence of anomaly patterns related to potential loss of nuclear material. It is thus assumed that the loss of a given mass amount of nuclear material can be directly associated with the execution of proliferation-driven activities that trigger the occurrence of an anomaly pattern consisting of series of events or signatures occurring at different unit operations and time instances. By effectively assessing these events over time and space, the PM-based DEI approach tries to infer whether this specific pattern of events has occurred and how many times within a given time period. To evaluate the goodness of PM, the 3 Sigma of the estimated mass loss is computed under both DEI approaches as function of the number of input batches processed. Simulation results are discussed.

  14. Evaluation of Corneal Topography and Biomechanical Parameters after Use of Systemic Isotretinoin in Acne Vulgaris

    Directory of Open Access Journals (Sweden)

    Yusuf Yildirim

    2014-01-01

    Full Text Available Purpose. We report the effect of isotretinoin on corneal topography, corneal thickness, and biomechanical parameters in patients with acne vulgaris. Method. Fifty-four eyes of 54 patients who received oral isotretinoin for treatment of acne vulgaris were evaluated. All patients underwent a corneal topographical evaluation with a Scheimpflug camera combined with Placido-disk (Sirius, ultrasonic pachymetry measurements, and corneal biomechanical evaluation with an ocular response analyzer at baseline, in the 1st, 3rd, and 6th months of treatment, and 6 months after isotretinoin discontinuation. Results. The thinnest corneal thickness measured with Sirius differed significantly in the 1st, 3rd, and 6th months compared with the baseline measurement; there was no significant change in ultrasonic central corneal thickness measurements and biomechanical parameters (corneal hysteresis and corneal resistance factor throughout the study. Average simulated keratometry and surface asymmetry index increased significantly only in the first month of treatment according to the baseline. All changes disappeared 6 months after the end of treatment. Conclusion. Basal tear secretion and corneal morphologic properties were significantly influenced during the systemic isotretinoin treatment and the changes were reversible after discontinuation. No statistical important biomechanical differences were found to be induced by isotretinoin.

  15. [Analysis of the parameters, traditional or not, for the evaluation of the metabolic acidosis].

    Science.gov (United States)

    Urso, Caterina; Brucculeri, Salvatore; Carollo, Caterina; Caimi, Gregorio

    2017-01-01

    Despite huge progress in acidbase knowledge, several confusing, irrational and controversial issues still remain. Acid-base disturbances have been usually evaluated with the traditional Henderson-Hasselbach method and with BE evaluation that seem inadequate since they define the magnitude of metabolic acidosis rather than its cause. Some studies have shown that the traditional approach is often not able to highlight the complicated acid-base disorders in critically ill patients; in these subjects, the possibility to identify tissue acids could offer a greater prognostic value than the evaluation of traditional parameters. An alternative approach is the Stewarts physiochemical method that defines the aetiology of a metabolic acidosis by quantifying the tissue acids. But the clinical utility of this method is limited due to its mathematical complexity. Therefore, some parameters of simplification were proposed in order to allow greater clinical applicability of this system. Specifically, it was observed that in the presence of metabolic acidosis, the chloride/sodium ratio (Cl-/Na+ ratio) or the sodium-chloride difference (DiffNa-Cl) would be useful indicators of the presence of unmeasured anions (UMA) and/or lactate.

  16. [Evaluation of fructosamine as a parameter of blood glucose control in diabetic pregnant women].

    Science.gov (United States)

    Feitosa, Alina Coutinho Rodrigues; Andrade, Flávio Silva

    2014-10-01

    To evaluate the alternative parameters to monitor glycemia in pregnant women with diabetes studying the relationship between fructosamine testing and self monitoring of blood glucose in pregnant women with diabetes. Serum fructosamine levels and the self monitoring of blood glucose over 14 days before the collection of fructosamine were evaluated in 47 diabetic pregnant women. Seventy-one fructosamine levels and 2,238 glucose measurements (CGs) were analysed. Levels of fructosamine correlated with high blood glucose index (HBGI) and the standard deviation of glycemias (r = 0.28; p = 0.021 and r = 0.26; p = 0.03, respectively). The comparison between the mothers of the newborns with appropriated or large birthweight and those who gave birth to small newborns for their gestational age (SGA) showed that the latter had a lower glycemic mean (105 vs. 114 and 119 mg/dL), a higher low blood glucose index (5.8 vs. 1.3 and 0.7) and a higher percentage of hyperglycemias (11 vs. 0 and 0%) even when the fructosamine falls within the reference values (242 vs. 218 and 213 μmol/l). The levels of fructosamine can be used as further parameter to aid self monitoring of blood glucose to evaluate hyperglycemias and glycemic variability, however, this can underestimate hypoglycemias in pregnant women carrying small-for-gestational age fetuses.

  17. Surface Irregularity Factor as a Parameter to Evaluate the Fatigue Damage State of CFRP

    Directory of Open Access Journals (Sweden)

    Pablo Zuluaga-Ramírez

    2015-11-01

    Full Text Available This work presents an optical non-contact technique to evaluate the fatigue damage state of CFRP structures measuring the irregularity factor of the surface. This factor includes information about surface topology and can be measured easily on field, by techniques such as optical perfilometers. The surface irregularity factor has been correlated with stiffness degradation, which is a well-accepted parameter for the evaluation of the fatigue damage state of composite materials. Constant amplitude fatigue loads (CAL and realistic variable amplitude loads (VAL, representative of real in- flight conditions, have been applied to “dog bone” shaped tensile specimens. It has been shown that the measurement of the surface irregularity parameters can be applied to evaluate the damage state of a structure, and that it is independent of the type of fatigue load that has caused the damage. As a result, this measurement technique is applicable for a wide range of inspections of composite material structures, from pressurized tanks with constant amplitude loads, to variable amplitude loaded aeronautical structures such as wings and empennages, up to automotive and other industrial applications.

  18. On the evaluation of Pierce parameters C and Q in a traveling wave tube

    Science.gov (United States)

    Simon, D. H.; Wong, P.; Chernin, D.; Lau, Y. Y.; Hoff, B.; Zhang, P.; Dong, C. F.; Gilgenbach, R. M.

    2017-03-01

    A study of an exactly solvable model of a traveling wave tube (TWT) shows that Pierce gain parameter C and space charge parameter Q generally depend on wavenumber k in addition to frequency ω. The choice of k at which C and Q are evaluated may strongly affect their values and, consequently, the values of the small signal gain obtained from 3- and 4-wave Pierce theory. In order to illustrate this effect, we calculate the spatial amplification rate, ki, from the exact dispersion relation for a dielectric TWT model which is exactly solvable. We compare this exact value of ki with approximate values obtained from Pierce's classical 3-wave and 4-wave dispersion relations, obtained by making various assumptions on k in the evaluation of C and Q. We find that the various ways to approximate C and Q will have a significant influence on the numerical values of ki. For our dielectric TWT example, Pierce's 4-wave TWT dispersion relation generally yields the most accurate values of ki if Q is evaluated for k = ω/v0, where v0 is the beam velocity, and if the complete frequency and wavelength dependence of C is retained. Pierce's 3-wave theory also yields accurate values of ki using a different form of Q from the 4-wave theory. The implications of this result for TWT design are explored.

  19. The development of design technology on the safety parameter display system for the operability improvement of the nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Young Joon; Choi, Hae Yoon; Ahn, Jang Sun; Lee, Tae Woo; Lee, Ki Won; Kim, Kil Kon; Baek, Seong Min; Sul, Young Sil [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-31

    The purpose of this study is, basically, threefold. Firstly, through detailed comparison, the difference between the safety parameters used in the EPG and CFMS is analyzed. Furthermore, to anticipate and extrapolate the problems that might be encountered when developing the CFMS system that utilizes safety parameters consistent with that of the EPG. Secondly, the setpoint analysis of the CFMS alarm algorithm was done for there is a possibility of causing spurious alarms since the alarm setpoint of the YGN 3,4 CFMS is not reflective of the plant operating conditions nor accident progression. Lastly, the analysis of the success path for each accident was done to help operator in mitigating the accident by using the pictorial path of the success path during an accident condition. Moreover, in this analysis, the contents of the concerns that KINS raised regarding the YGN 3,4 SPDS has been addressed from the designer`s perspective. 33 figs., 16 refs. (Author) .new.

  20. ENDF-102 DATA FORMATS AND PROCEDURES FOR THE EVALUATION NUCLEAR DATA FILE ENDF-6.

    Energy Technology Data Exchange (ETDEWEB)

    MCLANE,V.

    2001-05-15

    The Evaluated Nuclear Data File (ENDF) formats and libraries are decided by the Cross Section Evaluation Working Group (CSEWG), a cooperative effort of national laboratories, industry, and universities in the U.S. and Canada, and are maintained by the National Nuclear Data Center (NNDC). Earlier versions of the ENDF format provided representations for neutron cross sections and distributions, photon production from neutron reactions, a limited amount of charged-particle production from neutron reactions, photo-atomic interaction data, thermal neutron scattering data, and radionuclide production and decay data (including fission products). Version 6 (ENDF-6) allows higher incident energies, adds more complete descriptions of the distributions of emitted particles, and provides for incident charged particles and photonuclear data by partitioning the ENDF library into sub-libraries. Decay data, fission product yield data, thermal scattering data, and photo-atomic data have also been formally placed in sub-libraries. In addition, this rewrite represents an extensive update to the Version V manual.

  1. Choice of method - evaluation of strategies and systems for disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    2010-10-15

    This report deals with the question of how the Swedish spent nuclear fuel is to be disposed of. What are the requirements? What are the alternatives? In the main chapter of the report, an evaluation is made of the KBS-3 method compared with other strategies and systems for final disposal of spent nuclear fuel. An appendix to the report presents in general terms how the KBS-3 method has developed from the end of the 1970s up to today. The report is one of a number of supporting documents for SKB's applications for construction and operation of the final repository for spent nuclear fuel. In parallel with and as a basis for the present report, SKB has prepared the reports Principer, strategier och system foer slutligt omhaendertagande av anvaent kaernbraensle ('Principles, strategies and systems for final disposal of spent nuclear fuel') /Grundfelt 2010a/, Jaemfoerelse mellan KBS-3-metoden och deponering i djupa borrhaal foer slutlig foervaring av anvaent kaernbraensle ('Comparison between the KBS-3 method and deposition in deep boreholes for final disposal of spent nuclear fuel') /Grundfelt 2010b/ and Utvecklingen av KBS-3- metoden. Genomgaang av forskningsprogram, saekerhetsanalyser, myndighetsgranskningar samt SKB:s internationella forskningssamarbete ('Development of the KBS-3 method. Review of research programmes, safety assessments, regulatory reviews and SKB's international research cooperation') /SKB 2010a/. The reports are in Swedish, but contain summaries in English. The first report is an update of the comprehensive account of alternative methods presented by SKB in 2000. The second report presents a comparison between the KBS-3 method and the Deep Boreholes concept, plus a status report on research and development in the area of Deep Boreholes. The last report describes how the KBS-3 method has been developed from the end of the 1970s up to today. It further describes how the method has been further developed and

  2. Current and capacitance measurements as a fast diagnostic tool for evaluation of semiconductor parameters

    CERN Document Server

    Kemmer, J; Krause, N; Krieglmeyer, C; Yang Yi

    2000-01-01

    A fast qualitative method is described for evaluation of semiconductor parameters by analyzing both the capacitance/voltage (C/V) and current/voltage (I/V) characteristics of pn- or Schottky-diodes, which are fabricated on the material under investigation. The method is applied for measurement of recombination and generation lifetimes of minority charge carriers and for determination of doping profiles and distribution of active generation/recombination (G/R) centers after irradiation with Am-alpha particles and deep phosphorus implantation. Measurements on epitaxial silicon result in doping profiles and distributions of active impurities within the epi-layer.

  3. Gingival and dental parameters in the evaluation of aesthetic characteristics of fixed restorations (II

    Directory of Open Access Journals (Sweden)

    Obradović-Đuričić Kosovka

    2005-01-01

    Full Text Available This paper is a continuing evaluation of dental and facial parameters in the estimation of aesthetic characteristic of fixed restorations. First of all, attention is paid to the phenomenon describing the tooth tissue's characteristics (transiucency, opalescence, and transparency. The paper also discusses tooth color as a special occurrence, the position of the lower lip line as well as the symmetry of the smile. In addition to these fundamental objective criteria, the paper also deals with subjective criteria (tooth arrangement and position, variation in tooth form, and relative crown length, which play a part in the successful aesthetic integration of fixed restorations.

  4. Experimental study for quantative aging evaluation of epoxy liner in BWR nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Na, H. S. [KEPRI, Taejon (Korea, Republic of); Song, Y. C.; Kim, N. Y. [Korea Univ. of Educational Technology, Chonnon (Korea, Republic of)

    2001-10-01

    The purpose of this study is an experimental approach to quantitatively evaluate the aging status of epoxy coating onto containment structure in BWR nuclear power plant. Based on accelerated aging experiment for 64 days, adhesion test was performed to evaluate an physical bonding. To compare with adhesion data, both impedance data by UT and data by thermal gravimetric analysis were obtained during experiment. At almost 50% of adhesion force decrease, it was identified that aging phenamena of epoxy such as pine hole, blistering was discovered. Coating to establish aging status of epoxy, relations among three kinds of different data were analyze. By compatibility of these data, physical aging situation of as-built epoxy coating was figured out. The possibility to develop new methodology of time-dependent aging status on epoxy coating was identified.

  5. EARLY-STAGE DESIGN AND EVALUATION FOR NUCLEAR POWER PLANT CONTROL ROOM UPGRADES

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Jeffrey C. Joe; Thomas A. Ulrich; Roger T. Lew

    2015-03-01

    As control rooms are modernized with new digital systems at nuclear power plants, it is necessary to evaluate operator performance with these systems as part of a verification and validation process. While there is regulatory and industry guidance for some modernization activities, there are no well defined standard processes or predefined metrics available for assessing what is satisfactory operator interaction with new systems, especially during the early design stages. This paper proposes a framework defining the design process and metrics for evaluating human system interfaces as part of control room modernization. The process and metrics are generalizable to other applications and serve as a guiding template for utilities undertaking their own control room modernization activities.

  6. A method to evaluate the communication quality of operators in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Hwan; Park, Jin Kyun

    2009-12-15

    The communication problems have been regarded as one of the biggest causes in trouble in many industries. This led to extensive research on communication as a part of human error analysis. The results of existing researches have revealed that maintaining a good quality of communication is essential to secure the safety of a large and complex process system. In this report, we suggested a method to measure the quality of communication during off-normal situation in main control room of nuclear power plants. It evaluates the cosine similarity that is a measure of sentence similarity between two operators by finding the cosine of the angle between them. To check the applicability of the method to evaluate communication quality, we compared the result of communication quality analysis with the result of operation performance that was performed by operators under simulated environment.

  7. A possible parameter for gait clinimetric evaluation in Parkinson’s disease patients

    Science.gov (United States)

    Lescano, C. N.; Rodrigo, S. E.; Christian, D. A.

    2016-04-01

    The strength and usefulness of a rating scale for describing disease evolution relies on the accurate determination of variations representing clinically relevant changes. In this sense, the habitually used Hoehn-Yahr (HY) Scale for Parkinson Disease (PD) in its modified version distinguishes between the 2 and 2.5 stages to explain if the bilateral involvement is or is not accompanied by body balance impairment. Nevertheless, this scaling does not allow for differentiating the symptoms and signs associated with each stage accurately. Considering this difference, this work aims at analyzing some gait parameters-stance and swing phase times and magnitude of the vertical component of ground reaction force during the gait cycle-of PD patients classified as HY=2 and HY=2.5 in contrast with healthy subjects (HY=0), with the purpose of assessing whether there is a statistically significant difference among all these HY categories. For all gait parameters evaluated, the results indicated significant differences between HY=0 and HY=2.5. However, only the magnitude of the vertical component of ground reaction force presented relevant differences between HY=2 and 2.5. As expected, therefore, these results show the potential of such parameter to clinimetrically identify the level of gait impairment/disability in PD patients on the Hoehn-Yahr Scale.

  8. Evaluation of ACE inhibitors lipophilicity using in silico and chromatographically obtained hydrophobicity parameters

    Directory of Open Access Journals (Sweden)

    Odović Jadranka V.

    2013-01-01

    Full Text Available The aim of this study was to compare different calculation methods to determine lipophilicity, expressed as logP value, of seven ACE inhibitors (enalapril, quinapril, fosinopril, lisinopril, cilazapril, ramipril, and benazapril with significantly different structure. Experimentally determined n-octanol/water partition coefficients, logPO/W values, were obtained from relevant literature. The correlations between all collected logP values were studied and the best agreements between calculated logP and experimentally determined logPO/W values, were observed for KOWWINlogP or MilogP values (r = 0.999 or r = 0.974, respectively. The correlations between all collected logP values and chromatographically (reversed-phase thin-layer chromatography obtained hydrophobicity parameters, RM0 and C0, were established. The good correlations (r > 0.90 were obtained in the majority of relationships. The KOWWINlogP was established as the most suitable hydrophobicity parameter of investigated group of ACE inhibitors with r = 0.981 for correlation with RM0 and r = 0.977 for correlation with C0 parameters (water-methanol mobile phase. Using multiple linear regressions, it was established that application of two selected logP, calculated by different mathematical approaches, led to very good correlation due to the benefits of both calculation methods. The good relationships indicate that the computed logP, with careful selection of method calculation, can be useful in ACE inhibitors lipophilicity evaluation, as high-throughput screening technique.

  9. Evaluation of poly(vinylpyrrolidone) and collagen by Low Field Nuclear Magnetic Resonance Spectroscopy; Avaliacao da polivinilpirrolidona e do colageno por ressonancia magnetica nuclear de baixo campo

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Paula de M.; Tavares, Maria I.B. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Inst. de Macromoleculas Professora Eloisa Mano]. E-mail: pmcosta@ima.ufrj.br

    2005-07-01

    Blends of natural and synthetic polymers represent a new class of materials with better mechanical properties and biocompatibility than those of the single components. Collagen and poly(vinylpyrrolidone) are well known for their important biological properties. The blending of collagen with poly(vinylpyrrolidone) makes it possible to obtain new materials in which strong interactions between the synthetic and biological components occur. Do to the excellent biocompatibility of these polymers, this blend has been much studied intending biomedical applications. And a one technique that can provide important information on molecular mobility, compatibility and even evaluate the interactions that can occur with these polymers is the Low Field Nuclear Magnetic Resonance Spectroscopy. Thus, the purpose of this work is to evaluate collagen and poly(vinylpyrrolidone) by Low Field Nuclear Magnetic Resonance Spectroscopy. From the values of relaxation times obtained, we can conclude that these materials have different interactions, and different mobility domains, confirming the heterogeneity and complexity of these materials. (author)

  10. Innovative Nuclear Energy Systems: State-of-the Art Survey on Evaluation and Aggregation Judgment Measures Applied to Performance Comparison

    Directory of Open Access Journals (Sweden)

    Vladimir Kuznetsov

    2015-04-01

    Full Text Available This paper summarizes the experience gained in the application of multi-criteria decision making and uncertainty treatment methods to a comparative assessment of nuclear energy systems and related nuclear fuel cycles. These judgment measures provide a means for comprehensive evaluation according to different conflicting criteria, such as costs, benefits and risks, which are inevitably associated with the deployment of advanced technologies. Major findings and recommendations elaborated in international and national projects and studies are reviewed and discussed. A careful analysis is performed for multi-criteria comparative assessment of nuclear energy systems and nuclear fuel cycles on the basis of various evaluation and screening results. The purpose of this paper is to discuss the lessons learned, to share the identified solutions, and indicate promising future directions.

