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1

PC(Note PC catalogue) (Machine body)  

E-Print Network [OSTI]

Specifications PC PC Code Image Brand Model PC Kingsoft Office Plus () ESET SMART () Kingsoft Office Microsoft Wireless LAN Remarks Specifications PC PC Code Image Brand Model K012 Fujitsu LOOK FMVLR7YN24 Core2DUO Weight (Machine body) Accessory LAN Wireless LAN Remarks Specifications PC PC Code Image Brand

Katsumoto, Shingo

2

Solubility of Sugars and Sugar Alcohols in Ionic Liquids: Measurement and PC-SAFT Modeling  

Science Journals Connector (OSTI)

Solubility of Sugars and Sugar Alcohols in Ionic Liquids: Measurement and PC-SAFT Modeling ... The measured data as well as previously published solubility data of glucose and fructose in these ILs were modeled by means of PC-SAFT using a molecular-based associative approach for ILs. ... PC-SAFT was used in this work as it has shown to be applicable to model the solubility of xylitol and sorbitol in ILs (Paduszy?ski; et al. ...

Aristides P. Carneiro; Christoph Held; Oscar Rodríguez; Gabriele Sadowski; Eugénia A. Macedo

2013-07-30T23:59:59.000Z

3

Nuclear Systems Modeling, Simulation & Validation | Nuclear Science...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Research Areas Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation...

4

PC-Based Modeling and Simulation of Large Marine Propulsion Plant  

Science Journals Connector (OSTI)

At present, most of marine engine room simulators (MERS) in the ... So a simulation system of a PC-Based marine propulsion plant has been developed for training. In ... paper, a transient simulation model for lar...

Sun Jianbo; Guo Chen

2010-01-01T23:59:59.000Z

5

Modeling Poly(N-isopropylacrylamide) Hydrogels in Water/Alcohol Mixtures with PC-SAFT  

Science Journals Connector (OSTI)

Modeling Poly(N-isopropylacrylamide) Hydrogels in Water/Alcohol Mixtures with PC-SAFT ... The PC-SAFT equation of state is used for thermodynamic modeling of poly(N-isopropylacrylamide) PNIPAAm in water and alcohols (methanol, ethanol, 1-propanol, and 2-propanol). ... The statistical association fluid theory (SAFT) developed by Chapman et al.,(42) a generally accepted and powerful equation of state based on statistical thermodynamics, provides an excellent framework for a variety of extensions and modifications. ...

Markus C. Arndt; Gabriele Sadowski

2012-07-30T23:59:59.000Z

6

PC-SAFT modeling of asphaltene phase behavior in the presence of nonionic dispersants  

Science Journals Connector (OSTI)

Abstract This study introduced a new method to characterize asphaltenes in PC-SAFT equation of state (EOS) and correctly model the effect of nonionic dispersants on the thermodynamic behavior of asphaltenes. Our approach is to combine microscale parameters from Molecular Dynamics (MD) simulations with Perturbed Chain Statistical Associating Fluid Theory (PC-SAFT) to develop a comprehensive model that enables the prediction of macroscopic behavior such as the amount and onset of asphaltene precipitation at various pressures, temperatures, and fluid compositions. More specifically, association parameters were considered for asphaltene molecules and determined by equating the Gibbs energy of association calculated by PC-SAFT EOS to the one obtained from MD simulations. A correlation was derived to relate the association energy parameter (?AB) of asphaltenes to the molar weight of their aromatic cores. Our model showed that asphaltene association energy is affected by temperature and solvent type and is inversely proportional to the solubility parameter of the medium. The hetero-segment approach in PC-SAFT EOS was adopted to accurately characterize asphaltene molecules and their non-association parameters in PC-SAFT were determined based on the molecular weight and aromaticity factor of asphaltenes. Moreover, the average aggregation number of asphaltene nanoaggregates was calculated using the Wertheim association theory. This model was applied to predict asphaltene precipitation envelopes for three different live crude oils and showed excellent agreement with experimental data in the literature. Additionally, the model could correctly predict the amount of asphaltene precipitation upon addition of nonionic dispersants.

Mohammad Sedghi; Lamia Goual

2014-01-01T23:59:59.000Z

7

ForestGALES A PC-based wind risk model  

E-Print Network [OSTI]

agreement and warranty. You shall not alter, modify or reverse engineer the original software or give anyone by the model as they are regarded as indicative and not prescriptive. NO RESPONSIBILITY FOR LOSS OCCASIONED environments into which ForestGALES may be put, NO WARRANTY OF FITNESS FOR A PARTICULAR PURPOSE IS OFFERED

8

Modeling of molecular gas adsorption isotherms on porous materials with hybrid PC-SAFT–DFT  

Science Journals Connector (OSTI)

Abstract The developed hybrid PC-SAFT–DFT model, a coupling of density functional theory (DFT) with perturbed-chain statistical associating fluid theory (PC-SAFT), was used to study the adsorption of pure- and mixed-fluids on nano-porous materials, and carbons and zeolites were chosen as examples of nano-porous materials in this work for model performance evaluation. In the PC-SAFT–DFT model, the modified fundamental measure theory was used for the hard sphere contribution, the dispersion free energy functional was represented with a weighted density approximation, and the chain free energy functional from interfacial SAFT was used to account for the chain connectivity. The fluid was modeled as a chain molecule with molecular parameters taken from those in the bulk PC-SAFT. The external force field was used to describe the interaction between the solid surface of a nano-porous material and fluid. Application of this model was demonstrated on the gas adsorption on porous carbons and zeolites which were assumed to have slit- and cylinder-shaped pores with mean pore sizes, respectively. The parameters of the adsorption model were obtained by fitting to the pure-gas adsorption isotherms measured experimentally. With parameters of the model fitted to the pure-gas adsorption at one temperature, the model was used to predict the pure-gas adsorption at other temperatures as well as the adoption isotherms of mixtures. The model prediction was compared with the available experimental data, which shows that the predictions are reliable for most of the systems studied in this work. The effect of the pore size distribution on the model performance was further investigated, and it was found that the consideration of the pore size distribution (PSD) can improve the accuracy of the model results but the PSD analysis requires much more computing time.

Gulou Shen; Xiaohua Lu; Xiaoyan Ji

2014-01-01T23:59:59.000Z

9

Survey of thermal-hydraulic models of commercial nuclear power plants  

SciTech Connect (OSTI)

A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC`s current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described.

Determan, J.C.; Hendrix, C.E.

1992-12-01T23:59:59.000Z

10

Survey of thermal-hydraulic models of commercial nuclear power plants  

SciTech Connect (OSTI)

A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC's current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described.

Determan, J.C.; Hendrix, C.E.

1992-12-01T23:59:59.000Z

11

Nuclear models relevant to evaluation  

SciTech Connect (OSTI)

The widespread use of nuclear models continues in the creation of data evaluations. The reasons include extension of data evaluations to higher energies, creation of data libraries for isotopic components of natural materials, and production of evaluations for radiative target species. In these cases, experimental data are often sparse or nonexistent. As this trend continues, the nuclear models employed in evaluation work move towards more microscopically-based theoretical methods, prompted in part by the availability of increasingly powerful computational resources. Advances in nuclear models applicable to evaluation will be reviewed. These include advances in optical model theory, microscopic and phenomenological state and level density theory, unified models that consistently describe both equilibrium and nonequilibrium reaction mechanism, and improved methodologies for calculation of prompt radiation from fission. 84 refs., 8 figs.

Arthur, E.D.; Chadwick, M.B.; Hale, G.M.; Young, P.G.

1991-01-01T23:59:59.000Z

12

Computer aided nuclear reactor modeling  

E-Print Network [OSTI]

Nuclear reactor modeling is an important activity that lets us analyze existing as well as proposed systems for safety, correct operation, etc. The quality of a analysis is directly proportional to the quality of the model used. In this work we look...

Warraich, Khalid Sarwar

2012-06-07T23:59:59.000Z

13

Nuclear Shell Model  

E-Print Network [OSTI]

There are similarities between the electronic structure of atoms and nuclear structure. Atomic electrons are arranged in orbits (energy states) subject to the laws of quantum mechanics. The distribution of electrons in these states follows the Pauli exclusion principle. Atomic electrons can be excited up to normally unoccupied states, or they can be removed completely from the atom. From such phenomena one can deduce the structure of atoms. In nuclei there are two groups of like particles, protons and neutrons. Each group is separately distributed over certain energy states subject also to the Pauli exclusion principle. Nuclei have excited states, and nucleons can be added to or removed from a nucleus. Electrons and nucleons have intrinsic angular momenta called intrinsic spins. The total angular momentum of a system of interacting particles reflects the details of the forces between particles. For example, from the coupling of electron angular momentum in atoms we infer an interaction between the spin and the orbital motion of an electron in the field of the nucleus (the spin-orbit coupling). In nuclei there is also a coupling between the orbital motion of a nucleon and its intrinsic spin (but of different origin). In

unknown authors

14

Primer on nuclear exchange models  

SciTech Connect (OSTI)

Basic physics is applied to nuclear force exchange models between two nations. Ultimately, this scenario approach can be used to try and answer the age old question of 'how much is enough?' This work is based on Chapter 2 of Physics of Societal Issues: Calculations on National Security, Environment and Energy (Springer, 2007 and 2014)

Hafemeister, David [Physics Department, Cal Poly University, San Luis Obispo, California (United States)

2014-05-09T23:59:59.000Z

15

Evaluation of thermodynamic properties of fluid mixtures by PC-SAFT model  

Science Journals Connector (OSTI)

Abstract Densities and viscosities of binary mixtures of methyl isobutyl ketone (MIK) with polar solvents namely, 2-propanol, 2-butanol and 2-pentanol, were measured at 7 temperatures (293.15–323.15 K) over the entire range of composition. Using the experimental data, excess molar volumes V m E , isobaric thermal expansivity ? p , partial molar volumes V ¯ m , i and viscosity deviations ? ? , have been calculated due to their importance in the study of specific molecular interactions. The observed negative and positive values of deviation/excess parameters were explained on the basis of the intermolecular interactions occur in these mixtures. The Perturbed Chain Statistical Association Fluid Theory (PC-SAFT) has been used to correlate the volumetric behavior of the mixtures.

Mohammad Almasi

2014-01-01T23:59:59.000Z

16

Spent nuclear fuel reprocessing modeling  

SciTech Connect (OSTI)

The long-term wide development of nuclear power requires new approaches towards the realization of nuclear fuel cycle, namely, closed nuclear fuel cycle (CNFC) with respect to fission materials. Plant nuclear fuel cycle (PNFC), which is in fact the reprocessing of spent nuclear fuel unloaded from the reactor and the production of new nuclear fuel (NF) at the same place together with reactor plant, can be one variant of CNFC. Developing and projecting of PNFC is a complicated high-technology innovative process that requires modern information support. One of the components of this information support is developed by the authors. This component is the programme conducting calculations for various variants of process flow sheets for reprocessing SNF and production of NF. Central in this programme is the blocks library, where the blocks contain mathematical description of separate processes and operations. The calculating programme itself has such a structure that one can configure the complex of blocks and correlations between blocks, appropriate for any given flow sheet. For the ready sequence of operations balance calculations are made of all flows, i.e. expenses, element and substance makeup, heat emission and radiation rate are determined. The programme is open and the block library can be updated. This means that more complicated and detailed models of technological processes will be added to the library basing on the results of testing processes using real equipment, in test operating mode. The development of the model for the realization of technical-economic analysis of various variants of technologic PNFC schemes and the organization of 'operator's advisor' is expected. (authors)

Tretyakova, S.; Shmidt, O.; Podymova, T.; Shadrin, A.; Tkachenko, V. [Bochvar Institute, 5 Rogova str., Moscow 123098 (Russian Federation); Makeyeva, I.; Tkachenko, V.; Verbitskaya, O.; Schultz, O.; Peshkichev, I. [Russian Federal Nuclear Center - VNIITF E.I. Zababakhin, p.o.box 245, Snezhinsk, 456770 (Russian Federation)

2013-07-01T23:59:59.000Z

17

Note PC catalogue (Machine body)  

E-Print Network [OSTI]

Specifications Image Brand Model 009 lenovo X61s Core2Duo L7500 1.60GHz 4GB 160GB 12.1inch 1.42Kg Windows Remarks Specifications Image Brand Model 018 Panasonic CF-F8EWMCAC Core2Duo P9300 2.26GHz 2GB 250GB 14 (Machine body) Accessory LAN Wireless LAN PC PC Code Remarks Specifications Image Brand Model 027

Katsumoto, Shingo

18

Nuclear Systems Modeling and Design Analysis - Nuclear Engineering Division  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Systems Nuclear Systems Modeling and Design Analysis CAPABILITIES Overview Nuclear Systems Modeling and Design Analysis Nuclear Systems Technologies Risk and Safety Assessments Nonproliferation and National Security Materials Testing Engineering Computation & Design Engineering Experimentation Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Capabilities Nuclear Systems Modeling and Design Analysis Bookmark and Share Reactor Physics and Fuel Cycle Analysis Reactor Physics and Fuel Cycle Analysis We have played a major role in the design and analysis of most existing and past reactor types and of many

19

Evaluation of Cubic, SAFT, and PC-SAFT Equations of State for the Vapor–Liquid Equilibrium Modeling of CO2 Mixtures with Other Gases  

Science Journals Connector (OSTI)

Evaluation of Cubic, SAFT, and PC-SAFT Equations of State for the Vapor–Liquid Equilibrium Modeling of CO2 Mixtures with Other Gases ... In this work, we assess the capability of Redlich–Kwong (RK), Soave–Redlich–Kwong (SRK), Peng–Robinson (PR) cubic equations of state (EoS), as well as Statistical Associating Fluid Theory (SAFT) and Perturbed-Chain SAFT (PC-SAFT) in modeling vapor–liquid equilibria for binary mixtures of CO2 with CH4, N2, O2, SO2, Ar, and H2S, and for the ternary mixture CO2–N2–O2. ... PC-SAFT is, on average, more accurate than cubic EoS and SAFT when no binary interaction parameter is used. ...

Nikolaos I. Diamantonis; Georgios C. Boulougouris; Erum Mansoor; Dimitrios M. Tsangaris; Ioannis G. Economou

2013-02-07T23:59:59.000Z

20

"EMM Region","PC","IGCC","PC","Conv. CT","Adv. CT","Conv. CC","Adv. CC","Adv. CC w/CCS","Fuel Cell","Nuclear","Biomass","MSW","On-shore Wind","Off-shore Wind","Solar Thermal","Solar PV"  

U.S. Energy Information Administration (EIA) Indexed Site

Regional cost adjustments for technologies modeled by NEMS by Electric Market Modul (EMM) region 10,11" Regional cost adjustments for technologies modeled by NEMS by Electric Market Modul (EMM) region 10,11" "EMM Region","PC","IGCC","PC","Conv. CT","Adv. CT","Conv. CC","Adv. CC","Adv. CC w/CCS","Fuel Cell","Nuclear","Biomass","MSW","On-shore Wind","Off-shore Wind","Solar Thermal","Solar PV" ,,,"w/CCS" "1 (ERCT)",0.91,0.92,0.92,0.93,0.95,0.91,0.92,0.9,0.96,0.96,0.93,0.93,0.95,0.92,0.86,0.87 "2 (FRCC)",0.92,0.93,0.94,0.93,0.93,0.91,0.92,0.92,0.97,0.97,0.94,0.94,"N/A","N/A",0.89,0.9 "3 (MROE)",1.01,1.01,0.99,0.99,1.01,0.99,0.99,0.97,0.99,1.01,0.99,0.98,0.99,0.97,"N/A",0.96

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Modeling Nuclear Properties with Support Vector Machines  

E-Print Network [OSTI]

We have made initial studies of the potential of support vector machines (SVM) for providing statistical models of nuclear systematics with demonstrable predictive power. Using SVM regression and classification procedures, we have created global models of atomic masses, beta-decay halflives, and ground-state spins and parities. These models exhibit performance in both data-fitting and prediction that is comparable to that of the best global models from nuclear phenomenology and microscopic theory, as well as the best statistical models based on multilayer feedforward neural networks.

Haochen Li; J. W. Clark; E. Mavrommatis; S. Athanassopoulos; K. A. Gernoth

2006-03-21T23:59:59.000Z

22

NUCLEAR ENERGY SYSTEM COST MODELING  

SciTech Connect (OSTI)

The U.S. Department of Energy’s Fuel Cycle Technologies (FCT) Program is preparing to perform an evaluation of the full range of possible Nuclear Energy Systems (NES) in 2013. These include all practical combinations of fuels and transmuters (reactors and sub-critical systems) in single and multi-tier combinations of burners and breeders with no, partial, and full recycle. As part of this evaluation, Levelized Cost of Electricity at Equilibrium (LCAE) ranges for each representative system will be calculated. To facilitate the cost analyses, the 2009 Advanced Fuel Cycle Cost Basis Report is being amended to provide up-to-date cost data for each step in the fuel cycle, and a new analysis tool, NE-COST, has been developed. This paper explains the innovative “Island” approach used by NE-COST to streamline and simplify the economic analysis effort and provides examples of LCAE costs generated. The Island approach treats each transmuter (or target burner) and the associated fuel cycle facilities as a separate analysis module, allowing reuse of modules that appear frequently in the NES options list. For example, a number of options to be screened will include a once-through uranium oxide (UOX) fueled light water reactor (LWR). The UOX LWR may be standalone, or may be the first stage in a multi-stage system. Using the Island approach, the UOX LWR only needs to be modeled once and the module can then be reused on subsequent fuel cycles. NE-COST models the unit operations and life cycle costs associated with each step of the fuel cycle on each island. This includes three front-end options for supplying feedstock to fuel fabrication (mining/enrichment, reprocessing of used fuel from another island, and/or reprocessing of this island’s used fuel), along with the transmuter and back-end storage/disposal. Results of each island are combined based on the fractional energy generated by each islands in an equilibrium system. The cost analyses use the probability distributions of key parameters and employs Monte Carlo sampling to arrive at an island’s cost probability density function (PDF). When comparing two NES to determine delta cost, strongly correlated parameters can be cancelled out so that only the differences in the systems contribute to the relative cost PDFs. For example, one comparative analysis presented in the paper is a single stage LWR-UOX system versus a two-stage LWR-UOX to LWR-MOX system. In this case, the first stage of both systems is the same (but with different fractional energy generation), while the second stage of the UOX to MOX system uses the same type transmuter but the fuel type and feedstock sources are different. In this case, the cost difference between systems is driven by only the fuel cycle differences of the MOX stage.

Francesco Ganda; Brent Dixon

2012-09-01T23:59:59.000Z

23

Global nuclear material flow/control model  

SciTech Connect (OSTI)

This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The nuclear danger can be reduced by a system for global management, protection, control, and accounting as part of an international regime for nuclear materials. The development of an international fissile material management and control regime requires conceptual research supported by an analytical and modeling tool which treats the nuclear fuel cycle as a complete system. The prototype model developed visually represents the fundamental data, information, and capabilities related to the nuclear fuel cycle in a framework supportive of national or an international perspective. This includes an assessment of the global distribution of military and civilian fissile material inventories, a representation of the proliferation pertinent physical processes, facility specific geographic identification, and the capability to estimate resource requirements for the management and control of nuclear material. The model establishes the foundation for evaluating the global production, disposition, and safeguards and security requirements for fissile nuclear material and supports the development of other pertinent algorithmic capabilities necessary to undertake further global nuclear material related studies.

Dreicer, J.S.; Rutherford, D.S.; Fasel, P.K.; Riese, J.M.