  11. Computational code in atomic and nuclear quantum optics: Advanced computing multiphoton resonance parameters for atoms in a strong laser field

    Science.gov (United States)

    Glushkov, A. V.; Gurskaya, M. Yu; Ignatenko, A. V.; Smirnov, A. V.; Serga, I. N.; Svinarenko, A. A.; Ternovsky, E. V.

    2017-10-01

    The consistent relativistic energy approach to the finite Fermi-systems (atoms and nuclei) in a strong realistic laser field is presented and applied to computing the multiphoton resonances parameters in some atoms and nuclei. The approach is based on the Gell-Mann and Low S-matrix formalism, multiphoton resonance lines moments technique and advanced Ivanov-Ivanova algorithm of calculating the Green’s function of the Dirac equation. The data for multiphoton resonance width and shift for the Cs atom and the 57Fe nucleus in dependence upon the laser intensity are listed.

  12. Impact parameter dependence of pion ratio in probing the nuclear symmetry energy using heavy-ion collisions

    OpenAIRE

    Wei, Gao-Feng; He, Guo-Qiang; Cao, Xin-Wei; Lu, Yi-Xin

    2016-01-01

    The impact parameter dependence of \\rpi ratio is examined in heavy-ion collisions at 400MeV/nucleon within a transport model. It is shown that the sensitivity of \\rpi ratio on symmetry energy shows a transition from central to peripheral collisions, i.e., the stiffer symmetry energy leads to a larger \\rpi ratio in peripheral collisions while the softer symmetry energy always leads this ratio to be larger in central collisions. After checking the kinematic energy distribution of \\rpi ratio, we...

  13. Deuteron nuclear data for the design of accelerator-based neutron sources: Measurement, model analysis, evaluation, and application

    Science.gov (United States)

    Watanabe, Yukinobu; Kin, Tadahiro; Araki, Shouhei; Nakayama, Shinsuke; Iwamoto, Osamu

    2017-09-01

    A comprehensive research program on deuteron nuclear data motivated by development of accelerator-based neutron sources is being executed. It is composed of measurements of neutron and gamma-ray yields and production cross sections, modelling of deuteron-induced reactions and code development, nuclear data evaluation and benchmark test, and its application to medical radioisotopes production. The goal of this program is to develop a state-of-the-art deuteron nuclear data library up to 200 MeV which will be useful for the design of future (d,xn) neutron sources. The current status and future plan are reviewed.

  14. General Guidelines on Criteria for Adoption or Rejection of Evaluated Libraries and Data by the Nuclear Data Team

    Energy Technology Data Exchange (ETDEWEB)

    Neudecker, Denise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Conlin, Jeremy Lloyd [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gray, Mark Girard [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McCartney, Austin Paul [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Parsons, Donald Kent [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); White, Morgan Curtis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-04-12

    This memo contains general guidelines on what documentation and tools need to be in place as well as format and data testing requirements such that evaluated nuclear data sets or entire libraries can be adopted by the nuclear data team. Additional requirements beyond this memo might apply for specific nuclear data observables. These guidelines were established based on discussions between J.L. Conlin, M.G. Gray, A.P. McCartney, D. Neudecker, D.K. Parsons and M.C. White.

  15. Approximate parameter inference in systems biology using gradient matching: a comparative evaluation.

    Science.gov (United States)

    Macdonald, Benn; Niu, Mu; Rogers, Simon; Filippone, Maurizio; Husmeier, Dirk

    2016-07-15

    A challenging problem in current systems biology is that of parameter inference in biological pathways expressed as coupled ordinary differential equations (ODEs). Conventional methods that repeatedly numerically solve the ODEs have large associated computational costs. Aimed at reducing this cost, new concepts using gradient matching have been proposed, which bypass the need for numerical integration. This paper presents a recently established adaptive gradient matching approach, using Gaussian processes (GPs), combined with a parallel tempering scheme, and conducts a comparative evaluation with current state-of-the-art methods used for parameter inference in ODEs. Among these contemporary methods is a technique based on reproducing kernel Hilbert spaces (RKHS). This has previously shown promising results for parameter estimation, but under lax experimental settings. We look at a range of scenarios to test the robustness of this method. We also change the approach of inferring the penalty parameter from AIC to cross validation to improve the stability of the method. Methodology for the recently proposed adaptive gradient matching method using GPs, upon which we build our new method, is provided. Details of a competing method using RKHS are also described here. We conduct a comparative analysis for the methods described in this paper, using two benchmark ODE systems. The analyses are repeated under different experimental settings, to observe the sensitivity of the techniques. Our study reveals that for known noise variance, our proposed method based on GPs and parallel tempering achieves overall the best performance. When the noise variance is unknown, the RKHS method proves to be more robust.

  16. Evaluation of critical process parameters for intra-tablet coating uniformity using terahertz pulsed imaging.

    Science.gov (United States)

    Brock, Daniela; Zeitler, J Axel; Funke, Adrian; Knop, Klaus; Kleinebudde, Peter

    2013-11-01

    The purpose of this study was to evaluate the intra-tablet coating uniformity and the identification of critical process parameters in an active pan coating process using terahertz pulsed imaging (TPI). A design of experiments (DoE) was performed with drum load, drum speed, spray rate, run duration and spray pressure as factors. Different measures of intra-tablet uniformity were investigated: the average thickness on the individual tablet faces, spatial variation in layer thickness over the tablet surface, and the coefficient of variation (CV(intra)). Data analysis revealed that the process parameters in the investigated parameter space had hardly any influence on the difference in layer thickness of the tablet faces and centre band. No increase or decrease in layer thickness--as described in the literature--was found towards the edges of the tablet face. In overwetted process conditions a higher layer thickness at the centre band edges could be observed. Still, the highest variability in coating thickness was found along the circumference of the centre band rather than the height. In general, higher CV(intra) of layer thickness were found on the centre bands in comparison with the tablet faces. The analysis of the DoE model revealed that the run duration had the highest influence on the CV(intra) on the tablet faces. TPI showed high potential in the assessment of intra-tablet uniformity and layer thickness distributions over the whole tablet surface. It was successfully used to identify critical process parameters regarding intra-tablet coating uniformity. Copyright © 2013 Elsevier B.V. All rights reserved.

  17. Numerical Evaluation of Parameter Correlation in the Hartmann-Tran Line Profile

    Science.gov (United States)

    Adkins, Erin M.; Reed, Zachary; Hodges, Joseph T.

    2017-06-01

    The partially correlated quadratic, speed-dependent hard-collision profile (pCqSDHCP), for simplicity referred to as the Hartmann-Tran profile (HTP), has been recommended as a generalized lineshape for high resolution spectroscopy. The HTP parameterizes complex collisional effects such as Dicke narrowing, speed dependent narrowing, and correlations between velocity-changing and dephasing collisions, while also simplifying to simpler profiles that are widely used, such as the Voigt profile. As advanced lineshape profiles are adopted by more researchers, it is important to understand the limitations that data quality has on the ability to retrieve physically meaningful parameters using sophisticated lineshapes that are fit to spectra of finite signal-to-noise ratio. In this work, spectra were simulated using the HITRAN Application Programming Interface (HAPI) across a full range of line parameters. Simulated spectra were evaluated to quantify the precision with which fitted lineshape parameters can be determined at a given signal-to-noise ratio, focusing on the numerical correlation between the retrieved Dicke narrowing frequency and the velocity-changing and dephasing collisions correlation parameter. Tran, H., N. Ngo, and J.-M. Hartmann, Journal of Quantitative Spectroscopy and Radiative Transfer 2013. 129: p. 89-100. Tennyson, et al., Pure Appl. Chem. 2014, 86: p. 1931-1943. Kochanov, R.V., et al., Journal of Quantitative Spectroscopy and Radiative Transfer 2016. 177: p. 15-30. Tran, H., N. Ngo, and J.-M. Hartmann, Journal of Quantitative Spectroscopy and Radiative Transfer 2013. 129: p. 199-203.

  18. Stability evaluation of quality parameters for palm oil products at low temperature storage.

    Science.gov (United States)

    Ramli, Nur Aainaa Syahirah; Mohd Noor, Mohd Azmil; Musa, Hajar; Ghazali, Razmah

    2017-12-18

    Palm oil is one of the major oils and fats produced and traded worldwide. The value of palm oil products is mainly influenced by their quality. According to ISO 17025:2005, accredited laboratories shall have quality control procedure for monitoring the validity of tests for determination of quality parameters. This includes regular use of internal quality control using secondary reference materials. Unfortunately, palm oil reference materials are not currently available. In order to establish internal quality control samples, the stability of quality parameters need to be evaluated. In this study, the stability of quality parameters for palm oil products were examined over a period of ten months at low temperature storage (6 ± 2 °C). The palm oil products tested herein include crude palm oil (CPO), refined, bleached and deodorized (RBD) palm oil (RBDPO), RBD palm olein (RBDPOo), and RBD palm stearin (RBDPS). The quality parameters of the oils, i.e. moisture content, free fatty acid content (FFA), iodine value (IV), fatty acids composition (FAC) and slip melting point (SMP), were determined prior to and throughout the storage period. The moisture, FFA, IV, FAC and SMP for palm oil products changed significantly (P0.05). The stability study indicated that the quality of the palm oil products was stable within the specified limits throughout the storage period at low temperature. The storage condition has preserved the quality of palm oil products throughout the storage period. These findings qualify the use of the palm oil products; CPO, RBDPO, RBDPOo and RBDPS as control samples for validation of test results. This article is protected by copyright. All rights reserved.

  19. [Evaluation of sensor spectral parameters for the simulation accuracy of the vegetation spectrum].

    Science.gov (United States)

    Li, Bo; Yan, Lei; Zhang, Li-fu

    2010-07-01

    Hyperspectral imaging (HSI) has become one of the most promising and emerging techniques in remote sensing. Due to hundreds of co-registered bands used in HSI system, hyperspectral imagery may provide more spectral information than multi-band images. Unfortunately, original hyperspectral images are more expensive and difficult to achieve than multi-band ones. However, an abundance of spectral information has to be acquired by part of special research for the purpose of ground monitoring, which original HSI systems can easily provide. Then a solution, called hyperspectral satellite data simulation, is proposed for studies in satellite data simulation. It is also one of the most important studies to simulate satellite remote sensing data. In the method, the model with low computational complexity can simulate hyperspectral data quickly, which is based on the priori spectral knowledge of the ground objects. But the accuracy of the simulation data depends on spectral parameters of the sensor. In the present paper, the authors experiment with EO-1/ALI bands in VIS/NIR wavelengths. Then the relationship between the spectral parameters, including the number of bands, bandwidth and the peak wavelength, and the simulation accuracy of the vegetation spectrum are analyzed from their variation principles. According to the results, spectral parameters can determine the effective spectral feature of the vegetation, and impact simulation model directly. Optimal parameters are also summarized for spectral reconstruction in the paper. The experiment results are beneficial to enhancing spectral simulation precision. The conclusions can help evaluate the performance of multispectral sensors and perfect spectroscope and filter design.

  20. Information Theory Approach to Evaluate the Geomagnetic and Ionospheric Response to Solar Wind Parameters

    Science.gov (United States)

    Seemala, G. K.; R, S.; Bhaskara, V.; Ramesh, D. S.

    2014-12-01

    The importance of space weather and understanding onset o geomagnetic storms is increasing day by day as the space missions increase. It is known from the ground-based and space-borne observations that a geomagnetic storm is a temporary disturbance of earth's magnetosphere caused by a solar wind and/or solar eruptions. Geomagnetic storms are more disruptive now than in the past because of our greater dependence on technical systems that can be affected by electric currents and energetic particles high in the Earth's magnetosphere. It is known that number of phenomena occurs during the space weather events; and there are many un-solved questions like solar wind coupling with magnetosphere and ionosphere, relationship between geomagnetic storms & sub-storms etc. To evaluate contribution of various interplanetary parameters that have major role in the geomagnetic storm/geomagnetic variations, the information theory approach is used. In information theory, the measure of uncertainty or randomness of a signal can be quantified by using Shannon entropy or entropy for short. And Transfer entropy is capable of quantifying the directional flow of information between two signals. Thus the Transfer entropy is capable of distinguishing effectively driving and responding signals. In this study, we use Transfer entropy function on Solar wind parameters and ground magnetic data to derive the drivers and relations between them, and also study their contributed effect on ionospheric TEC. In this presentation, we will evaluate and present the results obtained, and discuss about the driving forces on the geomagnetic field disturbances.

  1. Alfuzosin hydrochloride transdermal films: evaluation of physicochemical, in vitro human cadaver skin permeation and thermodynamic parameters

    Directory of Open Access Journals (Sweden)

    Satyanarayan Pattnaik

    2009-12-01

    Full Text Available Purpose: The main objective of the investigation was to develop a transdermal therapeutic system for alfuzosin hydrochloride and to study the effects of polymeric system and loading dose on the in vitro skin permeation pattern. Materials and methods: Principles of experimental design have been exploited to develop the dosage form. Ratio of ethyl cellulose (EC and polyvinyl pyrrolidone (PVP and loading dose were selected as independent variables and their influence on the cumulative amount of alfuzosin hydrochloride permeated per cm2 of human cadaver skin at 24 h (Q24, permeation flux (J and steady state permeability coefficient (P SS were studied using experimental design. Various physicochemical parameters of the transdermal films were also evaluated. Activation energy for in vitro transdermal permeation has been estimated. Results: Ratio of EC and PVP was found to be the main influential factor for all the dependent variables studied. Drug loading dose was also found to influence the dependent variables but to a lesser extent. Physicochemical parameters of the prepared films were evaluated and found satisfactory. Activation energy for alfuzosin permeation has also been estimated and reported. Conclusion: The therapeutic system was found to be dermatologically non-irritant and hence, a therapeutically effective amount of alfuzosin hydrochloride can be delivered via a transdermal route.

  2. [Evaluation of efficacy and safety of drugs absorbed through skin using their physicochemical parameters].

    Science.gov (United States)

    Oshizaka, Takeshi; Todo, Hiroaki; Sugibayashi, Kenji

    2012-01-01

    Skin has been paid attention as a site of application of prescription drugs, over-the-counter drugs (non-prescription drugs) and cosmetics. Skin permeation and skin concentration of the compounds should be considered after topical administration, as well as their blood concentration to evaluate efficacy and safety. Since the evaluation of the amount of drugs permeated through skin is important for topically applied drugs, studies on the skin permeation has been greatly advanced. In addition, many reports proved that skin permeabilities of drugs could be predicted from physicochemical parameters of drugs. On the other hand, few reports have been found on the prediction of skin concentration of drugs. Furthermore, many experimented problems are left to determine the skin concentration of drugs: severe consume of human or animal skins, difficult removal of applied drugs from the skin surface, low drug extraction ratio from skin and low sensitivity to determine skin concentration of drugs, and requirement of long time measurement. Thus, fast and accurate measurement of skin concentration of applied drugs are urgently required. This report describes the relationship between skin permeation and skin concentration, and the prediction of skin concentration of drugs using skin permeation parameters of drugs.

  3. Studies and research concerning BNFP: computerized nuclear materials control and accounting system development evaluation report, FY 1978

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, J M; Ehinger, M H; Joseph, C; Madeen, M L

    1978-10-01

    Development work on a computerized system for nuclear materials control and accounting in a nuclear fuel reprocessing plant is described and evaluated. Hardware and software were installed and tested to demonstrate key measurement, measurement control, and accounting requirements at accountability input/output points using natural uranium. The demonstration included a remote data acquisition system which interfaces process and special instrumentation to a cenral processing unit.

  4. Economic analysis of Royalactin production under uncertainty: Evaluating the effect of parameter optimization.

    Science.gov (United States)

    Torres-Acosta, Mario A; Aguilar-Yañez, Jose M; Rito-Palomares, Marco; Titchener-Hooker, Nigel J

    2015-01-01

    Royalactin is a protein with several different potential uses in humans. Research, in insects and in mammalian cells, has shown that it can accelerate cell division and prevent apoptosis. The method of action is through the use of the epidermal growth factor receptor, which is present in humans. Potential use in humans could be to lower cholesterolemic levels in blood, and to elicit similar effects to those seen in bees, e.g., increased lifespan. Mass production of Royalactin has not been accomplished, though a recent article presented a Pichia pastoris fermentation and recovery by aqueous two-phase systems at laboratory scale as a possible basis for production. Economic modelling is a useful tool with which compare possible outcomes for the production of such a molecule and in particular, to locate areas where additional research is needed and optimization may be required. This study uses the BioSolve software to perform an economic analysis on the scale-up of the putative process for Royalactin. The key parameters affecting the cost of production were located via a sensitivity analysis and then evaluated by Monte Carlo analysis. Results show that if titer is not optimized the strategy to maintain a low cost of goods is process oriented. After optimization of this parameter the strategy changes to a product-oriented and the target output becomes the critical parameter determining the cost of goods. This study serves to provide a framework for the evaluation of strategies for future production of Royalactin, by analyzing the factors that influence its cost of manufacture. © 2015 The Authors Biotechnology Progress published by Wiley Periodicals, Inc. on behalf of American Institute of Chemical Engineers.

  5. Large-scale simulation of karst processes - parameter estimation, model evaluation and quantification of uncertainty

    Science.gov (United States)

    Hartmann, A. J.