1997-10-01T23:59:59.000Z

24

Modeling of asphaltene precipitation from n-alkane diluted heavy oils and bitumens using the PC-SAFT equation of state  

Science Journals Connector (OSTI)

Abstract In this work, the PC-SAFT equation of state was applied to the modeling of asphaltene precipitation from n-alkane diluted heavy oils and bitumens. Liquid–liquid equilibrium was assumed between a dense liquid phase (asphaltene-rich phase) and a light liquid phase. The liquid–liquid equilibrium calculation, in which only asphaltenes were allowed to partition to the dense phase, was performed using an efficient method with Michelsen's stability test. The bisection or Newton–Raphson method was used to improve convergence. Experimental information of the heavy oils and bitumens, characterized in terms of solubility fractions (saturates, aromatics, resins, and asphaltenes), was taken from the literature. Asphaltenes were divided into fractions of different molar masses using a gamma distribution function. Predictions of the PC-SAFT equation of state using linear correlations of the binary interaction parameters between asphaltene subfractions and the n-alkane were compared with the measured onset of precipitation and the amount of precipitated asphaltene (fractional yield) of the heavy oils and bitumens diluted with n-alkanes. Results of the comparison showed a satisfactory agreement between the experimental data and the calculated values with the PC-SAFT equation.

María A. Zúñiga-Hinojosa; Daimler N. Justo-García; Marco A. Aquino-Olivos; Luis A. Román-Ramírez; Fernando García-Sánchez

2014-01-01T23:59:59.000Z

25

Nuclear Fallout Models – An Overview  

SciTech Connect (OSTI)

This presentation is an introduction to a full report, which is a tutorial for individuals using the products of the models reviewed.

Hodges, Matthew [UNLV

2014-10-21T23:59:59.000Z

26

The Nuclear Thomas-Fermi Model  

DOE R&D Accomplishments [OSTI]

The statistical Thomas-Fermi model is applied to a comprehensive survey of macroscopic nuclear properties. The model uses a Seyler-Blanchard effective nucleon-nucleon interaction, generalized by the addition of one momentum-dependent and one density-dependent term. The adjustable parameters of the interaction were fitted to shell-corrected masses of 1654 nuclei, to the diffuseness of the nuclear surface and to the measured depths of the optical model potential. With these parameters nuclear sizes are well reproduced, and only relatively minor deviations between measured and calculated fission barriers of 36 nuclei are found. The model determines the principal bulk and surface properties of nuclear matter and provides estimates for the more subtle, Droplet Model, properties. The predicted energy vs density relation for neutron matter is in striking correspondence with the 1981 theoretical estimate of Friedman and Pandharipande. Other extreme situations to which the model is applied are a study of Sn isotopes from {sup 82}Sn to {sup 170}Sn, and the rupture into a bubble configuration of a nucleus (constrained to spherical symmetry) which takes place when Z{sup 2}/A exceeds about 100.

Myers, W. D.; Swiatecki, W. J.

1994-08-01T23:59:59.000Z

27

ePC-SAFT revised  

Science Journals Connector (OSTI)

Abstract So far, the electrolyte PC-SAFT equation of state developed in Cameretti et al. (2005) has been applied to model solution densities, vapor–liquid equilibria (VLE), liquid–liquid equilibria (LLE), and solid–liquid equilibria (SLE) of solutions containing electrolytes. For that purpose, two ion-specific parameters were used to characterize any ion: the diameter of the solvated ion and the dispersion-energy parameter between ion and solvent. Dispersion was only considered between ions and solvents. Considering the small number of adjustable parameters, this approach yielded acceptable results especially for low and moderate electrolyte concentrations. However, for high salt concentrations, a distinct deviation between modeled and experimental data was observed. In this work a new modeling approach is suggested that accounts explicitly also for dispersion interactions between anions and cations. This yields a much more precise description of electrolyte solutions at higher concentrations compared to original ePC-SAFT. With this new approach it is also possible to directly model weak electrolyte solutions without using an additional approach that accounts for ion-pair formation. The new approach for applying ePC-SAFT is now able to model phase equilibria (VLE, LLE, SLE) of ternary electrolyte solutions containing water, organic solvents, salts, and amino acids even at high salt concentrations in good agreement with experimental data.

Christoph Held; Thomas Reschke; Sultan Mohammad; Armando Luza; Gabriele Sadowski

2014-01-01T23:59:59.000Z

28

A probabilistic model of nuclear import of proteins  

Science Journals Connector (OSTI)

......Accuracy of predicting nuclear import for independent datasets (Hawkins et al...import. We use a nuclear localization signal dataset extracted from...mouse and yeast nuclear proteomes. We establish on a smaller dataset that the model......

Ahmed M. Mehdi; Muhammad Shoaib B. Sehgal; Bostjan Kobe; Timothy L. Bailey; Mikael Bodén

2011-05-01T23:59:59.000Z

29

Large scale kinematics and dynamical modelling of the Milky Way nuclear star cluster  

E-Print Network [OSTI]

Within the central 10pc of our Galaxy lies a dense nuclear star cluster (NSC), and similar NSCs are found in most nearby galaxies. Studying the structure and kinematics of NSCs reveals the history of mass accretion of galaxy nuclei. Because the Milky Way (MW) NSC is at a distance of only 8kpc, we can spatially resolve the MWNSC on sub-pc scales. This makes the MWNSC a reference object for understanding the formation of all NSCs. We have used the NIR long-slit spectrograph ISAAC (VLT) in a drift-scan to construct an integral-field spectroscopic map of the central 9.5 x 8pc of our Galaxy. We use this data set to extract stellar kinematics both of individual stars and from the unresolved integrated light spectrum. We present a velocity and dispersion map from the integrated light and model these kinematics using kinemetry and axisymmetric Jeans models. We also measure CO bandhead strengths of 1,381 spectra from individual stars. We find kinematic complexity in the NSCs radial velocity map including a misalignmen...

Feldmeier, A; Seth, A; Schödel, R; Lützgendorf, N; de Zeeuw, P T; Kissler-Patig, M; Nishiyama, S; Walcher, C J

2014-01-01T23:59:59.000Z

30

Nuclear curvature energy in relativistic models  

Science Journals Connector (OSTI)

The difficulties arising in the calculation of the nuclear curvature energy are analyzed in detail, especially with reference to relativistic models. It is underlined that the implicit dependence on curvature of the quantal wave functions is directly accessible only in a semiclassical framework. It is shown that also in the relativistic models quantal and semiclassical calculations of the curvature energy are in good agreement. © 1996 The American Physical Society.

M. Centelles; X. Viñas; P. Schuck

1996-02-01T23:59:59.000Z

31

Nuclear Energy Level Argument for a Spheroidal Nuclear Model  

Science Journals Connector (OSTI)

Recently there has been notable success, particularly by Maria Mayer, in explaining many nuclear phenomena including spins, magnetic moments, isomeric states, etc. on the basis of a single particle model for the separate nucleons in a spherical nucleus. The spherical model, however, seems incapable of explaining the observed large quadrupole moments of nuclei. In this paper it is shown that an extension of the logic of this model leads to the prediction that greater stability is obtained for a spheroidal than for a spherical nucleus of the same volume, when reasonable assumptions are made concerning the variation of the energy terms on distortion. The predicted quadrupole moment variation with odd A is in general agreement with the experimental values as concerns variation with A, but are even larger than the experimental values. Since the true situation probably involves considerable "dilution" of the extreme single particle model, it is encouraging that the present predictions are larger rather than smaller than the experimental results. A solution is given for the energy levels of a particle in a spheroidal box.

James Rainwater

1950-08-01T23:59:59.000Z

32

Utility system integration and optimization models for nuclear power management  

E-Print Network [OSTI]

A nuclear power management model suitable for nuclear utility systems optimization has been developed for use in multi-reactor fuel management planning over periods of up to ten years. The overall utility planning model ...

Deaton, Paul Ferris

1973-01-01T23:59:59.000Z

33

Nuclear response beyond the Fermi gas model  

E-Print Network [OSTI]

The Fermi gas model, while providing a reasonable qualitative description of the continuum nuclear response, does not include the effects of dynamical nucleon-nucleon correlations in the initial and final states, that have long been recognized to play a critical role in specific kinematical regions. We review a many-body approach in which these effects are consistently taken into account and discuss the results of a calculation of the quasielastic neutrino-oxygen cross section as an illustrative example.

Omar Benhar

2003-07-14T23:59:59.000Z

34

Thermodynamic model for predicting equilibrium conditions of clathrate hydrates of noble gases + light hydrocarbons: Combination of Van der Waals–Platteeuw model and sPC-SAFT EoS  

Science Journals Connector (OSTI)

Abstract In this communication, equilibrium conditions of clathrate hydrates containing mixtures of noble gases (Argon, Krypton and Xenon) and light hydrocarbons (C1–C3), which form structure I and II, are modeled. The thermodynamic model is based on the solid solution theory of Van der Waals–Platteeuw combined with the simplified Perturbed-Chain Statistical Association Fluid Theory equation of state (sPC-SAFT EoS). In dispersion term of sPC-SAFT EoS, the temperature dependent binary interaction parameters ( k ij ) are adjusted; taking advantage of the well described (vapor + liquid) phase equilibria. Furthermore, the Kihara potential parameters are optimized based on the P–T data of pure hydrate former. Subsequently, these obtained parameters are used to predict the binary gas hydrate dissociation conditions. The equilibrium conditions of the binary gas hydrates predicted by this model agree well with experimental data (overall AAD P  ?  2.17).

Mostafa Abolala; Farshad Varaminian

2015-01-01T23:59:59.000Z

35

Accurate viscosity modeling of liquid metals based on friction theory and PC-SAFT equation of state  

Science Journals Connector (OSTI)

Values of the viscosities of liquid metals are important in the prediction of fluid flow in many metallurgical manufacturing processes. In this work the friction theory (f-theory...) for viscosity modeling is use...

M. H. Mousazadeh

2012-06-01T23:59:59.000Z

36

NEAMS: The Nuclear Energy Advanced Modeling and Simulation Program  

Broader source: Energy.gov (indexed) [DOE]

NEAMS: The Nuclear Energy Advanced NEAMS: The Nuclear Energy Advanced Modeling and Simulation Program The Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program is developing a simulation tool kit using leading-edge computational methods that will accelerate the development and deployment of nuclear power technologies that employ enhanced safety and security features, produce power more cost-effectively, and utilize natural resources more efficiently. The NEAMS ToolKit

37

The PNL single-tower measurement model of rotationally sampled turbulent wind, with user's guide for STRS2PC  

SciTech Connect (OSTI)

This report describes a single-tower rotationally sampled wind model, STRS-2, that approximates a set of time series of turbulent wind experienced by individual points rotating in circles in a crosswind plane using measurements from anemometers arrayed vertically along a single line. The purposes of the model are (1) to use turbulence measurements made economically from conventional single-tower arrays of anemometers, (2) to incorporate measures characteristics of the wind at specific sites under consideration for operation of wind turbines, spanning the height range if interest, and (3) to estimate the unmeasured turbulence characteristics in the crosswind plane that spans the disk of the rotor blades. 17 refs., 15 figs., 5 tabs.

Connell, J.R.; Morris, V.R.; Powell, D.C.; Gower, G.L.

1988-06-01T23:59:59.000Z

38

Volume-translated cubic EoS and PC-SAFT density models and a free volume-based viscosity model for hydrocarbons at extreme temperature and pressure conditions  

SciTech Connect (OSTI)

This research focuses on providing the petroleum reservoir engineering community with robust models of hydrocarbon density and viscosity at the extreme temperature and pressure conditions (up to 533 K and 276 MPa, respectively) characteristic of ultra-deep reservoirs, such as those associated with the deepwater wells in the Gulf of Mexico. Our strategy is to base the volume-translated (VT) Peng–Robinson (PR) and Soave–Redlich–Kwong (SRK) cubic equations of state (EoSs) and perturbed-chain, statistical associating fluid theory (PC-SAFT) on an extensive data base of high temperature (278–533 K), high pressure (6.9–276 MPa) density rather than fitting the models to low pressure saturated liquid density data. This high-temperature, high-pressure (HTHP) data base consists of literature data for hydrocarbons ranging from methane to C{sub 40}. The three new models developed in this work, HTHP VT-PR EoS, HTHP VT-SRK EoS, and hybrid PC-SAFT, yield mean absolute percent deviation values (MAPD) for HTHP hydrocarbon density of ?2.0%, ?1.5%, and <1.0%, respectively. An effort was also made to provide accurate hydrocarbon viscosity models based on literature data. Viscosity values are estimated with the frictional theory (f-theory) and free volume (FV) theory of viscosity. The best results were obtained when the PC-SAFT equation was used to obtain both the attractive and repulsive pressure inputs to f-theory, and the density input to FV theory. Both viscosity models provide accurate results at pressures to 100 MPa but experimental and model results can deviate by more than 25% at pressures above 200 MPa.

Burgess, Ward A.; Tapriyal, Deepak; Morreale, Bryan D.; Soong, Yee; Baled, Hseen; O Enick, Robert M; Wu, Yue; Bamgbade, Babatunde A.; McHugh,Mark A.

2013-12-15T23:59:59.000Z

39

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software...  

Broader source: Energy.gov (indexed) [DOE]

Software Verification and Validation (V&V) Plan Requirements Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan Requirements...

40

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program...  

Broader source: Energy.gov (indexed) [DOE]

Program Plan Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program Plan The NEAMS program plan includes information on the program vision, objective, scope, schedule and...

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Application of the PC-SAFT equation of state to modeling of solid-liquid equilibria in systems with organic components forming chemical compounds  

Science Journals Connector (OSTI)

Equilibrium diagrams of liquid and solid phases were calculated by the equation of state, based on the perturbed-chain statistical associating fluid theory (PC-SAFT) for binary and ternary systems constituted by....

I. V. Prikhod’ko; F. Tumakaka; G. Sadowski

2007-04-01T23:59:59.000Z

42

Modeling and Simulation for Nuclear Reactors Hub | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Modeling and Simulation for Nuclear Reactors Hub Modeling and Simulation for Nuclear Reactors Hub Modeling and Simulation for Nuclear Reactors Hub August 1, 2010 - 4:20pm Addthis Scientists and engineers are working to help the nuclear industry make reactors more efficient through computer modeling and simulation. Scientists and engineers are working to help the nuclear industry make reactors more efficient through computer modeling and simulation. The Department's Energy Innovation Hubs are helping to advance promising areas of energy science and engineering from the earliest stages of research to the point of commercialization where technologies can move to the private sector by bringing together leadings scientists to collaborate on critical energy challenges. The Energy Innovation Hubs aim to develop innovation through a unique

43

Propagation of uncertainties in the nuclear DFT models  

E-Print Network [OSTI]

Parameters of the nuclear density functional theory (DFT) models are usually adjusted to experimental data. As a result they carry certain theoretical error, which, as a consequence, carries out to the predicted quantities. In this work we address the propagation of theoretical error, within the nuclear DFT models, from the model parameters to the predicted observables. In particularly, the focus is set on the Skyrme energy density functional models.

Markus Kortelainen

2014-09-04T23:59:59.000Z

44

Processing and intracellular localization of rice stripe virus Pc2 protein in insect cells  

SciTech Connect (OSTI)

Rice stripe virus (RSV) belongs to the genus Tenuivirus and its genome consists of four single-stranded RNAs encoding seven proteins. Here, we have analyzed the processing and membrane association of Pc2 encoded by vcRNA2 in insect cells. The enhanced green fluorescent protein (eGFP) was fused to the Pc2 and used for the detection of Pc2 fusion proteins. The results showed that Pc2 was cleaved to produce two proteins named Pc2-N and Pc2-C. When expressed alone, either Pc2-N or Pc2-C could transport to the Endoplasmic reticulum (ER) membranes independently. Further mutagenesis studies revealed that Pc2 contained three ER-targeting domains. The results led us to propose a model for the topology of the Pc2 in which an internal signal peptide immediately followed a cleavage site, and two transmembrane regions are contained.

Zhao, Shuling; Zhang, Gaozhan; Dai, Xuejuan; Hou, Yanling; Li, Min [College of Bioscience and Biotechnology, Yangzhou University, Yangzhou 225009 (China)] [College of Bioscience and Biotechnology, Yangzhou University, Yangzhou 225009 (China); Liang, Jiansheng, E-mail: jsliang@yzu.edu.cn [College of Bioscience and Biotechnology, Yangzhou University, Yangzhou 225009 (China)] [College of Bioscience and Biotechnology, Yangzhou University, Yangzhou 225009 (China); Liang, Changyong, E-mail: cyliang@yzu.edu.cn [College of Bioscience and Biotechnology, Yangzhou University, Yangzhou 225009 (China)] [College of Bioscience and Biotechnology, Yangzhou University, Yangzhou 225009 (China)

2012-08-01T23:59:59.000Z

45

Magnetic fields at resonant conditions for the hydrogen ion affect neurite outgrowth in PC-12 cells: A test of the ion parametric resonance model  

SciTech Connect (OSTI)

PC-12 cells primed with nerve growth factor (NGF) were exposed to sinusoidal extremely-low-frequency (ELF) magnetic fields (MFs) selected to test the predictions of the ion parametric resonance (IPR) model under resonance conditions for a single ion (hydrogen). The authors examined the field effects on the neurite outgrowth (NO) induced by NGF using three different combinations of flux densities of the parallel components of the AC MF (B{sub ac}) and the static MF (B{sub dc}). The first test examined the NO response in cells exposed to 45 Hz at a B{sub dc} of 2.96 {micro}T with resonant conditions for H{sup +} according to the model. The B{sub ac} values ranged from 0.29 to 4.11 {micro}T root-mean-square (rms). In the second test, the MF effects at off-resonance conditions (i.e., no biologically significant ion at resonance) were examined using the frequency of 45 Hz with a B{sub dc} of 1.97 {micro}T and covering a B{sub ac} range between 0.79 and 2.05 {micro}T rms. In the third test, the Ac frequency was changed to 30 Hz with the subsequent change in B{sub dc} to 1.97 {micro}T to tune for H{sup +} as in the first test. The B{sub ac} values ranged from 0.79 to 2.05 {micro}T rms. After a 23 h incubation and exposure to the MF in the presence of NGF (5 ng/ml), the NO was analyzed using a stereoscopic microscope. The results showed that the NGF stimulation of neurite outgrowth (NSNO) was affected by MF combinations over most of the B{sub ac} exposure range generally consistent with the predictions of the IPR model. However, for a distinct range of B{sub ac} where the IPR model predicted maximal ionic influence, the observed pattern of NSNO contrasted sharply with those predictions. The symmetry of this response suggests that values of B{sub ac} within this distinct range may trigger alternate or additional cellular mechanisms that lead to an apparent lack of response to the MF stimulus.