    2016-12-01

    Heterogeneity is an intrinsic property of karst systems. It results in complex hydrological behavior that is characterized by an interplay of diffuse and concentrated flow and transport. In large-scale hydrological models, these processes are usually not considered. Instead average or representative values are chosen for each of the simulated grid cells omitting many aspects of their sub-grid variability. In karst regions, this may lead to unreliable predictions when those models are used for assessing future water resources availability, floods or droughts, or when they are used for recommendations for more sustainable water management. In this contribution I present a large-scale groundwater recharge model (0.25° x 0.25° resolution) that takes into karst hydrological processes by using statistical distribution functions to express subsurface heterogeneity. The model is applied over Europe's and the Mediterranean's carbonate rock regions ( 25% of the total area). As no measurements of the variability of subsurface properties are available at this scale, a parameter estimation procedure, which uses latent heat flux and soil moisture observations and quantifies the remaining uncertainty, was applied. The model is evaluated by sensitivity analysis, comparison to other large-scale models without karst processes included and independent recharge observations. Using with historic data (2002-2012) I can show that recharge rates vary strongly over Europe and the Mediterranean. At regions with low information for parameter estimation there is a larger prediction uncertainty (for instance in desert regions). Evaluation with independent recharge estimates shows that, on average, the model provides acceptable estimates, while the other large scale models under-estimate karstic recharge. The results of the sensitivity analysis corroborate the importance of including karst heterogeneity into the model as the distribution shape factor is the most sensitive parameter for

  6. A state-of-the-art report on the evaluation technology of the environmental compatibility of nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Gyu; Oh, Won Zin; Cho, Il Hoon; Ahn, Ki Jung; Kim Young Min

    1997-09-01

    In order to evaluate the environmental compatibility of nuclear fuel cycle, the methodologies for quantifying evaluation factors and the global trend of the back-end nuclear fuel cycle is reviewed. The evaluation methods of monetary values of radiation dose are demonstrate. There are Human Capital, Legal Compensation Principles, Insurance Premium Analogies, and Willingness to Pay. It can be considered that the estimation of public acceptance cost is the estimation problem of economic value of environmental property. In this report, contingent valuation method is discussed, which is one of the estimation methods of economic value. The recent research on residual radiation detection system is analyzed. (author). 7 refs., 10 tabs., 11 figs

  7. The earlier the better: An evaluation of changes to teaching year 1 Nuclear Medicine

    Energy Technology Data Exchange (ETDEWEB)

    Adams, E.J.; Kilburn-Watt, E.; Cowell, S.F. [The University of Sydney, NSW (Australia). School of Medical Radiation Technology

    1998-06-01

    Full text: Changes were made to the content and mode of delivery of the Year 1 Nuclear Medicine degree program at The University of Sydney in 1996. Changes included increased study of skeletal, respiratory and cardiac Nuclear Medicine and the use of problem based learning to increase independent learning and clinical reasoning skills. Learning outcomes were qualitatively assessed to determine the educational value of the changes. The project aimed to evaluate whether changes made to the Year 1 program in 1996 raised clinical abilities of students entering their first clinical placement in Year 2. Retrospective surveys were conducted on both the 1995 and 1996 Year 1 students after completion of their first Year 2 clinical placement. Surveys were designed to assess the students perception of how well Year 1 had prepared them for both understanding and application of content studied in Year 1. Clinical Supervisors who assessed both cohorts of students were surveyed to determine if 1996 students presented with any appreciable difference in understanding and application to areas studied in Year 1. Results of the student survey indicated the 1996 students were more positive than the 1995 students about their clinical readiness. Clinical Supervisor survey results showed a positive response to the level of understanding and application of skills by the 1996 students. In conclusion, the 1996 Year 1 students were perceived to have a higher level of clinical abilities at the commencement of their Year 2 clinical placement. This result demonstrated worthwhile learning outcomes for the changes to content and mode of delivery in the Year 1 Nuclear Medicine degree program

  8. Evaluating the Cost, Safety, and Proliferation Risks of Small Floating Nuclear Reactors.

    Science.gov (United States)

    Ford, Michael J; Abdulla, Ahmed; Morgan, M Granger

    2017-11-01

    It is hard to see how our energy system can be decarbonized if the world abandons nuclear power, but equally hard to introduce the technology in nonnuclear energy states. This is especially true in countries with limited technical, institutional, and regulatory capabilities, where safety and proliferation concerns are acute. Given the need to achieve serious emissions mitigation by mid-century, and the multidecadal effort required to develop robust nuclear governance institutions, we must look to other models that might facilitate nuclear plant deployment while mitigating the technology's risks. One such deployment paradigm is the build-own-operate-return model. Because returning small land-based reactors containing spent fuel is infeasible, we evaluate the cost, safety, and proliferation risks of a system in which small modular reactors are manufactured in a factory, and then deployed to a customer nation on a floating platform. This floating small modular reactor would be owned and operated by a single entity and returned unopened to the developed state for refueling. We developed a decision model that allows for a comparison of floating and land-based alternatives considering key International Atomic Energy Agency plant-siting criteria. Abandoning onsite refueling is beneficial, and floating reactors built in a central facility can potentially reduce the risk of cost overruns and the consequences of accidents. However, if the floating platform must be built to military-grade specifications, then the cost would be much higher than a land-based system. The analysis tool presented is flexible, and can assist planners in determining the scope of risks and uncertainty associated with different deployment options. © 2017 Society for Risk Analysis.

  9. Assessment of Some Immune Parameters in Occupationally Exposed Nuclear Power Plants Workers: Flowcytometry Measurements of T, B, NK and NKT Cells.

    Science.gov (United States)

    Gyuleva, Ilona; Panova, Delyana; Djounova, Jana; Rupova, Ivanka; Penkova, Kalina

    2015-01-01

    The purpose of this article is to analyze the results of a 10-year survey of the radiation effects of some immune parameters of occupationally exposed personnel from the Nuclear Power Plant "Kozloduy", Bulgaria. 438 persons working in NPP with cumulative doses between 0.06 mSv and 766.36mSv and a control group with 65 persons were studied. Flow cytometry measurements of T, B, natural killer (NK) and natural killer T (NKT) cell lymphocyte populations were performed. Data were interpreted with regard to cumulative doses, length of service and age. The average values of the studied parameters of cellular immunity were in the reference range relative to age and for most of the workers were not significantly different from the control values. Low doses of ionizing radiation showed some trends of change in the number of CD3+CD4+ helper-inducer lymphocytes, CD3+ CD8+ and NKT cell counts. The observed changes in some of the studied parameters could be interpreted in terms of adaptation processes at low doses. At doses above 100-200 mSv, compensatory mechanisms might be involved to balance deviations in lymphocyte subsets. The observed variations in some cases could not be attributed only to the radiation exposure because of the impact of a number of other exogenous and endogenous factors on the immune system.

  10. Evaluating iron status and the risk of anemia in young infants using erythrocyte parameters.

    Science.gov (United States)

    Torsvik, Ingrid Kristin; Markestad, Trond; Ueland, Per Magne; Nilsen, Roy M; Midttun, Oivind; Bjørke Monsen, Anne-Lise

    2013-02-01

    Correct evaluation of iron status is important in young infants because both iron deficiency and excess may have negative effects on development, growth, and morbidity. We evaluated iron status using erythrocyte parameters, including reticulocyte hemoglobin content (CHr) in infants with birth weight <3,000 g (n = 80). Blood samples and infant characteristics were recorded at 6 wk and at 4 and 6 months. Infants with a birth weight ≤2,500 g (n = 36) were recommended for iron supplementation. Despite a significantly poorer status at 6 wk, iron-supplemented infants had significantly higher hemoglobin level (Hb): 12.2 (SD = 0.8) g/dl and CHr: 28.3 (SD = 1.4) pg at 6 mo, as compared with nonsupplemented infants, Hb: 11.7 (SD = 1.0) g/dl, P = 0.02 and CHr: 26.5 (SD = 2.5) pg, P < 0.001. Prolonged exclusive breastfeeding, high weight gain, and male gender were the predisposing factors for a low iron status at 6 mo. A CHr cutoff level of 26.9 pg at 4 mo proved to be a sensitive predictor for anemia at 6 mo. Signs of an iron-restricted erythropoiesis were observed in nonsupplemented infants (birth weight 2,501-3,000 g), and CHr was a useful tool for evaluating iron status. The need for iron supplementation in certain infant risk populations should be further evaluated.

  11. Evaluation of incident analysis practices in the Finnish nuclear power industry

    Energy Technology Data Exchange (ETDEWEB)

    Kettunen, J.; Laakso, K

    1999-12-01

    This report provides an analysis and evaluation of incident analysis methods and practices applied by the Finnish regulator Radiation and Nuclear Safety Authority (STUK) and the two Finnish nuclear power plant operators Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy (Fortum). The study was conducted in 1998-99. The research material was based on tape-recorded interviews as well as internal directions and event investigation reports provided by the three participating organisations. A framework for analysis and evaluation was developed as part of the study on the basis of referenced root cause analysis and operating experience review methods, selected (foreign) inspection reports, scientific papers and research literature. Well-known inspection methods and principles, such as ASSET and MTO/HPES, provided important guidance to this work. This study shows that although all the evaluated organisations had rather comprehensive incident analysis arrangements, more focus and priorisation is needed. Deficiencies were identified mostly in the areas of recording, assessment and classification of new events and observations, use of existing operating experience data, utilisation of information technology based tools, and allocation of work and resources. In general the direct causes of identified events can be detected and removed, but more emphasis should be given to the prevention of recurrence. This requires a more efficient feedback loop that can be created and maintained by focusing on the root causes of significant events, tasks and activities in which the originating errors occurred, and weaknesses of defensive barriers, and by implementing periodic operational experience reviews. A strategy document for the operating experience feedback process, and firm procedures for the initial assessment of new events and the carrying out of data analyses would help. (orig.)

  12. How do young people evaluate nuclear energy at nuclear power plant sites? An empirical study; Wie bewerten junge Menschen an Standorten von Kernkraftwerken die Kernenergie? Eine empirische Studie

    Energy Technology Data Exchange (ETDEWEB)

    Kretz, Simon [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Inst. fuer Geographie und Geooekologie; Kramer, Caroline [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Professur fuer Humangeographie

    2014-12-15

    How does the younger generation evaluate nuclear power at sites with nuclear power plants? This has been examined at four sites with different decommissioning stages, as the presence of a nuclear power plant in young people's daily life represents a potential employer as well as a potential risk factor. The attitude of this generation will expectedly and sustainably influence the development of communities. The decommissioning of a nuclear power plant is currently, optimistically estimated by different energy supplying companies with a time period of 15 to 20 year. Thus the resident population will deal with this topic until the year 2040. Furthermore the decision on a repository exploration has been sighted for the year 2013. As a final repository will not be ready for operation at that time, communities will have to deal with the storage of radioactive waste in local interim-storage facilities. The next generation has the opportunity to shape their future as well as the future of their community. Nevertheless the preconditions are to stay at the side as well as the political and social engagement of these young people. n order to study this aspect and the opportunities of action of young people, data was gathered by carrying out a standardised survey, interviewing 762 pupils in February 2014.

  13. An Evaluation of North Korea’s Nuclear Test by Belbasi Nuclear Tests Monitoring Center-KOERI

    Science.gov (United States)

    Necmioglu, O.; Meral Ozel, N.; Semin, K.

    2009-12-01

    Bogazici University and Kandilli Observatory and Earthquake Research Institute (KOERI) is acting as the Turkish National Data Center (NDC) and responsible for the operation of the International Monitoring System (IMS) Primary Seismic Station (PS-43) under Belbasi Nuclear Tests Monitoring Center for the verification of compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT) since February 2000. The NDC is responsible for operating two arrays which are part of the IMS, as well as for transmitting data from these stations to the International Data Centre (IDC) in Vienna. The Belbasi array was established in 1951, as a four-element (Benioff 1051) seismic array as part of the United States Atomic Energy Detection System (USAEDS). Turkish General Staff (TGS) and U.S. Air Force Technical Application Center (AFTAC) under the Defense and Economic Cooperation Agreement (DECA) jointly operated this short period array. The station was upgraded and several seismometers were added to array during 1951 and 1994 and the station code was changed from BSRS (Belbasi Seismic Research Station) to BRTR-PS43 later on. PS-43 is composed of two sub-arrays (Ankara and Keskin): the medium-period array with a ~40 km radius located in Ankara and the short-period array with a ~3 km radius located in Keskin. Each array has a broadband element located at the middle of the circular geometry. Short period instruments are installed at depth 30 meters from the surface while medium and broadband instruments are installed at depth 60 meters from surface. On 25 May 2009, The Democratic People’s Republic of Korea (DPRK) claimed that it had conducted a nuclear test. Corresponding seismic event was recorded by IMS and IDC released first automatic estimation of time (00:54:43 GMT), location (41.2896°N and 129.0480°E) and the magnitude (4.52 mb) of the event in less than two hours time (USGS: 00:54:43 GMT; 41.306°N, 129.029°E; 4.7 mb) During our preliminary analysis of the 25th May 2009 DPRK

  14. Parameter analysis for feasibility evaluation of shallow groundwater cooling of power plants

    Science.gov (United States)

    Dirix, Katrijn; Harcouët-Menou, Virginie; Van Bael, Johan; Laenen, Ben

    2017-04-01

    This paper presents the first results of a finite difference-based numerical model, aiming to evaluate the potential of a new cooling concept that is based on the use of closed loop groundwater cooling integrated in a binary cycle. The new concept includes the seasonal combination of air cooling and shallow groundwater cooling and is part of the H2020 MATChING project. The proposed cooling system under investigation will be compared with dry type cooler condenser (e.g. air cooled condenser systems) and aims to reduce overall water withdrawal without compromising the energy efficiency of the system. The pilot site for this evaluation is the geothermal Balmatt site in Mol-Dessel, Belgium. When operating at its full potential, this site could produce up to 27 MW of heat. To (partly) cool this heat, water from the permeable Miocene 'Diest formation' could be used in a closed loop, i.e. without consuming water. This aquifer is located at a depth of 35 to 151 m bgl, consists of glauconitic coarse sands and has an average permeability of 10 m/day. The water has a temperature of ca. 12°C. In the design under evaluation, this water will be heated up to a maximum of 22°C after passing through the condenser. During summer months, the water will be injected directly back into the aquifer, while in winter, additional cooling will be realised using an air cooler before injecting the water (at ca. 6 °C). By adding this extra cooling step, the lifetime of the system will increase significantly. To cool the large amount of rejected heat, over 2000 m3/h of water needs to be extracted from the aquifer, requiring the installation of several doublet systems. The feasibility of such an installation depends on several interdependent factors, such as temperature, pressure, well distance, distance between the doublets, permeability and natural flow conditions. Since no exact values of most of these factors are available, a large uncertainty exists for feasibility predictions. To assess

  15. Update and evaluation of decay data for spent nuclear fuel analyses

    Science.gov (United States)

    Simeonov, Teodosi; Wemple, Charles

    2017-09-01

    Studsvik's approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group cross-sections, calculated by the CASMO5 or HELIOS2 lattice transport codes, with core irradiation history data from the SIMULATE5 reactor core simulator and tabulated isotopic decay data. These data sources are used and processed by the code SNF to predict spent nuclear fuel characteristics. Recent advances in the generation procedure for the SNF decay data are presented. The SNF decay data includes basic data, such as decay constants, atomic masses and nuclide transmutation chains; radiation emission spectra for photons from radioactive decay, alpha-n reactions, bremsstrahlung, and spontaneous fission, electrons and alpha particles from radioactive decay, and neutrons from radioactive decay, spontaneous fission, and alpha-n reactions; decay heat production; and electro-atomic interaction data for bremsstrahlung production. These data are compiled from fundamental (ENDF, ENSDF, TENDL) and processed (ESTAR) sources for nearly 3700 nuclides. A rigorous evaluation procedure of internal consistency checks and comparisons to measurements and benchmarks, and code-to-code verifications is performed at the individual isotope level and using integral characteristics on a fuel assembly level (e.g., decay heat, radioactivity, neutron and gamma sources). Significant challenges are presented by the scope and complexity of the data processing, a dearth of relevant detailed measurements, and reliance on theoretical models for some data.

  16. Update and evaluation of decay data for spent nuclear fuel analyses

    Directory of Open Access Journals (Sweden)

    Simeonov Teodosi

    2017-01-01

    Full Text Available Studsvik’s approach to spent nuclear fuel analyses combines isotopic concentrations and multi-group cross-sections, calculated by the CASMO5 or HELIOS2 lattice transport codes, with core irradiation history data from the SIMULATE5 reactor core simulator and tabulated isotopic decay data. These data sources are used and processed by the code SNF to predict spent nuclear fuel characteristics. Recent advances in the generation procedure for the SNF decay data are presented. The SNF decay data includes basic data, such as decay constants, atomic masses and nuclide transmutation chains; radiation emission spectra for photons from radioactive decay, alpha-n reactions, bremsstrahlung, and spontaneous fission, electrons and alpha particles from radioactive decay, and neutrons from radioactive decay, spontaneous fission, and alpha-n reactions; decay heat production; and electro-atomic interaction data for bremsstrahlung production. These data are compiled from fundamental (ENDF, ENSDF, TENDL and processed (ESTAR sources for nearly 3700 nuclides. A rigorous evaluation procedure of internal consistency checks and comparisons to measurements and benchmarks, and code-to-code verifications is performed at the individual isotope level and using integral characteristics on a fuel assembly level (e.g., decay heat, radioactivity, neutron and gamma sources. Significant challenges are presented by the scope and complexity of the data processing, a dearth of relevant detailed measurements, and reliance on theoretical models for some data.

  17. Background Radiation Survey of the Radiological/Nuclear Countermeasures Test and Evaluation Center

    Energy Technology Data Exchange (ETDEWEB)

    Colin Okada

    2010-09-16

    In preparation for operations at the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC), the Department of Homeland Security Domestic Nuclear Detection Office (DHS/DNDO) requested that personnel from the Remote Sensing Laboratory (RSL) conduct a survey of the present radiological conditions at the facility. The measurements consist of the exposure rate from a high-pressure ion chamber (HPIC), high-resolution spectra from a high-purity germanium (HPGe) system in an in situ configuration, and low-resolution spectra from a sodium iodide (NaI) detector in a radiation detection backpack. Measurements with these systems were collected at discrete locations within the facility. Measurements were also collected by carrying the VECTOR backpack throughout the complex to generate a map of the entire area. The area was also to be surveyed with the Kiwi (an array of eight-2-inch x 4-inch x 16-inch NaI detectors) from the Aerial Measuring Systems; however, conflicts with test preparation activities at the site prevented this from being accomplished.

  18. Evaluation of the Effects of Menstrual Cycle on Anterior Chamber Parameters as Measured with Pentacam

    Directory of Open Access Journals (Sweden)

    Arzu Seyhan Karatepe

    2013-01-01

    Full Text Available Pur po se: To evaluate the effects of endogenous gonadotropic hormones (follicle-stimulating hormone, luteinizing hormone and sex steroids (progesterone, estrogen to anterior segment parameters. Ma te ri al and Met hod: Thirty healthy females who had a menstrual cycle of 28±1 day and with a mean age of 36.5±7.56 (range, 20 – 46 years were included in the study. Starting from the first day of their cycle, Pentacam Scheimpflug camera measurements were performed on the 1st, 3rd, 7th, 12th, 16th, 21st, 26th, and 28th days. The central corneal thickness, anterior chamber depth, anterior segment volume, keratometric values, anterior chamber angle value, and pupilla diameter of both eyes were evaluated. Repeated measures analysis of variance test was used for statistical analysis. Re sults: No difference that reaches statistical significance was found in the means of central corneal thickness, anterior chamber volume, keratometric values, anterior chamber angle, and pupilla diameter between the days. Mean anterior chamber depth measurement of the right eyes on the 1st day was 2.72±0.44 mm, whereas it was 2.77±0.46 mm on the 26th day. Mean anterior chamber depth measurement of the left eyes on the 1st day was 2.74±0.42 mm, whereas it was 2.80±0.43 mm on the 26th day. This increment of anterior chamber depth value from the 1st to the 26th days was found to be statistically significant (p≤0.05. Dis cus si on: Progesterone and estrogen that rise in the second half of the menstrual cycle might have a deepening effect on the anterior chamber. These findings should be further investigated with more profound studies that also evaluate the hormonal values and their correlations with anterior segment parameters. (Turk J Ophthalmol 2013; 43: 15-8

  19. Nuclear medicine imaging technique in the erectile dysfunction evaluation: a mini-review

    Directory of Open Access Journals (Sweden)

    Camila Godinho Ribeiro

    2007-09-01

    Full Text Available Functional imaging with positron emission tomography and single photon emission computed tomography is capable of visualizing subtle changes in physiological function in vivo. Erectile dysfunction(ED diminishes quality of life for affected men and their partners. Identification of neural substrates may provide information regarding the pathophysiology of types of sexual dysfunction originating in the brain. The aim of this work is to verify the approaches of the nuclear medicine techniques in the evaluation of the erectile function/disfunction. A search using the words ED and nuclear medicine, ED and scintigraphy, ED and spect and ED and pet was done in the PubMed. The number of citations in each subject was determined. Neuroimaging techniques offer insight into brain regions involved in sexual arousal and inhibition. To tackle problems such as hyposexual disorders or ED caused by brain disorders, it is crucial to understand how the human brain controls sexual arousal and penile erection.Imagens functionais, como o positron emission tomography e o single photon emission computed tomography são capazes de identificar súbitas alterações fisiológicas in vivo. A disfunção er��til diminui a qualidade de vida do casal. A identificação de substratos neurais pode esclarecer a fisiopatologia dos diferentes tipos de disfunções sexuais originadas no cérebro. O objetivo deste trabalho é verificar a abordagem das técnicas da medicina nuclear na avaliação da função/disfunção erétil. Uma pesquisa utilizando as palavras disfunção erétil e medicina nuclear, disfunção erétil e cintigrafia, disfunção erétil e SPECT e disfunção erétil e PET foi realizada no PubMed. O número de citações em cada palavra estudada foi determinado. Técnicas de neuroimagem permitem a avaliação das regiões cerebrais durante o estímulo ou inibição sexual. Para resolver alterações como disfunções hipossexuais ou disfunção erétil causada

  20. Suggestion of Design Evaluation Plan based on Star Life Cycle to introduce the Information Minimalism Concept of KOREA Nuclear Plant

    Science.gov (United States)

    Jang, Gwi-sook; Lee, Seung-min; Park, Gee-yong

    2018-01-01

    The design of Korea Nuclear Power Plant (NPP) main control rooms (MCR) has been changed to be fully digitalized. Five or six display devices are assigned to each operator in NPP MCR to provide the information of safety parameter and plant status, and various control functions by connecting computerized control devices. Under this circumstance, the distributed displays can induce a dispersion of the operators' attention and increase the workload while conducting monitoring and control tasks efficiently. In addition, to support human operators to reduce their workload and increase the performance, the concepts of the ecological interface design (EID) and the operator-centered design were applied to the design HMI display. However these designs are applied to a limited set of screens and did not differ largely from the traditional HMI design in that the layout of the information is somewhere similar to P&IDs. In this paper, we propose a design evaluation plan based on star life cycle to introduce the information minimalism concept for designing an HMI display.

  1. Evaluation of Computational Techniques for Parameter Estimation and Uncertainty Analysis of Comprehensive Watershed Models

    Science.gov (United States)

    Yen, H.; Arabi, M.; Records, R.

    2012-12-01

    The structural complexity of comprehensive watershed models continues to increase in order to incorporate inputs at finer spatial and temporal resolutions and simulate a larger number of hydrologic and water quality responses. Hence, computational methods for parameter estimation and uncertainty analysis of complex models have gained increasing popularity. This study aims to evaluate the performance and applicability of a range of algorithms from computationally frugal approaches to formal implementations of Bayesian statistics using Markov Chain Monte Carlo (MCMC) techniques. The evaluation procedure hinges on the appraisal of (i) the quality of final parameter solution in terms of the minimum value of the objective function corresponding to weighted errors; (ii) the algorithmic efficiency in reaching the final solution; (iii) the marginal posterior distributions of model parameters; (iv) the overall identifiability of the model structure; and (v) the effectiveness in drawing samples that can be classified as behavior-giving solutions. The proposed procedure recognize an important and often neglected issue in watershed modeling that solutions with minimum objective function values may not necessarily reflect the behavior of the system. The general behavior of a system is often characterized by the analysts according to the goals of studies using various error statistics such as percent bias or Nash-Sutcliffe efficiency coefficient. Two case studies are carried out to examine the efficiency and effectiveness of four Bayesian approaches including Metropolis-Hastings sampling (MHA), Gibbs sampling (GSA), uniform covering by probabilistic rejection (UCPR), and differential evolution adaptive Metropolis (DREAM); a greedy optimization algorithm dubbed dynamically dimensioned search (DDS); and shuffle complex evolution (SCE-UA), a widely implemented evolutionary heuristic optimization algorithm. The Soil and Water Assessment Tool (SWAT) is used to simulate hydrologic and

  2. Digital Evaluation of Functional Occlusion Parameters and their Association with Temporomandibular Disorders.

    Science.gov (United States)

    Haralur, Satheesh B

    2013-08-01

    Dental researchers are contradictory in their opinion on the role of occlusion in TMD. Occlusal evaluation of both conventional and digital methods in TMD patients will provide the accurate information about the factors accountable for occlusal instability. Identifying the factors responsible will facilitate precise diagnosis and treatment for TMD. The AIM of the study was to determine the dynamic occlusal parameters strongly associated with the etiology of Temporomandibular disorders. Study group consisted of 100 patients; it included 50 patients with normal TMJ(Group I) and remaining 50 patients had a minimum of one positive sign or symptom of Temporomandibular disorder (GroupII). The patient's dynamic occlusal contacts were evaluated by both conventional and digital methods. The Articulating paper was utilized for conventional occlusion analysis. During conventional analysis centric, lateral and protrusive interferences were evaluated along with loss of vertical dimension. Digital occlusal analysis was performed with T-Scan III. Clusion time, disclusion times were recorded for both groups. Chi-square and Student't' statistical analyses were performed to ascertain the association and statistically significant difference between the groups using SPSS19. Group II patients predominantly (66%)had Group-function occlusion compared to Group I subject. Centric slide more than 2 mm found to have strong influence (p value 0.008) on the etiology of TMD. Among the occlusal interferences evaluated balanced side interferences had a strong correlation with TMD with p-value of 0.003. Working side interferences, protrusive interferences had a p-value of 0.157, 0.826 respectively, indicating weak association. T-Scan analysis showed Group I had 0.689, 0.9136, 0.7952, 0.9794 seconds of clusion, left, right, protrusive disclusion time respectively compared to corresponding 1.862, 1.7995, 1.6978, 1.9296 seconds for Group II. Statistically significant difference (p≤0.05) was found

  3. Advantage of population pharmacokinetic method for evaluating the bioequivalence and accuracy of parameter estimation of pidotimod.

    Science.gov (United States)

    Huang, Jihan; Li, Mengying; Lv, Yinghua; Yang, Juan; Xu, Ling; Wang, Jingjing; Chen, Junchao; Wang, Kun; He, Yingchun; Zheng, Qingshan

    2016-09-01

    This study was aimed at exploring the accuracy of population pharmacokinetic method in evaluating the bioequivalence of pidotimod with sparse data profiles and whether this method is suitable for bioequivalence evaluation in special populations such as children with fewer samplings. Methods In this single-dose, two-period crossover study, 20 healthy male Chinese volunteers were randomized 1 : 1 to receive either the test or reference formulation, with a 1-week washout before receiving the alternative formulation. Noncompartmental and population compartmental pharmacokinetic analyses were conducted. Simulated data were analyzed to graphically evaluate the model and the pharmacokinetic characteristics of the two pidotimod formulations. Various sparse sampling scenarios were generated from the real bioequivalence clinical trial data and evaluated by population pharmacokinetic method. The 90% confidence intervals (CIs) for AUC0-12h, AUC0-∞, and Cmax were 97.3 - 118.7%, 96.9 - 118.7%, and 95.1 - 109.8%, respectively, within the 80 - 125% range for bioequivalence using noncompartmental analysis. The population compartmental pharmacokinetics of pidotimod were described using a one-compartment model with first-order absorption and lag time. In the comparison of estimations in different dataset, the estimation of random three- andstrategies can provide results similar to those obtained through rich sampling. The nonlinear mixed-effects model requires fewer data points. Moreover, compared with the noncompartmental analysis method, the pharmacokinetic parameters can be more accurately estimated using nonlinear mixed-effects model. The population pharmacokinetic modeling method was used to assess the bioequivalence of two pidotimod formulations with relatively few sampling points and further validated the bioequivalence of the two formulations. This method may provide useful information for regulating bioequivalence evaluation in special populations.

  4. Team interaction skills evaluation criteria for nuclear power plant control room operators

    Energy Technology Data Exchange (ETDEWEB)

    Montgomery, J.C. [Pacific Northwest Lab., Richland, WA (United States); Toquam, J. [Battelle Human Affairs Research Center, Seattle, WA (United States); Gaddy, C. [General Physics Corp., Columbia, MD (United States)

    1991-09-01

    Previous research has shown the value of good team interaction skills to group performance, yet little progress has been made on in terms of how such skills can be measured. In this study rating scales developed previously (Montgomery, et al., 1990) were extensively revised and cast into a Behaviorally Anchored Rating Scale (BARS) and a Behavioral Frequency format. Rating data were collected using 13 training instructors at the Diablo Canyon Nuclear Plant, who rated three videotapes of simulator scenario performance during a day-long training session and later evaluated control room crews during requalification training. High levels of interrater agreement on both rating scales were found. However, the factor structure of the ratings was generally inconsistent with that hypothesized. Analysis of training ratings using Cronbach`s components of accuracy (Cronbach, 1955) indicated that BARS ratings generally exhibited less error than did the Behavioral Frequency ratings. The results are discussed in terms of both field and research implications.

  5. Evaluation of ammonium bifluoride fusion for rapid dissolution in post-detonation nuclear forensic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Hubley, Nicholas T. [Missouri Univ., Columbia, MO (United States). Dept. of Chemistry; Brockman, John D. [Missouri Univ., Columbia, MO (United States). Research Reactor Center; Robertson, J. David [Missouri Univ., Columbia, MO (United States). Research Reactor Center; Missouri Univ., Columbia, MO (United States). Dept. of Chemistry

    2017-10-01

    Dissolution of geological reference materials by fusion with ammonium bifluoride, NH{sub 4}HF{sub 2} or ABF, was evaluated for its potential use in post-detonation nuclear forensics. The fusion procedure was optimized such that the total dissolution time was <3 h without compromising recovery. Geological reference materials containing various levels of silicates were dissolved and measured by ICP-MS to quantify elemental recovery. Dissolutions of NIST 278 obsidian and urban canyon matrix were performed with radiotracer spikes to measure potential loss of volatile elements during the fusion procedure via gamma-ray spectroscopy. Elemental percent recoveries obtained by ICP-MS were found to be 80-120% while recoveries of radiotracers were observed to be 90-100% with the exception of iodine.

  6. Multiple Attribute Decision Making Based on Cross-Evaluation with Uncertain Decision Parameters

    Directory of Open Access Journals (Sweden)

    Tao Ding

    2016-01-01

    Full Text Available Multiple attribute decision making (MADM problem is one of the most common and popular research fields in the theory of decision science. A variety of methods have been proposed to deal with such problems. Nevertheless, many of them assumed that attribute weights are determined by different types of additional preference information which will result in subjective decision making. In order to solve such problems, in this paper, we propose a novel MADM approach based on cross-evaluation with uncertain parameters. Specifically, the proposed approach assumes that all attribute weights are uncertain. It can overcome the drawback in prior research that the alternatives’ ranking may be determined by a single attribute with an overestimated weight. In addition, the proposed method can also balance the mean and deviation of each alternative’s cross-evaluation score to guarantee the stability of evaluation. Then, this method is extended to a more generalized situation where the attribute values are also uncertain. Finally, we illustrate the applicability of the proposed method by revisiting two reported studies and by a case study on the selection of community service companies in the city of Hefei in China.

  7. The ORSphere Benchmark Evaluation and Its Potential Impact on Nuclear Criticality Safety

    Energy Technology Data Exchange (ETDEWEB)

    John D. Bess; Margaret A. Marshall; J. Blair Briggs

    2013-10-01

    In the early 1970’s, critical experiments using an unreflected metal sphere of highly enriched uranium (HEU) were performed with the focus to provide a “very accurate description…as an ideal benchmark for calculational methods and cross-section data files.” Two near-critical configurations of the Oak Ridge Sphere (ORSphere) were evaluated as acceptable benchmark experiments for inclusion in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook). The results from those benchmark experiments were then compared with additional unmoderated and unreflected HEU metal benchmark experiment configurations currently found in the ICSBEP Handbook. For basic geometries (spheres, cylinders, and slabs) the eigenvalues calculated using MCNP5 and ENDF/B-VII.0 were within 3 of their respective benchmark values. There appears to be generally a good agreement between calculated and benchmark values for spherical and slab geometry systems. Cylindrical geometry configurations tended to calculate low, including more complex bare HEU metal systems containing cylinders. The ORSphere experiments do not calculate within their 1s uncertainty and there is a possibility that the effect of the measured uncertainties for the GODIVA I benchmark may need reevaluated. There is significant scatter in the calculations for the highly-correlated ORCEF cylinder experiments, which are constructed from close-fitting HEU discs and annuli. Selection of a nuclear data library can have a larger impact on calculated eigenvalue results than the variation found within calculations of a given experimental series, such as the ORCEF cylinders, using a single nuclear data set.

  8. Evaluation of the Medical Academic Community of Bosnia and Herzegovina Based on Scopus Parameters.

    Science.gov (United States)

    Masic, Izet

    2017-06-01

    The academic community of Bosnia and Herzegovina (B&H) is represented by four Academies, which include eminent personalities in the field of medical sciences (Academy of Sciences and Arts of Bosnia and Herzegovina, Department for Medical Sciences (ANUBiH), Academy of Sciences and Arts of the Republika Srpska (ANURS), Croatian Academy of Sciences and Arts in BiH (HAZU B&H), and the Academy of Medical Sciences of Bosnia and Herzegovina (AMNuBiH)). To present scientometric analysis of members of the medical sphere of the ANUBiH, ANURS, HAZU B&H and AMNuBiH, to evaluate members and their scientific rating. The work has an analytical character and presents analysis of the data obtained from the Scopus database. Results are shown through number of cases, percentage, arithmetic mean, standard deviation, median and interquartile range, with Spearman's rank correlation coefficient. The analysis showed a significant correlation between the Academy and the country of origin of the academician. In AMNuBiH and ANUBiH are mainly represented academics originating from Bosnia and Herzegovina, while ANURS, 71.4% of the members, are academics with background from Serbia. There is no significant correlation between the observed parameters (Scopus parameters-number of papers, H index, number of citations) according to memberschip in Academies. By analyzing the correlation between the country of residence, the number of papers, H index and the number of citations, it has been shown that the correlation is significant between the state and the number of papers, but not the other two observed parameters. Criteria for admission to main academic communities are highly questionable, as this analysis showed. Progress in the academic hierarchy must be more stringent, and the criteria must be set to the highest possible level, as this is the only path which leads to progress.

  9. Evaluation of Clinical Gait Analysis parameters in patients affected by Multiple Sclerosis: Analysis of kinematics.

    Science.gov (United States)

    Severini, Giacomo; Manca, Mario; Ferraresi, Giovanni; Caniatti, Luisa Maria; Cosma, Michela; Baldasso, Francesco; Straudi, Sofia; Morelli, Monica; Basaglia, Nino

    2017-06-01

    Clinical Gait Analysis is commonly used to evaluate specific gait characteristics of patients affected by Multiple Sclerosis. The aim of this report is to present a retrospective cross-sectional analysis of the changes in Clinical Gait Analysis parameters in patients affected by Multiple Sclerosis. In this study a sample of 51 patients with different levels of disability (Expanded Disability Status Scale 2-6.5) was analyzed. We extracted a set of 52 parameters from the Clinical Gait Analysis of each patient and used statistical analysis and linear regression to assess differences among several groups of subjects stratified according to the Expanded Disability Status Scale and 6-Minutes Walking Test. The impact of assistive devices (e.g. canes and crutches) on the kinematics was also assessed in a subsample of patients. Subjects showed decreased range of motion at hip, knee and ankle that translated in increased pelvic tilt and hiking. Comparison between the two stratifications showed that gait speed during 6-Minutes Walking Test is better at discriminating patients' kinematics with respect to Expanded Disability Status Scale. Assistive devices were shown not to significantly impact gait kinematics and the Clinical Gait Analysis parameters analyzed. We were able to characterize disability-related trends in gait kinematics. The results presented in this report provide a small atlas of the changes in gait characteristics associated with different disability levels in the Multiple Sclerosis population. This information could be used to effectively track the progression of MS and the effect of different therapies. Copyright © 2017. Published by Elsevier Ltd.

  10. [Evaluation of transfer parameters in patients admitted to our hospital with ST-elevation myocardial infarction].