Trillo, M.A.; Ubeda, A. [Hospital Ramon y Cajal, Madrid (Spain). Dept. Investigacion] [Hospital Ramon y Cajal, Madrid (Spain). Dept. Investigacion; Blanchard, J.P. [Bechtel Corp., San Francisco, CA (United States). Research and Development Dept.] [Bechtel Corp., San Francisco, CA (United States). Research and Development Dept.; House, D.E.; Blackman, C.F. [Environmental Protection Agency, Research Triangle Park, NC (United States)] [Environmental Protection Agency, Research Triangle Park, NC (United States)

1996-04-01T23:59:59.000Z

46

HOTSPOT Health Physics codes for the PC  

SciTech Connect (OSTI)

The HOTSPOT Health Physics codes were created to provide Health Physics personnel with a fast, field-portable calculation tool for evaluating accidents involving radioactive materials. HOTSPOT codes are a first-order approximation of the radiation effects associated with the atmospheric release of radioactive materials. HOTSPOT programs are reasonably accurate for a timely initial assessment. More importantly, HOTSPOT codes produce a consistent output for the same input assumptions and minimize the probability of errors associated with reading a graph incorrectly or scaling a universal nomogram during an emergency. The HOTSPOT codes are designed for short-term (less than 24 hours) release durations. Users requiring radiological release consequences for release scenarios over a longer time period, e.g., annual windrose data, are directed to such long-term models as CAPP88-PC (Parks, 1992). Users requiring more sophisticated modeling capabilities, e.g., complex terrain; multi-location real-time wind field data; etc., are directed to such capabilities as the Department of Energy`s ARAC computer codes (Sullivan, 1993). Four general programs -- Plume, Explosion, Fire, and Resuspension -- calculate a downwind assessment following the release of radioactive material resulting from a continuous or puff release, explosive release, fuel fire, or an area contamination event. Other programs deal with the release of plutonium, uranium, and tritium to expedite an initial assessment of accidents involving nuclear weapons. Additional programs estimate the dose commitment from the inhalation of any one of the radionuclides listed in the database of radionuclides; calibrate a radiation survey instrument for ground-survey measurements; and screen plutonium uptake in the lung (see FIDLER Calibration and LUNG Screening sections).

Homann, S.G.

1994-03-01T23:59:59.000Z

47

Modeling fabrication of nuclear components: An integrative approach  

SciTech Connect (OSTI)

Reduction of the nuclear weapons stockpile and the general downsizing of the nuclear weapons complex has presented challenges for Los Alamos. One is to design an optimized fabrication facility to manufacture nuclear weapon primary components in an environment of intense regulation and shrinking budgets. This dissertation presents an integrative two-stage approach to modeling the casting operation for fabrication of nuclear weapon primary components. The first stage optimizes personnel radiation exposure for the casting operation layout by modeling the operation as a facility layout problem formulated as a quadratic assignment problem. The solution procedure uses an evolutionary heuristic technique. The best solutions to the layout problem are used as input to the second stage - a simulation model that assesses the impact of competing layouts on operational performance. The focus of the simulation model is to determine the layout that minimizes personnel radiation exposures and nuclear material movement, and maximizes the utilization of capacity for finished units.

Hench, K.W.

1996-08-01T23:59:59.000Z

48

Verifiable Fuel Cycle Simulation Model (VISION): A Tool for Analyzing Nuclear Fuel Cycle Futures  

SciTech Connect (OSTI)

The nuclear fuel cycle consists of a set of complex components that are intended to work together. To support the nuclear renaissance, it is necessary to understand the impacts of changes and timing of events in any part of the fuel cycle system such as how the system would respond to each technological change, a series of which moves the fuel cycle from where it is to a postulated future state. The system analysis working group of the United States research program on advanced fuel cycles (formerly called the Advanced Fuel Cycle Initiative) is developing a dynamic simulation model, VISION, to capture the relationships, timing, and changes in and among the fuel cycle components to help develop an understanding of how the overall fuel cycle works. This paper is an overview of the philosophy and development strategy behind VISION. The paper includes some descriptions of the model components and some examples of how to use VISION. For example, VISION users can now change yearly the selection of separation or reactor technologies, the performance characteristics of those technologies, and/or the routing of material among separation and reactor types - with the model still operating on a PC in <5 min.

Jacob J. Jacobson; Steven J. Piet; Gretchen E. Matthern; David E. Shropshire; Robert F. Jeffers; A. M. Yacout; Tyler Schweitzer

2010-11-01T23:59:59.000Z

49

Modelling power output at nuclear power plant by neural networks  

Science Journals Connector (OSTI)

In this paper, we propose two different neural network (NN) approaches for industrial process signal forecasting. Real data is available for this research from boiling water reactor type nuclear power reactors. NNs are widely used for time series prediction, ... Keywords: evaluation methods, model input selection, neural networks, nuclear power plant, one-step ahead prediction

Jaakko Talonen; Miki Sirola; Eimontas Augilius

2010-09-01T23:59:59.000Z

50

Liquid?Liquid Equilibria for Binary and Ternary Polymer Solutions with PC-SAFT  

Science Journals Connector (OSTI)

Liquid?Liquid Equilibria for Binary and Ternary Polymer Solutions with PC-SAFT ... The algorithms are used for investigating the correlative and predictive capabilities of the thermodynamic model PC-SAFT. ... The algorithms are used for testing of a state-of-the-art model in polymer thermodynamics, PC-SAFT, by Gross and Sadowski. ...

Thomas Lindvig; Michael L. Michelsen; Georgios M. Kontogeorgis

2004-01-21T23:59:59.000Z

51

LANL researchers use computer modeling to study HIV | National Nuclear  

National Nuclear Security Administration (NNSA)

researchers use computer modeling to study HIV | National Nuclear researchers use computer modeling to study HIV | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > LANL researchers use computer modeling to study HIV LANL researchers use computer modeling to study HIV Posted By Office of Public Affairs Los Alamos National Laboratory researchers are investigating the complex

52

The optical model potential of the $?$ hyperon in nuclear matter  

E-Print Network [OSTI]

We present our attempts to determine the optical model potential $U_\\Sigma = V_\\Sigma -iW_\\Sigma$ of the $\\Sigma$ hyperon in nuclear matter. We analyze the following sources of information on $U_\\Sigma$: $\\Sigma N$ scattering, $\\Sigma^-$ atoms, and final state interaction of $\\Sigma$ hyperons in the $(\\pi,K^+)$ and $(K^-.\\pi)$ reactions on nuclear targets. We conclude that $V_\\Sigma$ is repulsive inside the nucleus and has a shallow a tractive pocket at the nuclear surface. These features of $V_\\Sigma$ are consistent with the Nijmegen model F of the hyperon-nucleon interaction.

J. Dabrowski; J. Rozynek

2009-11-17T23:59:59.000Z

53

Experimental density and PC-SAFT modeling of Krytox (R) (perfluoropolyether) at pressures to 275 MPa and temperatures to 533 K  

SciTech Connect (OSTI)

Density data from 298 to 533 K and to 275 MPa are reported for Krytox® GPL 102, a poly(perfluoropropyl ether) (PFPE) with a CF3-branched fluoropropylether repeat group. The Tait equation fit to each density isotherm have mean absolute percent deviations (MAPD) between 0.11 and 0.30% with standard deviations (SD) not exceeding 0.20%. The perturbed-chain statistical associating fluid theory (PC-SAFT) fit to the density data has an MAPD of 0.67% and an SD of 0.67%. Likewise the PC-SAFT fit to previously reported density data of Demnum®, a PFPE with an n-fluoropropylether repeat group, has an MAPD of 0.22% and a SD of 0.21% for Demnum® S-20 and an MAPD of 0.27% with a SD of 0.14% for Demnum® S-65. The trends exhibited by the PC-SAFT pure component parameters obtained from the fits of these three PFPEs are similar to those reported for linear and branched hydrocarbons with the same number of carbons.

Bamgbade, B. A.; Wu, Y.; Burgess, W. A.

2012-10-25T23:59:59.000Z

54

Materials Modeling and Simulation for Nuclear Fuels (MMSNF) Workshops  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Aerial photo of Argonne National Laboratory Argonne National Laboratory University of Chicago Chicago Photography courtesy Thomas F Ewing Privacy and Security Notice The MMSNF Workshops The goal of the Materials Modeling and Simulation for Nuclear Fuels (MMSNF) workshops is to stimulate research and discussions on modeling and simulations of nuclear fuels, to assist the design of improved fuels and the evaluation of fuel performance. In addition to research focused on existing or improved types of LWR reactors, recent modeling programs, networks, and links have been created to develop innovative nuclear fuels and materials for future generations of nuclear reactors. Examples can be found in Europe (e.g. F-BRIDGE project and ACTINET network and SAMANTHA cooperative network), in the USA (e.g. CASL, NEAMS, CESAR and CMSN network

55

Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational  

E-Print Network [OSTI]

Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna Medical Nuclear Supply Chain Design #12;Outline Background and Motivation Supply Chain Challenges The Medical Nuclear Supply Chain Network Design Model The Computational Approach Summary and Suggestions

Nagurney, Anna

56

Infrastructure development assistance modeling for nuclear power plant  

SciTech Connect (OSTI)

The purpose of this paper is to develop a model, a general frame to be utilized in assisting newcomer countries to start a nuclear power program. A nuclear power plant project involves technical complexity and high level of investment with long duration. Considering newcomers are mostly developing countries that lack the national infrastructure, key infrastructure issues may constitute the principal constraints to the development of a nuclear power program. In this regard, it is important to provide guidance and support to set up an appropriate infrastructure when we help them with the first launch of nuclear power plant project. To date, as a sole nuclear power generation company, KHNP has been invited many times to mentor or assist newcomer countries for their successful start of a nuclear power program since Republic of Korea is an exemplary case of a developing country which began nuclear power program from scratch and became a major world nuclear energy country in a short period of time. Through hosting events organized to aid newcomer countries' initiation of nuclear power projects, difficulties have been recognized. Each event had different contents according to circumstances because they were held as an unstructured and one-off thing. By developing a general model, we can give more adequate and effective aid in an efficient way. In this paper, we created a model to identify necessary infrastructures at the right stage, which was mainly based on a case of Korea. Taking into account the assistance we received from foreign companies and our own efforts for technological self-reliance, we have developed a general time table and specified activities required to do at each stage. From a donor's perspective, we explored various ways to help nuclear infrastructure development including technical support programs, training courses, and participating in IAEA technical cooperation programs on a regular basis. If we further develop the model, the next task would be to make the model more sophisticated as a 'semi-tailored model' so that it can be applied to a certain country reflecting its unique conditions. In accordance with its degree of established infrastructure, we can adjust or modify the model. Despite lots of benefits of using this model, there remain limitations such as time and budget constraints. These problems, however, can be addressed by cooperating with international organization such as the IAEA and other companies that share the same goal of helping newcomer countries introduce nuclear power. (authors)

Park, J. H.; Hwang, K.; Park, K. M.; Kim, S. W.; Lee, S. M. [Korea Hydro and Nuclear Power Co., LTD, 23, 106 gil, Yeongdong-daero, Gangnam-gu, 153-791 (Korea, Republic of)

2012-07-01T23:59:59.000Z

57

Nuclear equation of state in the MIT bag crystal model for nuclear matter  

Science Journals Connector (OSTI)

We developed the MIT bag crystal model for nuclear matter in two aspects. First, we proved a ??=4 selection rule in the harmonic expansion of quark wave function by group theory. It enables us to push the maximum Dirac quantum number ?m up from 7 to 15, therefore improving our calculation for the energy band and wave functions of quarks. Then, by a multipole expansion of the color fields we calculate the color interaction energy between quarks. These developments enable us to calculate the energy per nucleon in nuclear matter as done previously for a free nucleon. A nuclear equation of state is derived.