    Science.gov (United States)

    Başar, Cengiz; Özhan, Hakan; Albayrak, Enver Sinan; Türker, Yasin

    2016-01-01

    Acute coronary syndrom (ACS) is a common disease that causes severe morbidity and mortality. The most important aspect of ST-elevation myocardial infarction (STEMI) as a subgroup of ACS treatment is the rapid reperfusion of arteries. Successful results depend not only on the experience of the center but also on the rapidity in which reperfusion is achieved. In our study, the transfer parameters were evaluated in patients who were admitted to our hospital with STEMI. Two hundred consecutive patients (160 males, 40 females) who underwent primary percutaneous coronary intervention (PCI) for acute STEMI between January 2011 and March 2013 were included in our study. Transfer parameters of symptom-to-reperfusion treatment, clinical characteristics, and laboratory parameters were recorded. Thirty-six patients were admitted to our hospital with ambulances; 70 patients were admitted to centers without PCI capability, with a mean transfer time to our hospital of 73.9±12.5 min. Median pain-to-first medical contact time was 105 min (range: 5-600 min), and average first medical contact-to-balloon time was 115.5 min (range: 20-414 min). Total pain-to-balloon time in females was significantly higher than males (246 min [range: 70-840 min], 195 min [range: 45-684 min], respectively, p=0.032). Mean pain-to-balloon time was significantly lower in patients delivered to the hospital by ambulance than in patients admitted to emergency departments independently (185 min [range: 45-439 min], 248 min [range: 65-840 min], respectively, p=0.017). In this study, our hospital door-to-balloon time was found compatible with the target specified in the European Society of Cardiology and American College of Cardiology STEMI guidelines; however, first medical contact-to-balloon time was found to be above that advised by the current guidelines.

  11. Evaluation of some biotechnological parameters influencing the Pleurotus ostreatus biomass production by submerged cultivation

    Directory of Open Access Journals (Sweden)

    Vicenţiu-Bogdan HORINCAR

    2015-12-01

    Full Text Available The submerged culture of mushrooms represents a future for biotechnological processes at industrial level, in order to obtain biomass with economical value (food and ingredients, nutraceuticals and pharmaceuticals. Pleurotus ostreatus is well known worldwide for its culinary and medicinal value. The aim of the present study was to evaluate the most important biotechnological parameters that have influence on the biomass production of P. ostreatus, by cultivation in submerged conditions. Applying the Plackett-Burman experimental design, the significant parameters influencing the P. ostreatus biomass production were found to be the concentration of dextrose and yeast extract and time of cultivation. The best results in terms of maximising the biomass production (25.71 g·L-1 were obtained when the “+1” level of each independent variables was used in the Plackett-Burman experimental design. Analysis of variance (ANOVA exhibited a high correlation coefficient (R2 value of 0.9908, which certifies that the mathematical model was relevant for the biotechnological process.

  12. Introduction of Environmentally Degradable Parameters to Evaluate the Biodegradability of Biodegradable Polymers

    Science.gov (United States)

    Yang, Chao; Song, Cunjiang; Geng, Weitao; Li, Qiang; Wang, Yuanyuan; Kong, Meimei; Wang, Shufang

    2012-01-01

    Environmentally Degradable Parameter (EdK) is of importance in the describing of biodegradability of environmentally biodegradable polymers (BDPs). In this study, a concept EdK was introduced. A test procedure of using the ISO 14852 method and detecting the evolved carbon dioxide as an analytical parameter was developed, and the calculated EdK was used as an indicator for the ultimate biodegradability of materials. Starch and polyethylene used as reference materials were defined as the EdK values of 100 and 0, respectively. Natural soil samples were inoculated into bioreactors, followed by determining the rates of biodegradation of the reference materials and 15 commercial BDPs over a 2-week test period. Finally, a formula was deduced to calculate the value of EdK for each material. The EdK values of the tested materials have a positive correlation to their biodegradation rates in the simulated soil environment, and they indicated the relative biodegradation rate of each material among all the tested materials. Therefore, the EdK was shown to be a reliable indicator for quantitatively evaluating the potential biodegradability of BDPs in the natural environment. PMID:22675455

  13. A comparative evaluation of semen parameters in pre- and post-Hurricane Katrina human population

    Directory of Open Access Journals (Sweden)

    Caner Baran

    2015-01-01

    Full Text Available A natural disaster leading to accumulation of environmental contaminants may have substantial effects on the male reproductive system. Our aim was to compare and assess semen parameters in a normospermic population residing in the Southern Louisiana, USA area pre- and post-Hurricane Katrina. We retrospectively evaluated semen analyses data (n = 3452 of 1855 patients who attended the Tulane University Andrology/Fertility Clinic between 1999 and 2013. The study inclusion criteria were men whose semen analyses showed ≥ 1.5 ml volume; ≥15 million ml -1 sperm concentration; ≥39 million total sperm count; ≥40% motility; >30% morphology, with an abstinence interval of 2-7 days. After the inclusion criteria applied to the population, 367 normospermic patients were included in the study. Descriptive statistics and group-based analyses were performed to interpret the differences between the pre-Katrina (Group 1, 1999-2005 and the post-Katrina (Group 2, 2006-2013 populations. There were significant differences in motility, morphology, number of white blood cell, immature germ cell count, pH and presence of sperm agglutination, but surprisingly there were no significant differences in sperm count between the two populations. This long-term comparative analysis further documents that a major natural disaster with its accompanied environmental issues can influence certain semen parameters (e.g., motility and morphology and, by extension, fertility potential of the population of such areas.

  14. Evaluation of anterior segment parameters in patients with pseudoexfoliation syndrome using Scheimpflug imaging

    Directory of Open Access Journals (Sweden)

    Alime Gunes

    2016-06-01

    Full Text Available ABSTRACT Purpose: To evaluate anterior segment parameters in patients with pseudoexfoliation syndrome (PXS using Scheimpflug imaging. Methods: Forty-three PXS patients and 43 healthy control subjects were included in this cross-sectional study. All participants underwent a detailed ophthalmologic examination. Anterior segment parameters were measured using a Scheimpflug system. Results: Considering the PXS and control groups, the mean corneal thicknesses at the apex point (536 ± 31 and 560 ± 31 µm, respectively, p=0.001, at the center of the pupil (534 ± 31 and 558 ± 33 µm, respectively, p=0.001, and at the thinnest point (528 ± 30 and 546 ± 27 µm, respectively, p=0.005 were significantly thinner in PXS patients. Visual acuity was significantly lower (0.52 ± 0.37 versus 0.88 ± 0.23, p<0.001 and axial length was significantly longer (23.9 ± 0.70 mm versus 23.2 ± 0.90 mm, p=0.001 in the PXS eyes than in the control eyes. There were no statistically significant differences in the mean values of keratometry, anterior chamber angle, anterior chamber depth, corneal volume, and anterior chamber volume between the PXS and control eyes. Conclusions: The patients with PXS had thinner corneas, worse visual acuity, and longer axial length compared with those in the healthy controls.

  15. Parameters of evaluation and correlation of renal phosphate handling and of parathyroid function in children.

    Science.gov (United States)

    Stark, H; Eisenstein, B; Davidovits, M

    1989-01-01

    The aim of the study was to establish normal values for parameters of parathyroid (PT) function in childhood and to examine whether a correlation could be found between these parameters and tubular phosphate (P) reabsorption. Values for PTH (carboxyl terminal) and urinary cAMP (UcAMP) throughout childhood were found to be significantly lower than in adults, with mean values of 0.3 ng/ml (30 pmol/l) and 1.96 nmol/dl glomerular filtrate (GF) respectively. A significant correlation was found between UcAMP and tubular P reabsorption (TP), expressed by the equation: TP = 5.5-(0.5 x UcAMP) mg/dl GF (= 1.78-(0.16 x UcAMP) mmol/dl GF, with a scatter of 10.6 mg/dl around the mean (+/- 1 SD). These data appear to permit the evaluation of primary tubular components in patients with defects of renal P handling, as opposed to those related to PT activity.

  16. Nutritional parameters and yield evaluation of newly developed genotypes of lentil (Lens culinaris Medik.).

    Science.gov (United States)

    Solanki, I S; Kapoor, A C; Singh, U

    1999-01-01

    Among the commonly consumed food legumes, lentils occupy an important place in human nutrition in the Indian subcontinent. Twenty-one lentil genotypes were evaluated for such nutrition related parameters as moisture, protein, crude fiber, fat, ash (total mineral matter), carbohydrates, total energy and metabolizable energy. These genotypes were also analyzed for 100-seed weight and seed yield/plant. Protein content ranged between 22.1 and 27.4% with significant differences among genotypes. Considerable variations were observed among the genotypes for calcium, phosphorus, iron and tannin contents. Large variations existed in yield and 100-seed weight of these genotypes. Seed yield/plant was not significantly correlated with any of the principal seed constituents analyzed in the present study. The genotypes, LH 97 and LH 37 were found to be better and hence could be explored for further development and selection of desirable characteristics.

  17. Evaluation of pre-jamming indication parameter during blind backfilling technique

    Directory of Open Access Journals (Sweden)

    Susmita Panda

    2016-01-01

    Full Text Available Hydraulic blind backfilling is used to reduce subsidence problems above old underground water-logged coal mines. This paper describes experimental research on a fully transparent model of a straight underground mine gallery. An automatic data acquisition system was installed in the model to continuously record the sand and water flowrates along with the inlet pressure of the slurry near the model's inlet. Pressure signature graphs and pressure loss curves with bed advancement under different flow conditions are examined. Pressure signature analyses for various flowrates and sand slurry concentrations are conducted to evaluate a pre-jamming indication parameter, which could be used to indicate the arrival of the final stage of filling.

  18. Evaluation of turbine microjet engine operating parameters in conditions conducive to inlet freezing

    Directory of Open Access Journals (Sweden)

    Markowski Jaroslaw

    2017-01-01

    Full Text Available The problem of turbine microjet engine operation is related to flight conditions of unmanned aircraft. These flights are often performed at low altitudes, where, in autumn and winter conditions, the air can be characterized by high humidity and low temperature. Such operating conditions may cause freezing the turbine engine inlet. In particular, this problem may be related to microengines, which most often are not equipped with a de-icing installation. Frosting of the inlet violates the air flow conditions at the engine inlet and may cause unstable operation and even outages, which eventually may lead to a loss of aircraft’s stability and breakdown. Therefore, an attempt was made to evaluate the changes in operational parameters of the turbine microjet engine under conditions leading to the freezing of the inlet. The engine test was performed in stationary conditions and the analysis of the obtained results are presented in this article.

  19. Evaluation of some microbiological and chemical parameters of Campania buffalo ricotta cheese

    Directory of Open Access Journals (Sweden)

    Angela M.I. Montone

    2017-09-01

    Full Text Available Fresh ricotta (whey cheese, owing to its technological characteristics and intrinsic parameters (pH and aw, is an excellent substrate for the growth of spoilage and pathogenic microorganisms. On 19 July 2010, Campania buffalo ricotta cheese was assigned to the register of Protected Designations of Origin (PDO by the European Commission, with EC Reg. 634/2010. It is mainly produced in the provinces of Caserta and Salerno around the rivers Garigliano and Volturno, the plain of the river Sele and the area of Cilento. This article reports the results of a 9-month monitoring (from May 2014 to January 2015 of ricotta samples aiming at evaluate the microbial status of some cheese factories, since ricotta is considered particularly suitable to judge the hygienic level of the dairy establishments. Four dairies were selected for sampling according to their different structural characteristics and the adequacy of both their premises and equipment.

  20. The stable status evaluation for female breast implant surgery by calculating related physics parameters.

    Science.gov (United States)

    Sun, Shuh-Ping; Hsu, Ko-Wen; Chen, Jing-Shyr

    2008-05-01

    Cosmetic doctor utilizes the position, size and shapes of female's breast to judge whether the breast is under steady-state condition after breast implant plastic surgery. Since, doctor evaluates the breast condition with the subjective discrimination (such as vision, sense of touch) without using the objective physical parameters auxiliary. This study uses the 3D optics scanner editing 3D image to obtain full-scale 3D female breasts image. The CAD system converts the breast position, size and shapes, as the length of the curve between UBL (upper breast line) and NBL (nipple base line), the length of the curve between NBL and LBL (lower breast line), breast volume and breasts congruence rate. The stability after the breast implant plastic surgery is one of the important successful indexes of plastic surgery, so with the continuity analysis the breast curve length, volume and congruence rate can let the doctor really grasp the stability of the breast after plastic surgery.

  1. PARAMETERS FOR THE EVALUATION OF CERVICAL SAGITTAL BALANCE IN IDIOPATHIC SCOLIOSIS

    Directory of Open Access Journals (Sweden)

    MAURICIO COELHO LIMA

    Full Text Available ABSTRACT Objective: There are no values defined as standard in the literature for the parameters of assessment of cervical sagittal balance in patients with idiopathic scoliosis. This study describes the sagittal cervical parameters in patients with idiopathic scoliosis. Methods: Study carried out in a tertiary public hospital in patients with adolescent idiopathic scoliosis, through the evaluation of panoramic radiographs in lateral view. The Cobb method was used to evaluate cervical lordosis from C2 to C7, distance from the center of gravity (COG of the skull to C7, measurement of T1 slope, thoracic inlet angle (TIA, neck tilt, and plumb line from C7 to S1 (SVA C7-S1. A statistical analysis was performed, to demonstrate the relationship between the alignment of the thoracic spine in the sagittal plane and the cervical sagittal balance of patients with scoliosis. Results: Thirty-four patients were female (69.4% and 15 male (30.6%. The mean values for COG-C7 were 0.71 mm (median 0.8 mm/standard deviation [SD]= 0.51 mm. For Cobb C2-C7, the mean was -11.7° (median -10°/SD= 20.4°. The mean slope of T1 was 23.5° (median 25°/SD= 9.5°. The mean cervical version was 58.8° (median 60°/DP= 15.4°. The mean TIA was 81.8° (median 85°/SD= 16.7°. The mean plumb line C7-S1 was -0.28 (-0.3/SD= 1.0. Conclusion: The analysis of the results showed that the mean values for the cervical lordosis are lower than the values described as normal in the literature, suggesting a loss of sagittal cervical balance in these patients.

  2. Recovery of Marginal Maximum Likelihood Estimates in the Two-Parameter Logistic Response Model: An Evaluation of MULTILOG.

    Science.gov (United States)

    Stone, Clement A.

    1992-01-01

    Monte Carlo methods are used to evaluate marginal maximum likelihood estimation of item parameters and maximum likelihood estimates of theta in the two-parameter logistic model for varying test lengths, sample sizes, and assumed theta distributions. Results with 100 datasets demonstrate the methods' general precision and stability. Exceptions are…

  3. Evaluation of CFETR as a Fusion Nuclear Science Facility using multiple system codes

    Science.gov (United States)

    Chan, V. S.; Costley, A. E.; Wan, B. N.; Garofalo, A. M.; Leuer, J. A.

    2015-02-01

    This paper presents the results of a multi-system codes benchmarking study of the recently published China Fusion Engineering Test Reactor (CFETR) pre-conceptual design (Wan et al 2014 IEEE Trans. Plasma Sci. 42 495). Two system codes, General Atomics System Code (GASC) and Tokamak Energy System Code (TESC), using different methodologies to arrive at CFETR performance parameters under the same CFETR constraints show that the correlation between the physics performance and the fusion performance is consistent, and the computed parameters are in good agreement. Optimization of the first wall surface for tritium breeding and the minimization of the machine size are highly compatible. Variations of the plasma currents and profiles lead to changes in the required normalized physics performance, however, they do not significantly affect the optimized size of the machine. GASC and TESC have also been used to explore a lower aspect ratio, larger volume plasma taking advantage of the engineering flexibility in the CFETR design. Assuming the ITER steady-state scenario physics, the larger plasma together with a moderately higher BT and Ip can result in a high gain Qfus ˜ 12, Pfus ˜ 1 GW machine approaching DEMO-like performance. It is concluded that the CFETR baseline mode can meet the minimum goal of the Fusion Nuclear Science Facility (FNSF) mission and advanced physics will enable it to address comprehensively the outstanding critical technology gaps on the path to a demonstration reactor (DEMO). Before proceeding with CFETR construction steady-state operation has to be demonstrated, further development is needed to solve the divertor heat load issue, and blankets have to be designed with tritium breeding ratio (TBR) >1 as a target.

  4. Visual system of recovering and combination of information for ENDF (Evaluated Nuclear Data File) format libraries; Sistema visual de recuperacao e combinacao de informacoes para bibliotecas no formato ENDF (Evaluated Nuclear Data File)

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Claudia A.S. Velloso [Centro Tecnico Aeroespacial, Sao Jose dos Campos, SP (Brazil); Corcuera, Raquel A. Paviotti [Instituto Nacional de Pesquisas Espaciais (INPE), Sao Jose dos Campos, SP (Brazil)

    1997-04-01

    This report presents a data information retrieval and merger system for ENDF (Evaluated Nuclear Data File) format libraries, which can be run on personal computers under the Windows {sup TM} environment. The input is the name of an ENDF/B library, which can be chosen in a proper window. The system has a display function which allows the user to visualize the reaction data of a specific nuclide and to produce a printed copy of these data. The system allows the user to retrieve and/or combine evaluated data to create a single file of data in ENDF format, from a number of different files, each of which is in the ENDF format. The user can also create a mini-library from an ENDF/B library. This interactive and easy-to-handle system is a useful tool for Nuclear Data Centers and it is also of interest to nuclear and reactor physics researchers. (author)

  5. Evaluating the reliability of ultrasonographic parameters in differentiating benign from malignant superficial lymphadenopathy

    Directory of Open Access Journals (Sweden)

    Sarir Nazemi

    2016-11-01

    Full Text Available Diagnosis of malignant lymphadenopathy is of particular importance for treatment planning, before treatment staging and also for prognosis determination. Currently various diagnostic procedures are used to differentiate benign and malignant lymphadenopathy which are invasive and costly. Ultrasonography as a noninvasive, low-cost and accessible method is proposed. The aim of this study was to evaluate the reliability of some ultrasonographic parameters in differentiating malignant from benign superficial lymphadenopathies. In this study ultrasonography was performed for lymph nodes of 100 patients who were eligible for pathological evaluation of superficial lymphadenopathy. The most accessible lymph nodes were marked and biopsied. Sonographic and pathologic results were compared. The sensitivity and specificity of the test and the appropriate cutoff point was determined based on the Receiver Operating Characteristics (ROC curve using SPSS Ver.17. From 100 evaluated lymph nodes 55 were benign and 45 were malignant. There was no significant difference between malignant and benign lymph nodes in terms of cortical and medullary thickness (p=0.055,but there was a significant difference between benign and malignant lymph nodes in terms of blood supply pattern and mean of Pulsatility Index (PI (P=.007 and Resistive Index (RI (P<0.001 . The cortex thickness of 7.95 mm with 62.2٪ sensitivity, 72.7٪ specificity and 70٪ accuracy was the appropriate cutoff point in differentiating malignant and benign lymphadenopathy. The color Doppler criteria in combination with gray scale ultrasonography could be helpful to select patients for biopsy or Fine Needle Aspiration (FNA, but cannot fully replace pathological evaluation.