Qi-Ren Zhang and Huai-Min Liu

1992-12-01T23:59:59.000Z

58

Improving the flexibility of the desktop PC supply chain  

E-Print Network [OSTI]

Dell Inc. is a company headquartered in Round Rock, TX founded by entrepreneur Michael Dell in 1984. In its 20+ years of history, Dell has revolutionized the PC industry by deploying the "Dell Direct" model--eliminating ...

Wu, Johnson (Johnson Chun Hsien)

2006-01-01T23:59:59.000Z

59

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software  

Broader source: Energy.gov (indexed) [DOE]

Advanced Modeling and Simulation (NEAMS) Software Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan Requirements Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan Requirements The purpose of the NEAMS Software V&V Plan is to define what the NEAMS program expects in terms of V&V for the computational models that are developed under NEAMS. NEAMS Software Verification and Validation Plan Requirements Version 0.pdf More Documents & Publications NEAMS Quarterly Report for January-March 2013 Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program Plan CRAD, Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities

60

A nuclear data acquisition system flow control model  

SciTech Connect (OSTI)

A general Petri Net representation of a nuclear data acquisition system model is presented. This model provides for the unique requirements of a nuclear data acquisition system including the capabilities of concurrently acquiring asynchronous and synchronous data, of providing multiple priority levels of flow control arbitration, and of permitting multiple input sources to reside at the same priority without the problem of channel lockout caused by a high rate data source. Finally, a previously implemented gamma camera/physiological signal data acquisition system is described using the models presented.

Hack, S.N.

1988-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Nuclear Mass Datasets and Models at nuclearmasses.org  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

This online repository for nuclear mass information allows nuclear researchers to upload their own mass values, store then, share them with colleagues, and, in turn, visualize and analyze the work of others. The Resources link provides access to published information or tools on other websites. The Contributions page is where users will find software, documents, experimental mass data sets, and theoretical mass models that have been uploaded for sharing with the scientific community.

62

Testing nuclear models via neutrino scattering  

E-Print Network [OSTI]

Recent progresses on the relativistic modeling of neutrino-nucleus reactions are presented and the results are compared with high precision experimental data in a wide energy range.

Barbaro, M B; Amaro, J E; Antonov, A N; Caballero, J A; Donnelly, T W; Gonzalez-Jimenez, R; Ivanov, M V; de Guerra, E Moya; Megias, G D; Simo, I Ruiz; Udias, J M

2014-01-01T23:59:59.000Z

63

Testing nuclear models via neutrino scattering  

E-Print Network [OSTI]

Recent progresses on the relativistic modeling of neutrino-nucleus reactions are presented and the results are compared with high precision experimental data in a wide energy range.

M. B. Barbaro; C. Albertus; J. E. Amaro; A. N. Antonov; J. A. Caballero; T. W. Donnelly; R. Gonzalez-Jimenez; M. V. Ivanov; E. Moya de Guerra; G. D. Megias; I. Ruiz Simo; J. M. Udias

2014-11-21T23:59:59.000Z

64

A model to illustrate forces in nuclear fusion  

Science Journals Connector (OSTI)

A model consisting of magnets and iron which makes a good analogy of the behavior of the electrostatic and nuclear force involved in the fusion of two protons has been constructed and used as a lecture demonstration. Detailed calculations of the magnetic field and of the forces that explain the unusual behavior of the model are presented. The model can also be useful in electricity and magnetism where students can be challenged to explain the unusual behavior of this ‘‘science puzzle.’’ ?

E. Kashy; D. A. Johnson

1994-01-01T23:59:59.000Z

65

Nano-Continuum Modeling of a Nuclear Glass Specimen Altered for 25 Years  

E-Print Network [OSTI]

Contract No. DE-AC02-05CH11231. Nano-Continuum Modeling of aNano-Continuum Modeling of a Nuclear Glass Specimen AlteredSignature on File) iv Nano-Continuum Modeling of a Nuclear

Steefel, Carl

2014-01-01T23:59:59.000Z

66

288 Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, 2013 Multi-physics modelling of nuclear reactors  

E-Print Network [OSTI]

288 Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, 2013 Multi-physics modelling practices in a nutshell', Int. J. Nuclear Energy Science and Technology, Vol. 7, No. 4, pp.288 Energy and Nuclear Applications', Göteborg, Sweden, 13­14 October 2011 Copyright © 2013 Inderscience

Demazière, Christophe

67

The Bonn nuclear quark model revisited  

SciTech Connect (OSTI)

We present the exact solutions to the equations of the lowest energy states of the colored and color-symmetric sectors of the Bonn quark model, which is SU(3) symmetric and is defined in terms of an effective pairing force with su(4) algebraic structure. We show that the groundstate of the model is not color symmetrical except for a narrow interval in the range of possible quark numbers. We also study the performance of the Glauber coherent state, as well as of superconducting states of the BCS type, with respect to the description, not only of the absolute (colored) groundstate, but also of the minimum energy state of the color-symmetrical sector, finding that it is remarkably good. We use the model to discuss, in a schematic context, some controversial aspects of the conventional treatment of color superconductivity.

Providencia, Constanca [Departamento de Fi sica, Universidade de Coimbra, Rua Larga, P-3004-516 Coimbra (Portugal); Providencia, Joao da [Departamento de Fi sica, Universidade de Coimbra, Rua Larga, P-3004-516 Coimbra (Portugal)], E-mail: providencia@teor.fis.uc.pt; Cordeiro, Flavio [Departamento de Fi sica, Universidade de Coimbra, Rua Larga, P-3004-516 Coimbra (Portugal); Yamamura, Masatoshi [Department of Pure and Applied Physics, Faculty of Engineering Science, Kansai University, Suita 564-8680 (Japan); Tsue, Yasuhiko; Nishiyama, Seiya [Physics Division, Faculty of Science, Kochi University, Kochi 780-8520 (Japan)

2009-08-15T23:59:59.000Z

68

Nuclear fusion control-oriented plasma current linear models  

Science Journals Connector (OSTI)

The control of plasma in nuclear fusion has been revealed as a promising application of Control Engineering, with increasing interest in the control community during last years. In this paper it is developed a control-oriented linear model for the control ...

Aitor J. Garrido; Izaskun Garrido; M. Goretti Sevillano; Mikel Alberdi; Modesto Amundarain; Oscar Barambones; Manuel De La Sen

2010-07-01T23:59:59.000Z

69

LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS  

E-Print Network [OSTI]

LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS M. V. Bazhenov and E. F. Sabaev UDC employed for analyzing reactor dynamics. Equations of this type are used for analyzing the stability of the reactor power, etc. Among these problems the question of the boundedness of reactor power bursts

Bazhenov, Maxim

70

Thermohydraulic modeling of nuclear thermal rockets: The KLAXON code  

SciTech Connect (OSTI)

The hydrogen flow from the storage tanks, through the reactor core, and out the nozzle of a Nuclear Thermal Rocket is an integral design consideration. To provide an analysis and design tool for this phenomenon, the KLAXON code is being developed. A shock-capturing numerical methodology is used to model the gas flow (the Harten, Lax, and van Leer method, as implemented by Einfeldt). Preliminary results of modeling the flow through the reactor core and nozzle are given in this paper.

Hall, M.L.; Rider, W.J.; Cappiello, M.W.

1992-07-01T23:59:59.000Z

71

Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational  

E-Print Network [OSTI]

Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna Chain Challenges The Medical Nuclear Supply Chain Network Design Model The Computational Approach Medical Nuclear Supply Chain Design #12;This presentation is based on the paper, "Medical Nuclear Supply

Nagurney, Anna

72

INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS  

SciTech Connect (OSTI)

Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

2011-07-18T23:59:59.000Z

73

Relativistic mean-field models and nuclear matter constraints  

SciTech Connect (OSTI)

This work presents a preliminary study of 147 relativistic mean-field (RMF) hadronic models used in the literature, regarding their behavior in the nuclear matter regime. We analyze here different kinds of such models, namely: (i) linear models, (ii) nonlinear {sigma}{sup 3}+{sigma}{sup 4} models, (iii) {sigma}{sup 3}+{sigma}{sup 4}+{omega}{sup 4} models, (iv) models containing mixing terms in the fields {sigma} and {omega}, (v) density dependent models, and (vi) point-coupling ones. In the finite range models, the attractive (repulsive) interaction is described in the Lagrangian density by the {sigma} ({omega}) field. The isospin dependence of the interaction is modeled by the {rho} meson field. We submit these sets of RMF models to eleven macroscopic (experimental and empirical) constraints, used in a recent study in which 240 Skyrme parametrizations were analyzed. Such constraints cover a wide range of properties related to symmetric nuclear matter (SNM), pure neutron matter (PNM), and both SNM and PNM.