  6. An analytical method for estimating the 14N nuclear quadrupole resonance parameters of organic compounds with complex free induction decays for radiation effects studies

    Energy Technology Data Exchange (ETDEWEB)

    Iselin, Louis Henry [Univ. of Florida, Gainesville, FL (United States)

    1992-01-01

    The use of 14N nuclear quadrupole resonance (NQR) as a radiation dosimetry tool has only recently been explored. An analytical method for analyzing 14N NQR complex free induction decays is presented with the background necessary to conduct pulsed NQR experiments. The 14N NQR energy levels and possible transitions are derived in step-by-step detail. The components of a pulsed NQR spectrometer are discussed along with the experimental techniques for conducting radiation effects experiments using the spectrometer. Three data analysis techniques -- the power spectral density Fourier transform, state space singular value decomposition (HSVD), and nonlinear curve fitting (using the downhill simplex method of global optimization and the Levenberg-Marquart method) -- are explained. These three techniques are integrated into an analytical method which uses these numerical techniques in this order to determine the physical NQR parameters. Sample data sets of urea and guanidine sulfate data are used to demonstrate how these methods can be employed to analyze both simple and complex free induction decays. By determining baseline values for biologically significant organics, radiation effects on the NQR parameters can be studied to provide a link between current radiation dosimetry techniques and the biological effects of radiation.

  7. Critical parameters and performance tests for the evaluation of digital data acquisition hardware

    OpenAIRE

    PAEPEN Jan; Gårdestig, Magnus; Reppenhagen Grim, Per; KEIGHTLEY John; Nilsson, Jonas; Peräjärvi, Kari; Tengblad, Olof; Toivonen, Harri

    2014-01-01

    Recent developments of digital data acquisition systems allow real-time pre-processing of detector signals at a high count rate. These so-called pulse processing digitizers are powerful and versatile instruments offering techniques which are important for nuclear security, critical infrastructure protection, nuclear physics and radiation metrology. Certain aspects of digital data acquisition affect the performance of the total system in a critical way and therefore require special attention. ...

  8. Updating Nutritional Data and Evaluation of Technological Parameters of Italian Milk

    Directory of Open Access Journals (Sweden)

    Pamela Manzi

    2013-06-01

    Full Text Available Different technologically treated Italian milks (whole and semi-skimmed ultra-high temperature (UHT, pasteurized and microfiltered milk, collected from 2009 to 2012, were evaluated for nutritional and technological properties. No significant differences in calcium and sodium were detected (p > 0.05, while significant differences were observed concerning phosphorus content, between whole and semi-skimmed milk, and lactose content, between pasteurized and UHT milk (p 0.05 were detected for choline, a functional molecule, between whole (11.3–14.6 mg/100 g and semi-skimmed milk (11.1–14.7 mg/100 g, but there were significant differences (p < 0.05 in processing milk (UHT vs. pasteurized milk and UHT vs. microfiltered milk. Among the unsaponifiable compounds, only 13 cis retinol and trans retinol showed differences in technologically treated milk (pasteurized vs. UHT milk and microfiltered vs. UHT milk; p < 0.05. In this research, the greater was the “severity” of milk treatment, the higher was the percent ratio 13 cis/trans retinol (DRI, degree of retinol isomerization. The degree of antioxidant protection parameter (DAP, useful to estimate the potential oxidative stability of fat in foods, was significantly different between whole and semi-skimmed milk (p < 0.05. Finally, the evaluation of color measurement of whole milk showed a good correlation between beta carotene and b* (r = 0.854 and between lactulose and a* (r = 0.862.

  9. An Evaluation of Kinetic Parameters of Cadmium and Copper Biosorption by Immobilized Cells

    Directory of Open Access Journals (Sweden)

    Nelly Georgieva

    2007-10-01

    Full Text Available Bioremediation is the use of living organisms to reduce or eliminate environmental hazards resulting from the accumulation of toxic chemicals and other hazardous wastes. This technology is based on the utilization of microorganisms to transform organic and inorganic compounds. The filamentous yeast Trichosporon cutaneum strain R57, immobilized and free cells was cultivated as batch culture on a liquid medium in the presence of various concentrations of cadmium and copper ions. The simultaneous uptake and accumulation of Cd2+ and Cu2+ ions by Tr. cutaneum cells depending on the initial concentration of Cd2+ and Cu2+ in the medium were studied. The potential use of the free and immobilized cells of Trichosporon cutaneum to remove cadmium and copper ions, from aqueous solutions was evaluated. Two important physicochemical aspects for the evaluation of the sorption process as a unit operation are the equilibrium of sorption and the kinetics. The Cd2+ and Cu2+ ions biosorption capacities of all tested adsorbent were presented as a function of the initial concentration of metal ions within the aqueous biosorption medium. The individual, as well as bicomponent sorption kinetics of copper and cadmium ions by immobilised cells of Trichosporon cutaneum R57 is presented. A second order kinetic model obtains kinetic parameters for the copper and cadmium ions.

  10. Use of hematological parameters in evaluation of treatment efficacy in cutaneous leishmaniasis

    Directory of Open Access Journals (Sweden)

    Bilal Sula

    2015-12-01

    Full Text Available Objective: In the present study we investigated the role of hematological parameters, including neutrophil/lymphocyte ratio and platelet/lymphocyte ratio, mean platelet volume and platelet distribution width in the evaluation of treatment efficacy in adult patients diagnosed with cutaneous leishmaniasis. Methods: The study group included 45 adult patients diagnosed with cutaneous leishmaniasis and treated as inpatients in the dermatology clinic between 2011 and 2014. A group of 45 healthy adults served as a control group. Results: Pre- and post-treatment white blood cell count, neutrophils, and lymphocytes were significantly reduced among the patient group relative to the control group. Platelet distribution width, red cell distribution width, neutrophil/lymphocyte ratio and platelet/lymphocyte ratio were significantly elevated among the patients compared to the healthy subjects. Pre-treatment white blood cell, lymphocyte and platelet counts were significantly elevated compared to post-treatment counts among the patient cohort. Treatment was associated with reduced eosinophil count, neutrophil/lymphocyte ratio and platelet/lymphocyte ratio relative to pre-treatment status. Conclusion: Routine hematological testing results such as platelet/lymphocyte ratio, white blood cell count, neutrophil count, red cell distribution width, platelet distribution width, and mean platelet volume may be clinically significant markers of the inflammatory state useful in the evaluation of early treatment efficacy among patients with cutaneous leishmaniasis. J Microbiol Infect Dis 2015;5(4: 167-172

  11. Myocardial response to a triathlon in male athletes evaluated by Doppler tissue imaging and biochemical parameters

    DEFF Research Database (Denmark)

    Leetmaa, T H; Dam, A; Glintborg, D

    2008-01-01

    The aim of this study was to examine cardiac dysfunction following ultra-endurance exercise in male athletes. Fourteen athletes (mean+/-SD, age 39+/-8 years) were evaluated before and after the European Championship in Triathlon 2003 using echocardiogram (ECG), cardiac markers [cardiac troponin T...... and systolic velocities decreased, thus suggesting reversible cardiac fatigue. When using cardiac markers and echocardiographic findings, a triathlon was found to have no significant negative effects on left ventricular function or myocardial tissue in male athletes.......The aim of this study was to examine cardiac dysfunction following ultra-endurance exercise in male athletes. Fourteen athletes (mean+/-SD, age 39+/-8 years) were evaluated before and after the European Championship in Triathlon 2003 using echocardiogram (ECG), cardiac markers [cardiac troponin T...... echocardiography, no significant differences were found in regional or global systolic parameters. Early diastolic peak flow velocity (9+/-2, P = 0.04) and E/A ratio (2+/-1, P = 0.004) were increased pre-race and decreased significantly toward normal values. In one athlete, cTnT levels increased significantly...

  12. Evaluation of nitrogen containing reducing agents for the corrosion control of materials relevant to nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, Padma S. [Water and Steam Chemistry Division, BARC Facilities, Kalpakkam, Tamilnadu (India); Mohan, D. [Department of Chemistry, Anna University, Chennai, Tamilnadu (India); Chandran, Sinu; Rajesh, Puspalata; Rangarajan, S. [Water and Steam Chemistry Division, BARC Facilities, Kalpakkam, Tamilnadu (India); Velmurugan, S., E-mail: svelu@igcar.gov.in [Water and Steam Chemistry Division, BARC Facilities, Kalpakkam, Tamilnadu (India)

    2017-02-01

    Materials undergo enhanced corrosion in the presence of oxidants in aqueous media. Usually, hydrogen gas or water soluble reducing agents are used for inhibiting corrosion. In the present study, the feasibility of using alternate reducing agents such as hydrazine, aqueous ammonia, and hydroxylamine that can stay in the liquid phase was investigated. A comparative study of corrosion behavior of the structural materials of the nuclear reactor viz. carbon steel (CS), stainless steel (SS-304 LN), monel-400 and incoloy-800 in the oxidizing and reducing conditions was also made. In nuclear industry, the presence of radiation field adds to the corrosion problems. The radiolysis products of water such as oxygen and hydrogen peroxide create an oxidizing environment that enhances the corrosion. Electrochemical studies at 90 °C showed that the reducing agents investigated were efficient in controlling corrosion processes in the presence of oxygen and hydrogen peroxide. Evaluation of thermal stability of hydrazine and its effect on corrosion potential of SS-304 LN were also investigated in the temperature range of 200–280 °C. The results showed that the thermal decomposition of hydrazine followed a first order kinetics. Besides, a change in electrochemical corrosion potential (ECP) was observed from −0.4 V (Vs SHE) to −0.67 V (Vs SHE) on addition of 5 ppm of hydrazine at 240 °C. Investigations were also made to understand the distribution behavior of hydrogen peroxide and hydrazine in water-steam phases and it was found that both the phases showed identical behavior. - Highlights: • Hydrazine was found to be a promising reducing agent for oxidant control. • In presence of hydrazine corrosion potential of SS304 LN was well below −230 mV. • SS304LN could be protected from IGSCC by hydrazine addition. • Thermal and radiation stability of hydrazine at 285 °C was found satisfactory.

  13. Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

    1976-08-10

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre.

  14. Evaluation of counter movement jump parameters in young male soccer players.

    Science.gov (United States)

    Quagliarella, Livio; Sasanelli, Nicola; Belgiovine, Giuseppe; Accettura, Domenico; Notarnicola, Angela; Moretti, Biagio

    2011-01-01

    The Counter Movement Jump (CMJ) is widely used as a field test to evaluate the muscular explosive power of lower limbs in various sports, including soccer. The aim of the present study was to verify the possibility to discriminate the effect of training level and age on young adult male soccer players, adopting the flight time, the peak force, or the peak power obtained from a countermovement jump. One hundred and twenty three young male soccer players were enrolled in the study; the participants were split into groups according to Tanner's stages (pre- and post-pubertal) and training level (high and low activity). A piezoelectric force plate was used to acquire the ground reaction force used to calculate the flight time, the peak value of the vertical component of the ground reaction force, and the peak value of the developed power. As expected, the best performances were obtained by the post pubertal highly-trained soccer players. All performance parameters presented statistically significant differences between ages, while only the flight time exhibited statistically significant differences between training levels. After normalization of the experimental data to body height and weight, there were no statistical differences between ages; statistically significant differences were found only for the flight time and for peak power between training levels. The flight time was the parameter more sensitive to detect differences in the jump performance related to training and age. Adopting a normalization procedure it was possible to highlight that only the flight time and the peak power are sensitive to training effects on young adult male soccer players.

  15. Limits of Nuclear Stability

    CERN Document Server

    Nerlo-Pomorska, B; Kleban, M

    2003-01-01

    The modern version of the liquid-drop model (LSD) is compared with the macroscopic part of the binding energy evaluated within the Hartree-Fock- Bogoliubov procedure with the Gogny force and the relativistic mean field theory. The parameters of a liquid-drop like mass formula which approximate on the average the self-consistent results are compared with other models. The limits of nuclear stability predicted by these models are discussed.

  16. Quantitative evaluation of ozone and selected climate parameters in a set of EMAC simulations

    Directory of Open Access Journals (Sweden)

    M. Righi

    2015-03-01

    Full Text Available Four simulations with the ECHAM/MESSy Atmospheric Chemistry (EMAC model have been evaluated with the Earth System Model Validation Tool (ESMValTool to identify differences in simulated ozone and selected climate parameters that resulted from (i different setups of the EMAC model (nudged vs. free-running and (ii different boundary conditions (emissions, sea surface temperatures (SSTs and sea ice concentrations (SICs. To assess the relative performance of the simulations, quantitative performance metrics are calculated consistently for the climate parameters and ozone. This is important for the interpretation of the evaluation results since biases in climate can impact on biases in chemistry and vice versa. The observational data sets used for the evaluation include ozonesonde and aircraft data, meteorological reanalyses and satellite measurements. The results from a previous EMAC evaluation of a model simulation with nudging towards realistic meteorology in the troposphere have been compared to new simulations with different model setups and updated emission data sets in free-running time slice and nudged quasi chemistry-transport model (QCTM mode. The latter two configurations are particularly important for chemistry-climate projections and for the quantification of individual sources (e.g., the transport sector that lead to small chemical perturbations of the climate system, respectively. With the exception of some specific features which are detailed in this study, no large differences that could be related to the different setups (nudged vs. free-running of the EMAC simulations were found, which offers the possibility to evaluate and improve the overall model with the help of shorter nudged simulations. The main differences between the two setups is a better representation of the tropospheric and stratospheric temperature in the nudged simulations, which also better reproduce stratospheric water vapor concentrations, due to the improved

  17. Evaluating summary statistics used to test for incomplete lineage sorting: mito-nuclear discordance in the reef sponge Callyspongia vaginalis.

    Science.gov (United States)

    Debiasse, Melissa B; Nelson, Bradley J; Hellberg, Michael E

    2014-01-01

    Conflicting patterns of population differentiation between the mitochondrial and nuclear genomes (mito-nuclear discordance) have become increasingly evident as multilocus data sets have become easier to generate. Incomplete lineage sorting (ILS) of nucDNA is often implicated as the cause of such discordance, stemming from the large effective population size of nucDNA relative to mtDNA. However, selection, sex-biased dispersal and historical demography can also lead to mito-nuclear discordance. Here, we compare patterns of genetic diversity and subdivision for six nuclear protein-coding gene regions to those for mtDNA in a common Caribbean coral reef sponge, Callyspongia vaginalis, along the Florida reef tract. We also evaluated a suite of summary statistics to determine which are effective metrics for comparing empirical and simulated data when testing drivers of mito-nuclear discordance in a statistical framework. While earlier work revealed three divergent and geographically subdivided mtDNACOI haplotypes separated by 2.4% sequence divergence, nuclear alleles were admixed with respect to mitochondrial clade and geography. Bayesian analysis showed that substitution rates for the nuclear loci were up to 7 times faster than for mitochondrial COI. Coalescent simulations and neutrality tests suggested that mito-nuclear discordance in C. vaginalis is not the result of ILS in the nucDNA or selection on the mtDNA but is more likely caused by changes in population size. Sperm-mediated gene flow may also influence patterns of population subdivision in the nucDNA. © 2013 John Wiley & Sons Ltd.

  18. Evaluation of different recording parameters to establish a standard for flash electroretinography in rodents.

    Science.gov (United States)

    Bayer, A U; Cook, P; Brodie, S E; Maag, K P; Mittag, T

    2001-08-01

    Different electrodes and stimulus protocols commonly used for electroretinography in rodent eyes were compared for convenience of use, degree of damage to corneal epithelium, and for magnitude of amplitude, reproducibility, left versus right eye accuracy, and reliability of recorded parameters of the flash electroretinogram (ERG). Adult C57BL/6 pigmented mice and albino Wistar rats were used to determine scotopic ERGs in response to Ganzfeld or strobe-light stimulation and light-adapted (photopic) ERGs recorded from both eyes at the same time. Test-retest data were used for statistical analyses to compare a monopolar gold-wire contact lens electrode (CLE), a cotton-wick silver-silver chloride electrode (CSCE), a DTL fiber electrode (DTLE), and a circular stainless steel wire electrode (SSE). Corneas were evaluated for abrasion after ERG recordings using fluorescein staining and also for the time taken, ease of insertion, and re-insertions required for the different electrodes. Compared to CSCE, DTLE, and SSE, the ERG potentials recorded by CLE had significantly larger scotopic amplitudes and oscillatory potentials under strobe or Ganzfeld stimulation and for light-adapted ERG b-wave amplitudes in both mice and rats. In analyzing test-retest data of scotopic ERG a-wave and b-wave amplitudes, the intraclass correlation coefficient showed the best agreement for the CLE (range 0.61-0.94) compared to the SSE (0.13-0.77), DTLE (0.02-0.69), and CSCE (0.12-0.51). In mice and rats, logistic regression analyses revealed significant correlations for amplitudes of most scotopic ERG parameters between contralateral eyes obtained with CLE and for some ERG components recorded by SSE. When comparing ERG amplitudes for stimulation by strobe or Ganzfeld, the difference was least with the CLE compared to DTLE, CSCE, or SSE. The time taken to insert the four different electrodes was greatest for the CLE in both mice and rats. The extent of corneal abrasion resulting from electrode use

  19. Information needs for siting new, and evaluating current, nuclear facilities: ecology, fate and transport, and human health.

    Science.gov (United States)

    Burger, Joanna; Clarke, James; Gochfeld, Michael

    2011-01-01

    The USA is entering an era of energy diversity, and increasing nuclear capacity and concerns focus on accidents, security, waste, and pollution. Physical buffers that separate outsiders from nuclear facilities often support important natural ecosystems but may contain contaminants. The US Nuclear Regulatory Commission (NRC) licenses nuclear reactors; the applicant provides environmental assessments that serve as the basis for Environmental Impact Statements developed by NRC. We provide a template for the types of information needed for safe siting of nuclear facilities with buffers in three categories: ecological, fate and transport, and human health information that can be used for risk evaluations. Each item on the lists is an indicator for evaluation, and individual indicators can be selected for specific region. Ecological information needs include biodiversity (species, populations, communities) and structure and functioning of ecosystems, habitats, and landscapes, in addition to common, abundant, and unique species and endangered and rare ones. The key variables of fate and transport are sources of release for radionuclides and other chemicals, nature of releases (atmospheric vapors, subsurface liquids), features, and properties of environmental media (wind speed, direction and atmospheric stability, hydraulic gradient, hydraulic conductivity, groundwater chemistry). Human health aspects include receptor populations (demography, density, dispersion, and distance), potential pathways (drinking water sources, gardening, fishing), and exposure opportunities (lifestyle activities). For each of the three types of information needs, we expect that only a few of the indicators will be applicable to a particular site and that stakeholders should agree on a site-specific suite.