Dutra, M.; Lourenco, O.; Carlson, B. V. [Departamento de Fisica, Instituto Tecnologico de Aeronautica-CTA, 12228-900, Sao Jose dos Campos, SP (Brazil); Delfino, A. [Instituto de Fisica, Universidade Federal Fluminense, 24210-150, Boa Viagem, Niteroi, RJ (Brazil); Menezes, D. P.; Avancini, S. S. [Departamento de Fisica, CFM, Universidade Federal de Santa Catarina, CP. 476, CEP 88.040-900, Florianopolis, SC (Brazil); Stone, J. R. [Oxford Physics, University of Oxford, OX1 3PU Oxford (United Kingdom) and Department of Physics and Astronomy, University of Tennessee, Knoxville, Tennessee 37996 (United States); Providencia, C. [Centro de Fisica Computacional, Department of Physics, University of Coimbra, P-3004-516 Coimbra (Portugal); Typel, S. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Theorie, Planckstrasse 1,D-64291 Darmstadt (Germany)

2013-05-06T23:59:59.000Z

74

Validation of nuclear models used in space radiation shielding applications  

SciTech Connect (OSTI)

A program of verification and validation has been undertaken to assess the applicability of models to space radiation shielding applications and to track progress as these models are developed over time. In this work, simple validation metrics applicable to testing both model accuracy and consistency with experimental data are developed. The developed metrics treat experimental measurement uncertainty as an interval and are therefore applicable to cases in which epistemic uncertainty dominates the experimental data. To demonstrate the applicability of the metrics, nuclear physics models used by NASA for space radiation shielding applications are compared to an experimental database consisting of over 3600 experimental cross sections. A cumulative uncertainty metric is applied to the question of overall model accuracy, while a metric based on the median uncertainty is used to analyze the models from the perspective of model development by examining subsets of the model parameter space.

Norman, Ryan B., E-mail: Ryan.B.Norman@nasa.gov [NASA Langley Research Center, Hampton, VA 23681 (United States); Blattnig, Steve R. [NASA Langley Research Center, Hampton, VA 23681 (United States)] [NASA Langley Research Center, Hampton, VA 23681 (United States)

2013-01-15T23:59:59.000Z

75

Nuclear temperature effects in the scission-point model of nuclear fission  

Science Journals Connector (OSTI)

According to the scission-point model, the probability for a particular fission event can be expressed in terms of the collective potential and the collective kinetic energy at the scission point. Two additional assumptions make the scission-point model an easily calculable model: the assumption of equal collective kinetic energies for constant distances d between the tips of the fragments, and the assumption that one is able to characterize the excitation energy of the fragments with a nuclear temperature T, independent of both the mass ratio and the charge ratio, and of the deformations of the fragments. It is pointed out that the latter assumption violates energy conservation. A modified, recursive procedure is proposed, resulting in an "energy conservation consistent" scission-point method. Mass and charge distributions for the fission of U235 and Cf252 compound systems have been calculated and compared with distributions following the "standard" scission-point method of Wilkins, Steinberg, and Chasman.NUCLEAR REACTIONS Scission-point model. Collective potential and intrinsic excitation energy. Nuclear temperature T. Mass and charge distributions. Fission of U235 and C252.

J. Moreau; K. Heyde; M. Waroquier

1983-10-01T23:59:59.000Z

76

PRAAGE-1988: An interactive IBM-PC code for aging analysis of NUREG-1150 systems  

SciTech Connect (OSTI)

Probabilistic Risk Assessments (PRA) contain a great deal of information for estimating the risk of a nuclear power plant but do not consider aging. PRAAGE (PRA+AGE) is an interactive, IBM-PC code for processing PRA-developed system models using non-aged failure rate data in conjunction with user-supplied time-dependent nuclear plant experience component failure rate data to determine the effects of component aging on a system's reliability as well as providing the age-dependent importances of various generic components. This paper describes the structure, use and application of PRAAGE to the aging analysis of the Peach Bottom 2 RHR system in the LPCI and SDC modes of operation. 4 refs., 15 figs., 5 tabs.

Fullwood, R.R.; Shier, W.G.

1988-01-01T23:59:59.000Z

77

Nuclear EMC effect in non-extensive statistical model  

SciTech Connect (OSTI)

In the present work, we attempt to describe the nuclear EMC effect by using the proton structure functions obtained from the non-extensive statistical quark model. We record that such model has three fundamental variables, the temperature T, the radius, and the Tsallis parameter q. By combining different small changes, a good agreement with the experimental data may be obtained. Another interesting point of the model is to allow phenomenological interpretation, for instance, with q constant and changing the radius and the temperature or changing the radius and q and keeping the temperature.

Trevisan, Luis A. [Departamento de Matematica e Estatistica, Universidade Estadual de Ponta Grossa, 84010-790, Ponta Grossa, PR (Brazil); Mirez, Carlos [ICET, Universidade Federal dos Vales do Jequitinhonha e Mucuri - UFVJM, Campus do Mucuri, Rua do Cruzeiro 01, Jardim Sao Paulo, 39803-371, Teofilo Otoni, MG (Brazil)

2013-05-06T23:59:59.000Z

78

Advanced nuclear reactors and tritium impacts. Modeling the aquatic pathway  

Science Journals Connector (OSTI)

The effective contribution of nuclear energy will depend on various factors related to economics, safety, public acceptance and sustainability. To assure, however, the nuclear energy development, reactor accident impacts, as Fukushima, must be evaluated in a predictive way. Environmental assessment models are used for evaluating the radiological impact of potential releases of radionuclides from nuclear reactors to the environment. It is important to evaluate, to the extent possible, the reliability of the predictions of such models, by comparing with measured values in the environment or by comparing with the predictions of other models. Tritium has a complex environmental behavior once released into the environment. It is essential to establish reference scenarios to allow the simulation of tritium aquatic pathway subsequent to accidental releases. For this purpose, two scenarios for seawater circulation were analyzed by hydrodynamic modeling. An inverse modeling procedure was successfully applied to estimate tide elevations on the borders, which are based on applying the harmonic constants and using the same overestimation percentage produced by model results to correct the border values. Simulations of validated model for postulated accidental releases of tritium inventory from heavy water reactors, whose doses could be relevant, were presented here. It was observed differences between the two scenarios for the transport modeling that were caused by the removal of large volume of polluted waters from the accident site and its dilution in the discharge area, which has minor tritium concentrations. Moreover, the processes involved in the dynamic transfer of tritium in the environment were analyzed in dependence on the environmental conditions of tropical coastal ecosystem.

Francisco Fernando Lamego Simões Filho; Abner Duarte Soares; André da Silva Aguiar; Celso Marcelo Franklin Lapa; Antonio Carlos Ferreira Guimarães

2013-01-01T23:59:59.000Z

79

Benchmarking nuclear models for Gamow-Teller response  

E-Print Network [OSTI]

A comparative study of the nuclear Gamow-Teller response (GTR) within conceptually different state-of-the-art approaches is presented. Three nuclear microscopic models are considered: (i) the recently developed charge-exchange relativistic time blocking approximation (RTBA) based on the covariant density functional theory, (ii) the shell model (SM) with an extended "jj77" model space and (iii) the non-relativistic quasiparticle random-phase approximation (QRPA) with a Brueckner G-matrix effective interaction. We study the physics cases where two or all three of these models can be applied. The Gamow-Teller response functions are calculated for 208-Pb, 132-Sn and 78-Ni within both RTBA and QRPA. The strengths obtained for 208-Pb are compared to data that enables a firm model benchmarking. For the nucleus 132-Sn, also SM calculations are performed within the model space truncated at the level of a particle-hole (ph) coupled to vibration configurations. This allows a consistent comparison to the RTBA where ph+phonon coupling is responsible for the spreading width and considerable quenching of the GTR. Differences between the models and perspectives of their future developments are discussed.

E. Litvinova; B. A. Brown; D. -L. Fang; T. Marketin; R. G. T. Zegers

2014-02-04T23:59:59.000Z

80

Pathway Controlled Penetration (PcP)  

SciTech Connect (OSTI)

The technical approach employs advanced computational simulation tools to demonstrate how current assets can destroy RWK-RFI-12-0001's HDBT, a tunnel complex with two portals built into the base of a granite mountain. The granite over layer is assumed to be 60 meters thick over both portals and 80 meters over the facility's mission space. Key S&T is the completed development of a highly innovative viscoplastic fracture material model, 3D parallel gas-fracture capabilities into FDEM, and a stochastic handling of the material properties. Phase I - Develop and validate code simulation tools: (1) develop, incorporate and validate AZ-Frac material model for granite; and (2) Develop and incorporate gas-driven-fracture modeling into LANL's FDEM MUNROU code; (3) Develop and incorporate stochastic features into FDEM modeling. Phase II - Conduct PcP analysis on above HDBT: (1) Acquire HDBT design data, develop simulation model; and (2) Evaluate and select most promising defeat alternative. Phase III - Deliver code, train Service target analysts, and conduct simulations against real world HDBTs. PcP uses advanced computer simulations to enhance HDBT functional defeat efforts. Newly developed material models that account for fractural energy coupled with the finite discrete element methodology (FDEM) will provide targeting packages that will create penetration avenues for current or future lethality options. This novel computational approach requires full 3D geologic and structure characterization as well as significant high performance computing capabilities. The goal is to distinctively alter the targeting paradigm by leveraging critical DoD assets along with insitu geologic strata. In other words, assets will utilize underground rock structure to their benefit by creating rubbilization zones that will allow pathway controlled penetration.

Knight, Earl E. [Los Alamos National Laboratory; Rougier, Esteban [Los Alamos National Laboratory; Zubelewicz, Aleksander [Los Alamos National Laboratory

2012-08-29T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Azimuthal Anisotropies as Stringent Test for Nuclear Transport Models  

E-Print Network [OSTI]

Azimuthal distributions of charged particles and intermediate mass fragments emitted in Au+Au collisions at 600AMeV have been measured using the FOPI facility at GSI-Darmstadt. Data show a strong increase of the in-plane azimuthal anisotropy ratio with the charge of the detected fragment. Intermediate mass fragments are found to exhibit a strong momentum-space alignment with respect of the reaction plane. The experimental results are presented as a function of the polar center-of-mass angle and over a broad range of impact parameters. They are compared to the predictions of the Isospin Quantum Molecular Dynamics model using three different parametrisations of the equation of state. We show that such highly accurate data provide stringent test for microscopic transport models and can potentially constrain separately the stiffness of the nuclear equation of state and the momentum dependence of the nuclear interaction.