  20. Evaluating the efficiency of nuclear energy policies: an empirical examination for 26 countries.

    Science.gov (United States)

    Gozgor, Giray; Demir, Ender

    2017-08-01

    The decarbonization of the global economy is an urgent concern. As a potential solution, it can be important to understand the efficiency of nuclear energy policies. For this purpose, the paper analyzes whether there is a unit root in nuclear energy consumption in 26 countries and it uses the unit root tests with two endogenous (unknown) structural breaks. The paper finds that nuclear energy consumption is stationary around a level and the time trend in 25 of 26 countries and nuclear energy consumption contains a unit root only in France. The paper also discusses the potential implications of the findings.

  1. Evaluation of the Reference Numerical Parameters of the Monthly Method in ISO 13790 Considering S/V Ratio

    Directory of Open Access Journals (Sweden)

    Hee-Jeong Kwak

    2015-01-01

    Full Text Available Many studies have investigated the accuracy of the numerical parameters in the application of the quasi steady-state calculation method. The aim of this study is to derive the reference numerical parameters of the ISO 13790 monthly method by reflecting the surface-to-volume (S/V ratio and the characteristics of the structures. The calculation process was established, and the parameters necessary to derive the reference numerical parameters were calculated based on the input data prepared for the established calculation processes. The reference numerical parameters were then derived through regression analyses of the calculated parameters and the time constant. The parameters obtained from an apartment building and the parameters of the international standard were both applied to the Passive House Planning Package (PHPP and EnergyPlus programs, and the results were analyzed in order to evaluate the validity of the results. The analysis revealed that the calculation results based on the parameters derived from this study yielded lower error rates than those based on the default parameters in ISO 13790. However, the differences were shown to be negligible in the case of high heat capacity.

  2. Association and linkage analysis of COL1A1 and AHSG gene polymorphisms with femoral neck bone geometric parameters in both Caucasian and Chinese nuclear families.

    Science.gov (United States)

    Jiang, Hui; Lei, Shu-Feng; Xiao, Su-Mei; Chen, Yuan; Sun, Xiao; Yang, Fang; Li, Li-Ming; Wu, Shan; Deng, Hong-Wen

    2007-03-01

    To simultaneously investigate the contribution of the alpha 1 chain of collagen type 1 (COL1A1) and alpha2-HS-glycoprotein (AHSG) genes to the variation of bone geometric parameters in both Caucasians and Chinese. Six hundred and five Caucasian individuals from 157 nuclear families and 1228 Chinese subjects from 400 nuclear families were genotyped at the AHSG-SacI, COL1A1- PCOL2 and Sp1 polymorphisms using polymerase chain reaction (PCR)-restriction fragment length polymorphism (RFLP). 5 FN bone geometric parameters were calculated based on bone mineral density and bone area of femoral neck (FN) measured by dual energy X-ray absorptiometry. Population stratification, total family association, within-family association, and linkage tests were performed by the quantitative transmission disequilibrium test program. The t-test showed the significant differences of all bone geometric phenotypes (except ED) between Caucasians and Chinese in the offspring using both unadjusted and adjusted (by age, height, weight, and gender) data. In Caucasians, we found significant within-family association results between the COL1A1-Sp1 polymorphism (rs1800012) and cross sectional area (CSA), cortical thickness (CT), endocortical diameter (ED), buckling ratio (BR) (P=0.018, 0.002, 0.023, and 0.001, respectively); the COL1A1-Sp1 polymorphism also detected significant linkage with BR (P=0.039). In the population of China, the within-family associations between the COL1A1-PCOL2 polymorphism (rs1107946) and CT, BR were significant (P=0.012 and 0.008, respectively). Furthermore, evidence of linkage were observed between the AHSG-SacI polymorphism (rs4918) and CT, BR (P=0.042 and 0.014, respectively) in Caucasians, but not in Chinese. Our results suggest that the COL1A1 gene may have significantly association with bone geometry in both Caucasians and Chinese, and the AHSG gene may be linked to bone geometry in Caucasians, but not in Chinese. This study represents our first efforts on

  3. A Depletion Evaluation of PLUS7 16X16 Nuclear Fuel Assembly using TRITON

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Hyung Ju; Park, Kwang Heon; Hong, Ser Gi [Kyung Hee University, Yongin (Korea, Republic of)

    2016-05-15

    A nuclear criticality safety evaluation that applies burnup credit (BUC) to a DSC is performed mainly through a two-step process: (1) the determination of isotopic compositions within UNFs to be loaded into a DSC by a depletion analysis and (2) the determination of the k{sub eff} value with respect to the DSC by a criticality analysis . In particular, isotopic compositions by a depletion analysis should be estimated accurately because the nuclides, especially major actinides such as uranium or plutonium, contained in a UNF has a significant influence on a depletion analysis and the subsequent criticality analysis. One way for an accurate estimation of isotopic compositions is to apply accurate cross section libraries to a depletion analysis. In this work, the new one-group cross section libraries of the ORIGEN code were generated with respect to a domestic nuclear fuel assembly (NFA), PLUS7, with and without gadolinia rods using the SCALE 6.1/TRITON code. Then, one of the new libraries was applied to the SCALE 6.1/STARBUCS code to evaluate the effect of the k{sub eff} value. From the results calculated in these conditions, the following conclusions are drawn. (1) The fission and absorption cross-sections of two fissile nuclides generated from burnups of low-enriched NFAs had higher values than those of high-enriched NFAs, while the fission and absorption cross-sections of U-238 generated from burnups of low-enriched NFAs had lower values than those of high-enriched NFAs. (2) The fission and absorption cross-sections below approximately 15,000 MWD/MTU depended on the amount of gadolinia rods and the initial enrichment, while those above approximately 15,000 MWD/MTU depended on the only initial enrichment. (3) The applications of the new PLUS7 16X16 cross section library gave larger k{sub eff} values than the CE 16X16 cross-section library, except for a few cases. The effects of the new library on the k{sub eff} values ranged from -135 to 434 pcm in reactivity.

  4. Evaluation of Serum Resistin Levels and Metabolic Syndrome Related Parameters in Chronic Spontaneous Urticaria

    Directory of Open Access Journals (Sweden)

    Hanife Merve Akça

    2017-03-01

    Full Text Available Objective: To evaluate the relationship between the serum resistin levels and metabolic syndrome (MetS in chronic spontaneous urticaria (CSU patients. Methods: In the study 42 CSU patients and 42 healthy volunteers were included. Height, weight, waist circumference, and blood pressure measurements were assesed for both of the groups. Fasting blood sugar, serum lipid levels, resistin and tumor necrosis factor-alpha (TNF-α levels were evaluated in the venous blood samples. The metabolic syndrome (MetS diagnosis was determined using the National Cholesterol Education Program Adult Treatment Panel III diagnostic criteria. Results: MetS was found in 14 (33.3% CSU patients and 5 (11.9% control subjects. There was a statistically significant difference between the two groups (p=0.037 in terms of MetS presence. It was found that the mean serum resistin levels was 1928.31±212.85 pg/mL in the CSU patients and 2107.60±156.71 pg/mL in the control group. There was no statistically significant difference between the groups in terms of serum resistin levels. No difference was seen between the patients with and without a diagnosis of MetS regarding the urticaria activity score, duration of the disease, autologous serum skin test positivity, serum immunoglobulin E levels, presence of autoimmunity, serum resistin and TNF-α levels. Conclusion: An increased incidence of MetS in the CSU patient group is found in our study. However, there was no difference between the CSU patients with and without MetS regarding the disorder-associated parameters and the serum resistin and TNF-α levels.

  5. Updating Nutritional Data and Evaluation of Technological Parameters of Italian Milk.

    Science.gov (United States)

    Manzi, Pamela; Di Costanzo, Maria Gabriella; Mattera, Maria

    2013-06-20

    Different technologically treated Italian milks (whole and semi-skimmed ultra-high temperature (UHT), pasteurized and microfiltered milk), collected from 2009 to 2012, were evaluated for nutritional and technological properties. No significant differences in calcium and sodium were detected ( p > 0.05), while significant differences were observed concerning phosphorus content, between whole and semi-skimmed milk, and lactose content, between pasteurized and UHT milk ( p UHT milk, lactose isomerization occurred, and lactulose (from 8.6 to 104.0 mg/100 g) was detected. No significant differences ( p > 0.05) were detected for choline, a functional molecule, between whole (11.3-14.6 mg/100 g) and semi-skimmed milk (11.1-14.7 mg/100 g), but there were significant differences ( p milk (UHT vs. pasteurized milk and UHT vs. microfiltered milk). Among the unsaponifiable compounds, only 13 cis retinol and trans retinol showed differences in technologically treated milk (pasteurized vs. UHT milk and microfiltered vs. UHT milk; p milk treatment, the higher was the percent ratio 13 cis / trans retinol (DRI, degree of retinol isomerization). The degree of antioxidant protection parameter (DAP), useful to estimate the potential oxidative stability of fat in foods, was significantly different between whole and semi-skimmed milk ( p milk showed a good correlation between beta carotene and b * ( r = 0.854) and between lactulose and a * ( r = 0.862).

  6. Evaluation of Laboratory Parameters in Patients Receiving Isotretinoin For Treatment of Acne Vulgaris

    Directory of Open Access Journals (Sweden)

    Arzu Ataseven

    2013-09-01

    Full Text Available Objective: Oral isotretinoin (13-cis retinoic acid is the most effective medication in the treatment of acne vulgaris. The present study investigates the changes in the parameters such as lipid profile, liver enzymes, urea and creatinine, following the oral retinoic acid treatment in patients with acne vulgaris. Methods: The study group consisted of 110 patients who presented to the dermatology clinic of Konya Research and Training Hospital; they were clinically diagnosed with acne and received isotretinoin treatment. The levels of total cholesterol, triglyceride, high-density lipoprotein (HDL, low-density lipoprotein (LDL, alanine aminotranspherase (ALT, aspartate aminotranspherase (AST, urea and creatinine were evaluated retrospectively prior to and three months after the treatment. Results: When the levels prior to and following the treatment were compared, total cholesterol, triglyceride and AST were significantly increased (p0.05. Conclusion: The levels of serum lipids should be closely monitored during isotretinoin treatment, which is an effective agent particularly in the severe form of acne.

  7. Evaluating the spatio-temporal factors that structure network parameters of plant-herbivore interactions.

    Directory of Open Access Journals (Sweden)

    Antonio López-Carretero

    Full Text Available Despite the dynamic nature of ecological interactions, most studies on species networks offer static representations of their structure, constraining our understanding of the ecological mechanisms involved in their spatio-temporal stability. This is the first study to evaluate plant-herbivore interaction networks on a small spatio-temporal scale. Specifically, we simultaneously assessed the effect of host plant availability, habitat complexity and seasonality on the structure of plant-herbivore networks in a coastal tropical ecosystem. Our results revealed that changes in the host plant community resulting from seasonality and habitat structure are reflected not only in the herbivore community, but also in the emergent properties (network parameters of the plant-herbivore interaction network such as connectance, selectiveness and modularity. Habitat conditions and periods that are most stressful favored the presence of less selective and susceptible herbivore species, resulting in increased connectance within networks. In contrast, the high degree of selectivennes (i.e. interaction specialization and modularity of the networks under less stressful conditions was promoted by the diversification in resource use by herbivores. By analyzing networks at a small spatio-temporal scale we identified the ecological factors structuring this network such as habitat complexity and seasonality. Our research offers new evidence on the role of abiotic and biotic factors in the variation of the properties of species interaction networks.

  8. Evaluation of reconstruction parameters of electrical impedance tomography on aorta detection during saline bolus injection

    Directory of Open Access Journals (Sweden)

    Thürk Florian

    2016-09-01

    Full Text Available An accurate detection of anatomical structures in electrical impedance tomography (EIT is still at an early stage. Aorta detection in EIT is of special interest, since it would favor non-invasive assessment of hemodynamic processes in the body. Here, diverse EIT reconstruction parameters of the GREIT algorithm were systematically evaluated to detect the aorta after saline bolus injection in apnea. True aorta position and size were taken from computed tomography (CT. A comparison with CT showed that the smallest error for aorta displacement was attained for noise figure nf = 0.7, weighting radius rw = 0.15, and target size ts = 0.01. The spatial extension of the aorta was most precise for nf = 0.7, rw = 0.25, and ts = 0.07. Detection accuracy (F1-score was highest with nf = 0.6, rw = 0.15, and ts = 0.04. This work provides algorithm-related evidence for potentially accurate aorta detection in EIT after injection of a saline bolus.

  9. Evaluation of some cardiovascular risk parameters in health professionals exposed to night work.

    Science.gov (United States)

    Caciari, T; Tomei, G; De Sio, S; Capozzella, A; Schifano, M P; Trovè, L; Casale, T; Cardella, C; Tomei, F; Rosati, M V

    2013-01-01

    Shift work and night work in particular represent a risk factor for the health of exposed workers; aim of our study is to evaluate whether night work may cause alteration of some cardiovascular risk parameters in health workers. The research was carried out on 415 health workers, 163 exposed to night work and 252 not exposed. A blood sample was taken from each worker, between 8.00 a.m. and 10.00 a.m. before lunch time, to test total cholesterol, HDL cholesterol, and triglycerides. Blood pressure and heart rate were also measured. Workers with cardiovascular diseases, thyroid diseases, diabetes mellitus, dyslipidemia, those who made use of antihypertensive drugs, hypoglycemic and/or lipid-lowering drugs, subjects with body mass index (BMI) (kg/m2) higher than 30 were excluded. In the group of exposed compared to controls, increasing values of arterial pressure and heart rate, were not significant. The mean values of total cholesterol and triglycerides were significantly higher in exposed compared to controls while values of HDL cholesterol were significantly lower. Night workers have clinically significant changes in blood levels of total cholesterol, HDL cholesterol and triglycerides, such alterations are presumably related to poor food hygiene and to psychosocial stressors.

  10. Evaluation of tropical plants containing tannin on in vitro methanogenesis and fermentation parameters using rumen fluid.

    Science.gov (United States)

    Hariadi, Bambang Tjahyono; Santoso, Budi

    2010-02-01

    Methane (CH(4)) produced during ruminal fermentation represents a loss of 10-11% of gross energy intake. The use of browse species containing tannin as feed supplement for ruminants tends to increase in order to reduce CH(4) production. The present study was conducted to evaluate some tropical plants containing tannin as feed supplement (200 g kg(-1)) on in vitro CH(4) production and fermentation parameters. The crude protein (CP) content ranged from 87 to 390 g kg(-1) dry matter (DM) and was highest in Sesbania grandiflora (L.) Poiret. The neutral detergent fibre (NDF) concentration was highest in Pennisetum purpureum Schumach (725 g kg(-1) DM) and lowest in S. grandiflora (330 g kg(-1) DM). The ranking order of plants based on their total tannin content was Acacia mangium Willd. > Biophytum petersianum Klotzch > Jatropa curcas Linnaeus > Psidium guajava Linnaeus > Phaleria papuana > Persea americana Mill. > S. grandiflora. Methane gas production after 48 h of incubation was significantly (P mangium (PP + AM), B. petersianum (PP + BP), J. curcas (PP + JC) or P. guajava (PP + PG) as compared to control feed (PP). There was negative correlation between total tannin content and CH(4) production at 48 h of incubation (r = - 0.76). Concentration NH(3)-N was significantly (P mangium, B. petersianum, J. curcas and P. guajava have potential to be used as a feed supplement to reduce CH(4) production in ruminants.

  11. Low-level laser therapy on skeletal muscle inflammation: evaluation of irradiation parameters

    Science.gov (United States)

    Mantineo, Matías; Pinheiro, João P.; Morgado, António M.

    2014-09-01

    We evaluated the effect of different irradiation parameters in low-level laser therapy (LLLT) for treating inflammation induced in the gastrocnemius muscle of rats through cytokines concentration in systemic blood and analysis of muscle tissue. We used continuous (830 and 980 nm) and pulsed illuminations (830 nm). Animals were divided into five groups per wavelength (10, 20, 30, 40, and 50 mW), and a control group. LLLT was applied during 5 days with a constant irradiation time and area. TNF-α, IL-1β, IL-2, and IL-6 cytokines were quantified by ELISA. Inflammatory cells were counted using microscopy. Identical methodology was used with pulsed illumination. Average power (40 mW) and duty cycle were kept constant (80%) at five frequencies (5, 25, 50, 100, and 200 Hz). For continuous irradiation, treatment effects occurred for all doses, with a reduction of TNF-α, IL-1β, and IL-6 cytokines and inflammatory cells. Continuous irradiation at 830 nm was more effective, a result explained by the action spectrum of cytochrome c oxidase (CCO). Best results were obtained for 40 mW, with data suggesting a biphasic dose response. Pulsed wave irradiation was only effective for higher frequencies, a result that might be related to the rate constants of the CCO internal electron transfer process.

  12. Clinical evaluation of an ionic tooth brush on oral hygiene status, gingival status, and microbial parameter

    Directory of Open Access Journals (Sweden)

    Deshmukh J

    2006-01-01

    Full Text Available It has long been recognised that the presence of dental plaque leads to gingivitis and periodontal disease, as well as dental caries. Today tooth brushing is the most widely accepted method of removing plaque. Hence this present clinical study was undertaken to evaluate the effectiveness of an ionic toothbrush on oral hygiene status. For this study, 20 dental students in the age group of 18-20 years were included. All the subjects after undergoing dental prophylaxis were then provided with ionic toothbrushes, either active (equipped with lithium battery or inactive (without lithium battery. Plaque index and gingival bleeding index were examined at 7th, 14th, and 21st day. Microbial assessment was done for detection of colony forming units (CFU from the plaque samples which were collected on 0 day and 21st day, both before brushing and after brushing. Results shown a significant reduction in all the parameters and the reduction was more significant in active and inactive ionic toothbrush users. It was concluded that both active and inactive ionic toothbrushes reduced the plaque index and gingival bleeding index scores significantly and active ionic tooth brushes were more effective as compared to inactive ionic toothbrushes. There was no soft tissue trauma following the use of both type of toothbrushes, which showed that ionic toothbrushes were equally safe for regular long-term use.

  13. Transmission avoided cost: a new parameter to evaluate the economic competitiveness of generations plants projects

    Energy Technology Data Exchange (ETDEWEB)

    Ramos, D.S. [Companhia Energetica de Sao Paulo, SP (Brazil); Albuquerque, J.C.R.; Rosenblat, J. [ELETROBRAS, Rio de Janeiro, RJ (Brazil)

    1994-12-31

    The paper presents a new formulation that makes feasible a composition of long run production marginal costs with the long run transmission marginal costs, including the costs related to the interconnection EHV networks and that related to the voltage levels below. The goal top be attained is to have available a more adequate parameter in order to compare production cost related to a plant, that will be connected to a certain voltage level network, to the cost related supplying the sam,e amount of energy from the bulk power system which will be represented by the marginal costs up to the voltage level under consideration. This procedure brings to light the Transmission Avoided Costs concepts, that are stressed throughout the text. The proposed methodology is now being used, in the brazilian Power Sector, as a rule of thumb in order to guide planning decisions about the schedule of new plants that have installed capacity below 30 MW. For plants with higher capacity, the transmission avoided costs are evaluated for each specific case, simulating the system behavior without the quoted hydroelectric plant. This paper focuses, an an application example, the case of the Canoas Hydroelectric Project, recently included in the Generation Expansion Reference Plan after a detailed analysis supported by the methodology described here. (author) 7 refs., 3 tabs.

  14. Statistical evaluation of hydrobiological parameters of Narmada River water at Hoshangabad City, India.

    Science.gov (United States)

    Sharma, Shraddha; Dixit, Savita; Jain, Praveen; Shah, K W; Vishwakarma, Rakesh

    2008-08-01

    Narmada is considered to be the lifeline of the state of Madhya Pradesh in Central India. The Narmada water is used for bathing, drinking, irrigation and industrial purposes. The city sewage and industrial effluent from Security paper mill at Hoshangabad drains in the Narmada River and pollutes the water quality. Urban sewage enters into Narmada through main nallas. River water quality at Hoshangabad has become a matter of concern due to continuous changing environment and increasing social and industrial activity that influence the water quality directly or indirectly. The present investigation is undertaken to study the effect of domestic sewage and effluent from Security paper Mill on the water quality and ecology of river Narmada at Hoshangabad. The study is carried on at four sites along with the bank of river Narmada. Water samples from four stations were collected, out of which three main sewage mixing points of the city and one fresh water site are taken into account. The samples collected were analyzed, as per standard methods parameters such as Temperature, pH, were measured in-situ. The statistical evaluations were also made. The result showed increase in BOD, Nitrates, Phosphates and Total Coliforms, No. of phytoplanktons. The results revealed that most of the water samples were below or out of limited; according to the WHO, BIS standards.

  15. Evaluation of uric acid levels, thyroid function, and anthropometric parameters in Japanese children with Down syndrome.

    Science.gov (United States)

    Niegawa, Tomomi; Takitani, Kimitaka; Takaya, Ryuzo; Ishiro, Manabu; Kuroyanagi, Yuichi; Okasora, Keisuke; Minami, Yukako; Matsuda, Takuya; Tamai, Hiroshi

    2017-09-01

    Down syndrome, caused by trisomy 21, is characterized by congenital abnormalities as well as mental retardation. From the neonatal stage through adolescence, patients with Down syndrome often have several complications. Thus, it is important to attain knowledge of the prevalence of these comorbidities in children with Down syndrome. We, therefore, evaluated the biochemical data, thyroid function, and anthropometric parameters, and analyzed the association among them in Japanese children and early adolescents with Down syndrome. There was no difference in the prevalence of obesity and overweight between boys and girls. The level of uric acid was higher in boys than in girls. Moreover, the prevalence of hyperuricemia was also higher in boys than in girls (approximately 32% and 10%, respectively). The prevalence of subclinical hypothyroidism in children with Down syndrome was approximately 20%, with no significant sex differences. The levels of uric acid and dehydroepiandrosterone-sulfate were positively associated with age, while the levels of thyroid-stimulating hormone and free thyroxine had a negative association with age. Overall, children with Down syndrome, exhibit a higher incidence of hyperuricemia. Therefore, uric acid levels, as well as thyroid function, from childhood to early adulthood should be monitored in this patient cohort.

  16. 20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez, Amanda Ann

    2008-09-01

    The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

  17. Evaluation of uncertainties of key neutron parameters of PWR-type reactors with slab fuel, application to neutronic conformity; Determination des incertitudes liees aux grandeurs neutroniques d'interet des reacteurs a eau pressurisee a plaques combustibles et application aux etudes de conformite

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, D

    2001-12-01

    The aim of this thesis was to evaluate uncertainties of key neutron parameters of slab reactors. Uncertainties sources have many origins, technologic origin for parameters of fabrication and physical origin for nuclear data. First, each contribution of uncertainties is calculated and finally, a factor of uncertainties is associated to key slab parameter like reactivity, isotherm reactivity coefficient, control rod efficiency, power form factor before irradiation and life-time. This factors of uncertainties were computed by Generalized Perturbations Theory in case of step 0 and by directs calculations in case of irradiation problems. One of neutronic conformity applications was about fabrication and nuclear data targets precision adjustments. Statistic (uncertainties) and deterministic (deviations) approaches were studied. Then, neutronics key slab parameters uncertainties were reduced and so nuclear performances were optimized. (author)

  18. From bare interactions, low-energy constants, and unitary gas to nuclear density functionals without free parameters: Application to neutron matter

    Science.gov (United States)

    Lacroix, Denis; Boulet, Antoine; Grasso, Marcella; Yang, C.-J.

    2017-05-01

    We further progress along the line of Ref. [D. Lacroix, Phys. Rev. A 94, 043614 (2016), 10.1103/PhysRevA.94.043614] where a functional for Fermi systems with anomalously large s -wave scattering length as was proposed that has no free parameters. The functional is designed to correctly reproduce the unitary limit in Fermi gases together with the leading-order contributions in the s - and p -wave channels at low density. The functional is shown to be predictive up to densities ˜0.01 fm-3 that is much higher densities compared to the Lee-Yang functional, valid for ρ functional retained in this work is further motivated. It is shown that the new functional corresponds to an expansion of the energy in (askF) and (rekF) to all orders, where re is the effective range and kF is the Fermi momentum. One conclusion from the present work is that, except in the extremely low-density regime, nuclear systems can be treated perturbatively in -(askF) -1 with respect to the unitary limit. Starting from the functional, we introduce density-dependent scales and show that scales associated with the bare interaction are strongly renormalized by medium effects. As a consequence, some of the scales at play around saturation are dominated by the unitary gas properties and not directly by low-energy constants. For instance, we show that the scale in the s -wave channel around saturation is proportional to the so-called Bertsch parameter ξ0 and becomes independent of as. We also point out that these scales are of the same order of magnitude than those empirically obtained in the Skyrme energy density functional. We finally propose a slight modification of the functional such that it becomes accurate up to the saturation density ρ ≃0.16 fm-3.

  19. Nuclear Data Evaluation for Mass Chain A=217:Odd-Proton Nuclei.

    Directory of Open Access Journals (Sweden)

    Sherif S Nafee

    Full Text Available Thallium (81(217Tl, Bismuth (83(217Bi, Astatine (85(217At, Francium (87(217Fr, Actinium (89(217Ac and Protactinium (91(217Pa are of odd-proton numbers among the mass chain A = 217. In the present work, the half-lives and gamma transitions for the six nuclei have been studied and adopted based on the recently published interactions or unevaluated nuclear data sets XUNDL. The Q (α has been updated based on the recent published work of the Atomic Mass Evaluation AME2012 as well. Moreover, the total conversion electrons as well as the K-Shell to L-Shell, L-Shell to M-Shell and L-Shell to N-Shell Conversion Electron Ratios have been calculated using BrIcc code v2.3. An updated skeleton decay scheme for each of the above nuclei has been presented here. The decay hindrance factors (HF calculated using the ALPHAD program, which is available from Brookhaven National Laboratory's website, have been calculated for the α- decay data sets for (221Fr-, (221Ac- and (221Pa-α-decays.

  20. Nuclear Data Evaluation for Mass Chain A=217:Odd-Proton Nuclei.

    Science.gov (United States)

    Nafee, Sherif S; Shaheen, Salem A; Al-Ramady, Amir M

    2016-01-01

    Thallium (81(217)Tl, Bismuth (83(217)Bi), Astatine (85(217)At), Francium (87(217)Fr), Actinium (89(217)Ac) and Protactinium (91(217)Pa) are of odd-proton numbers among the mass chain A = 217. In the present work, the half-lives and gamma transitions for the six nuclei have been studied and adopted based on the recently published interactions or unevaluated nuclear data sets XUNDL. The Q (α) has been updated based on the recent published work of the Atomic Mass Evaluation AME2012 as well. Moreover, the total conversion electrons as well as the K-Shell to L-Shell, L-Shell to M-Shell and L-Shell to N-Shell Conversion Electron Ratios have been calculated using BrIcc code v2.3. An updated skeleton decay scheme for each of the above nuclei has been presented here. The decay hindrance factors (HF) calculated using the ALPHAD program, which is available from Brookhaven National Laboratory's website, have been calculated for the α- decay data sets for (221)Fr-, (221)Ac- and (221)Pa-α-decays.

  1. Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2002-01-01

    1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from ...

  2. Evaluation of a Business Case for Safeguards by Design in Nuclear Power Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Wood, Thomas W.; Seward, Amy M.; Lewis, Valerie A.; Gitau, Ernest TN; Zentner, Michael D.

    2012-12-01

    Safeguards by Design (SbD) is a well-known paradigm for consideration and incorporation of safeguards approaches and associated design features early in the nuclear facility development process. This paradigm has been developed as part of the Next Generation Safeguards Initiative (NGSI), and has been accepted as beneficial in many discussions and papers on NGSI or specific technologies under development within NGSI. The Office of Nuclear Safeguards and Security funded the Pacific Northwest National Laboratory to examine the business case justification of SbD for nuclear power reactors. Ultimately, the implementation of SbD will rely on the designers of nuclear facilities. Therefore, it is important to assess the incentives which will lead designers to adopt SbD as a standard practice for nuclear facility design. This report details the extent to which designers will have compelling economic incentives to adopt SbD.

  3. Evaluation of Quercetin Content, Colour and Selected Physico-Chemical Quality Parameters of Croatian Blackberry Wines

    Directory of Open Access Journals (Sweden)

    Klarić Daniela Amidžić

    2017-03-01

    Full Text Available Blackberry wine, the most widespread Croatian fruit wine, is produced by yeast fermentation of raw blackberry juice or must. Even though the production and intake of blackberry wine in Croatia has been increasing for years, the available data on the overall quality and blackberry wine composition is still scarce. The objective of this work was to evaluate the quercetin content, colour and selected physico-chemical quality parameters of 15 Croatian blackberry wine samples, divided into two groups denominated as CWB and OWB regarding the blackberries’ cultivation type (conventional and organic. The quercetin content ranged from 0.81 to 21.67 mg/L (average: 6.16 mg/L, median 3.96 mg/L and was consistent with some published studies. Compared to CBW group, quercetin content of OBW samples seemed to be more balanced and slightly higher (OBW median: 3.99 mg/L, CWB median: 1.80 mg/L. The presence of cyanidin and pelargonidin (as aglycons was detected in very low concentrations in four and seven samples, respectively. Determination of the colour revealed that the most important component contributing to colour intensity was yellow (51 %, followed by red (40 %. The chemical quality parameters were in accordance with the available published results on blackberry and grape wines and were as follows: relative density 1.0017–1.0660 g/mL, concentration of reducing sugars 13.5–177.6 g/L, alcoholic strength 9.37–14.78% vol, pH 3.11–3.56, total acidity 6.7–18.1 g/L, ash 1.59–4.11 g/L, alkalinity of ash 1.54–3.79 g/L, total nitrogen 65.50–361.15 mg/L, and total phosphorus 32.03–118.53 mg/L. No significant overall differences were noticed between the conventional and organic group of samples.

  4. Evaluation of geostatistical parameters based on well tests; Estimation de parametres geostatistiques a partir de tests de puits

    Energy Technology Data Exchange (ETDEWEB)

    Gauthier, Y.

    1997-10-20

    Geostatistical tools are increasingly used to model permeability fields in subsurface reservoirs, which are considered as a particular random variable development depending of several geostatistical parameters such as variance and correlation length. The first part of the thesis is devoted to the study of relations existing between the transient well pressure (the well test) and the stochastic permeability field, using the apparent permeability concept.The well test performs a moving permeability average over larger and larger volume with increasing time. In the second part, the geostatistical parameters are evaluated using well test data; a Bayesian framework is used and parameters are estimated using the maximum likelihood principle by maximizing the well test data probability density function with respect to these parameters. This method, involving a well test fast evaluation, provides an estimation of the correlation length and the variance over different realizations of a two-dimensional permeability field

  5. Evaluation of environmental data relating to selected nuclear power plant sites. The Zion Nuclear Power Station site

    Energy Technology Data Exchange (ETDEWEB)

    Murarka, I.P.; Policastro, A.; Daniels, E.; Ferrante, J.; Vaslow, F.

    1976-11-01

    Environmental monitoring data for the years 1972 through 1975 pertaining to the Zion Station, which began commercial operation in 1974, were analyzed by the most practical qualitative and quantitative methods. Thermal plume, water chemistry and aquatic biota data were evaluated and the results are presented. The results showed no significant immediate deleterious effects, thus confirming preoperational predictions. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data utilized, the methods of analysis, and the results obtained are presented in detail, along with recommendations for improving monitoring techniques.

  6. Evaluation and assessment of 25 years of environmental radioactivity monitoring data at Tarapur (India) nuclear site.

    Science.gov (United States)

    Rao, D D; Baburajan, A; Sudheendran, V; Verma, P C; Hegde, A G

    2010-08-01

    The evaluation and assessment of monitoring data generated over a period of 1983-2007 (25 years) of a nuclear facility is presented. Time trends of particulate radioactivity, correlation between (137)Cs in discharge canal seawater and station discharged activity and correlation of (137)Cs, (60)Co, and (131)I in marine species such as sponge and Nerita (gastropod) and corresponding discharged activity are discussed. The concentration of (137)Cs and (131)I in seawater versus biota are discussed. A good correlation between (137)Cs in seawater and (137)Cs in liquid waste discharged was observed (R(2) = 0.8, p Nerita and discharged concentration of (137)Cs, (131)I and (60)Co (R(2) = 0.55-0.73 and p < 0.001). The measurements over the years indicated that there is no accumulation of radionuclides in either the terrestrial or aquatic environments. The mean (137)Cs decreased from the pre-operational levels: 7.0-3.6 Bq kg(-1) in soil, 0.91-0.016 Bq L(-1) in milk and 0.28-0.036 Bq kg(-1) in vegetation. Similarly, the mean (90)Sr in these matrixes decreased from 3.9 to 0.26 Bq kg(-1); 0.37-0.011 Bq L(-1) and 0.34-0.022 Bq kg(-1) respectively. Cesium-137 of about 700 microBq m(-3) was measured in the air filter disks during 1986 and there was a decrease of three orders of magnitude in concentration over the 25 years. The evaluation of environmental data indicated that the radionuclide concentrations and potential impacts, in terms of effective dose to the members of public, have significantly reduced since 1969. Copyright 2010 Elsevier Ltd. All rights reserved.

  7. Evaluation and assessment of 25 years of environmental radioactivity monitoring data at Tarapur (India) nuclear site

    Energy Technology Data Exchange (ETDEWEB)

    Rao, D.D., E-mail: raoddev@rediffmail.co [Environmental Survey Laboratory, Tarapur Atomic Power Station Staff Colony, TAPP (Post), Thane 401 504 (Dist.), Maharashtra State (India); Baburajan, A.; Sudheendran, V. [Environmental Survey Laboratory, Tarapur Atomic Power Station Staff Colony, TAPP (Post), Thane 401 504 (Dist.), Maharashtra State (India); Verma, P.C.; Hegde, A.G. [Health Physics Division, Health, Safety and Environment Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India)

    2010-08-15

    The evaluation and assessment of monitoring data generated over a period of 1983-2007 (25 years) of a nuclear facility is presented. Time trends of particulate radioactivity, correlation between {sup 137}Cs in discharge canal seawater and station discharged activity and correlation of {sup 137}Cs, {sup 60}Co, and {sup 131}I in marine species such as sponge and Nerita (gastropod) and corresponding discharged activity are discussed. The concentration of {sup 137}Cs and {sup 131}I in seawater versus biota are discussed. A good correlation between {sup 137}Cs in seawater and {sup 137}Cs in liquid waste discharged was observed (R{sup 2} = 0.8, p < 0.001). Similarly, correlation was good for Nerita and discharged concentration of {sup 137}Cs, {sup 131}I and {sup 60}Co (R{sup 2} = 0.55-0.73 and p < 0.001). The measurements over the years indicated that there is no accumulation of radionuclides in either the terrestrial or aquatic environments. The mean {sup 137}Cs decreased from the pre-operational levels: 7.0-3.6 Bq kg{sup -1} in soil, 0.91-0.016 Bq L{sup -1} in milk and 0.28-0.036 Bq kg{sup -1} in vegetation. Similarly, the mean {sup 90}Sr in these matrixes decreased from 3.9 to 0.26 Bq kg{sup -1}; 0.37-0.011 Bq L{sup -1} and 0.34-0.022 Bq kg{sup -1} respectively. Cesium-137 of about 700 {mu}Bq m{sup -3} was measured in the air filter disks during 1986 and there was a decrease of three orders of magnitude in concentration over the 25 years. The evaluation of environmental data indicated that the radionuclide concentrations and potential impacts, in terms of effective dose to the members of public, have significantly reduced since 1969.

  8. New approaches to provide feedback from nuclear and covariance data adjustment for effective improvement of evaluated nuclear data files

    Energy Technology Data Exchange (ETDEWEB)

    Palmiotti, Giuseppe; Salvatores, Massimo; Hursin, Mathieu; Kodeli, Ivo; Gabrielli, Fabrizio; Hummel, Andrew

    2016-11-01

    A critical examination of the role of uncertainty assessment, target accuracies, role of integral experiment for validation and, consequently, of data adjustments methods is underway since several years at OECD-NEA, the objective being to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and experimentalists in order to improve without ambiguities the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications and to meet new requirements and constraints for innovative reactor and fuel cycle system design. An approach will be described that expands as much as possible the use in the adjustment procedure of selected integral experiments that provide information on “elementary” phenomena, on separated individual physics effects related to specific isotopes or on specific energy ranges. An application to a large experimental data base has been performed and the results are discussed in the perspective of new evaluation projects like the CIELO initiative.

  9. New approaches to provide feedback from nuclear and c