P. Crochet; F. Rami; R. Dona; the FOPI Collaboration

1997-09-15T23:59:59.000Z

82

LATTICE-BOLTZMANN SIMULATIONS OF THE Pc -S -anw RELATIONSHIP  

E-Print Network [OSTI]

LATTICE-BOLTZMANN SIMULATIONS OF THE Pc - S - anw RELATIONSHIP Mark L. Porter 1, Dorthe-water experiments [Culligan et al., WRR, 2004]. Shan & Chen multi-component lattice-Boltzmann (LB) model. Mark L-component lattice-Boltzmann (LB) model. Schaap, Porter, Christensen and Wildenschild, WRR, 2007. Mark L. Porter

Wildenschild, Dorthe

83

Benchmarking nuclear models for Gamow-Teller response  

E-Print Network [OSTI]

A comparative study of the nuclear Gamow-Teller response (GTR) within conceptually different state-of-the-art approaches is presented. Three nuclear microscopic models are considered: (i) the recently developed charge-exchange relativistic time blocking approximation (RTBA) based on the covariant density functional theory, (ii) the shell model (SM) with an extended "jj77" model space and (iii) the non-relativistic quasiparticle random-phase approximation (QRPA) with a Brueckner G-matrix effective interaction. We study the physics cases where two or all three of these models can be applied. The Gamow-Teller response functions are calculated for 208-Pb, 132-Sn and 78-Ni within both RTBA and QRPA. The strengths obtained for 208-Pb are compared to data that enables a firm model benchmarking. For the nucleus 132-Sn, also SM calculations are performed within the model space truncated at the level of a particle-hole (ph) coupled to vibration configurations. This allows a consistent comparison to the RTBA where ph+ph...

Litvinova, E; Fang, D -L; Marketin, T; Zegers, R G T

2014-01-01T23:59:59.000Z

84

Projection Operator Formalisms and the Nuclear Shell Model  

E-Print Network [OSTI]

The shell model solve the nuclear many-body problem in a restricted model space and takes into account the restricted nature of the space by using effective interactions and operators. In this paper two different methods for generating the effective interactions are considered. One is based on a partial solution of the Schrodinger equation (Bloch-Horowitz or the Feshbach projection formalism) and other on linear algebra (Lee-Suzuki). The two methods are derived in a parallel manner so that the difference and similarities become apparent. The connections with the renormalization group are also pointed out.

B. K. Jennings

2005-04-13T23:59:59.000Z

85

METHANE de-NOX FOR UTILITY PC BOILERS  

SciTech Connect (OSTI)

The project seeks to develop and validate a new pulverized coal combustion system to reduce utility PC boiler NOx emissions to 0.15 lb/million Btu or less without post-combustion flue gas cleaning. Work during previous reporting periods completed the design, installation, shakedown and initial PRB coal testing of a 3-million Btu/h pilot system at BBP's Pilot-Scale Combustion Facility (PSCF) in Worcester, MA. Based on these results, modifications to the gas-fired preheat combustor and PC burner were defined, along with a modified testing plan and schedule. During the current reporting period, BBP's subcontract was modified to reflect changes in the pilot testing program, and the modifications to the gas-fired preheat combustor were completed. The Computational Fluid Dynamics (CFD) modeling approach was defined for the combined PC burner and 3-million Btu/h pilot system. Modeling of the modified gas-fired preheat combustor was also started.

Joseph Rabovitser; Bruce Bryan; Serguei Nester; Stan Wohadlo

2002-04-29T23:59:59.000Z

86

Nuclear winter revisited with a modern climate model and current nuclear arsenals: Still catastrophic consequences  

E-Print Network [OSTI]

of nuclear weapons states, with additional states trying to develop nuclear arsenals. We use a modern climate and upper stratosphere, producing a long aerosol lifetime. The indirect effects of nuclear weapons would. [2007], who showed that a regional nuclear conflict using 100 Hiroshima-size (15 kt) nuclear weapons

Stenchikov, Georgiy L.

87

PC/104 Embedded IOCs at Jefferson Lab  

SciTech Connect (OSTI)

Jefferson Lab has developed embedded IOCs based on PC/104 single board computers (SBC) for low level control systems. The PC/104 IOCs run EPICS on top of the RTEMS operating system. Two types of control system configurations are used in different applications, PC/104 SBC with commercial PC/104 I/O cards and PC/104 SBC with custom designed FPGA-based boards. RTEMS was built with CEXP shell to run on the PC/104 SBC. CEXP shell provides the function of dynamic object loading, which is similar to the widely used VxWorks operating system. Standard software configurations were setup for PC/104 IOC application development to provide a familiar format for new projects as well as ease the conversion of applications from VME based IOCs to PC/104 IOCs. Many new projects at Jefferson Lab are going to employ PC/104 SBCs as IOCs and some applications have already been running them for accelerator operations. The PC/104 - RTEMS IOC provides a free open source Real-Time Operating System (RTOS), low cost/maintenance, easily installed/ configured, flexible, and reliable solution for accelerator control and 12GeV Upgrade projects.

Jianxun Yan, Trent Allison, Sue Witherspoon, Anthony Cuffe

2009-10-01T23:59:59.000Z

88

METHANE de-NOX FOR UTILITY PC BOILERS  

SciTech Connect (OSTI)

The project seeks to develop and validate a new pulverized coal combustion system to reduce utility PC boiler NOx emissions to 0.15 lb per million Btu or less without post-combustion flue gas cleaning. Work during previous reporting periods completed the design, installation, shakedown and initial PRB coal testing of a 3-million Btu/h pilot system at BBP's Pilot-Scale Combustion Facility (PSCF) in Worcester, MA. Based on these results, modifications to the gas-fired preheat combustor and PC burner were defined, along with a modified testing plan and schedule. A revised subcontract was executed with BBP to reflect changes in the pilot testing program. Modeling activities were continued to develop and verify revised design approaches for both the Preheat gas combustor and PC burner. Reactivation of the pilot test system was then begun with BBP personnel. During the previous reporting period, reactivation of the pilot test system was completed with the modified Preheat gas combustor. Following shakedown of the modified gas combustor alone, a series of successful tests of the new combustor with PRB coal using the original PC burner were completed. NOx at the furnace exit was reduced significantly with the modified gas combustor, to as low as 150 ppm with only 36 ppm CO (both corrected to 3% O2). Concurrent with testing, GTI and BBP collaborated on development of two modified designs for the PC burner optimized to fire preheated char and pyrolysis products from the Preheat gas combustor. During the current reporting period, one of the two modified PC burner designs was fabricated and installed in the pilot test facility. Testing of the modified pilot system (modified gas combustor and modified PC burner) during the quarter included 38 tests with PRB coal. NOx reduction was significantly improved to levels as low as 60-100 ppmv with CO in the range of 35-112 ppmv without any furnace air staging.

Joseph Rabovitser; Bruce Bryan; Serguei Nester; Stan Wohadlo

2002-01-31T23:59:59.000Z

89

A nuclear vibron model applied to light and heavy nuclear molecules  

Science Journals Connector (OSTI)

A nuclear vibron model for nuclear molecules consisting of two clusters with inner structure is investigated. The Hamiltonian model has a UC1(6)?UC2(6)?UR(4)?SUC1(3)?SUC2(3)?SUR(3) dynamical symmetry. Applying a geometrical mapping, the relation of the parameter of the coherent state to the relative distance of the two clusters is deduced. The Hamiltonian model exhibits a minimum at relative distances different from zero. It is discussed how to deduce the potential, knowing the spectrum, and how to deduce the spectrum, knowing the potential. As a classical example the system 12C+12C is taken, where the spectrum is known and the internuclear potential can be obtained. This system serves as a consistency check of the method. Afterwards, the heavy system 96Sr+146Ba, playing a role as a subsystem of a possible three cluster molecule, is investigated and the possible structure of the spectrum is deduced. We show that in order to obtain a Hamiltonian consistent with a geometrical picture, the structure of this Hamiltonian is restricted. Ambiguities of the structure of the spectrum still exist but can be ordered into different classes.

Huitzilin Yépez-Martínez; Peter O. Hess; ?erban Mi?icu

2003-07-29T23:59:59.000Z

90

Prediction and Correlation of High-Pressure Gas Solubility in Polymers with Simplified PC-SAFT  

Science Journals Connector (OSTI)

Prediction and Correlation of High-Pressure Gas Solubility in Polymers with Simplified PC-SAFT ... Using simplified PC-SAFT we have modeled gas solubilities at high temperatures and pressures for the gases methane and carbon dioxide in each of the three polymers high-density polyethylene (HDPE), nylon polyamide-11 (PA-11), and poly(vinylidene fluoride) (PVDF). ... Equations of Simplified PC-SAFT ...

Nicolas von Solms; Michael L. Michelsen; Georgios M. Kontogeorgis

2005-03-26T23:59:59.000Z

91

Petri-Net Simulation Model of a Nuclear Component Degradation Process , E. Zioa,b  

E-Print Network [OSTI]

1 Petri-Net Simulation Model of a Nuclear Component Degradation Process Y.F. Lia* , E. Zioa,b , Y models [2-5] and simulation models [1, 6, 7]. The analytical degradation models can be further classified

Paris-Sud XI, Université de

92

Constituent quark model for nuclear stopping in high energy nuclear collisions  

Science Journals Connector (OSTI)

We study nuclear stopping in high energy nuclear collisions using the constituent quark model. It is assumed that wounded nucleons with a different number of interacted quarks hadronize in different ways. The probabilities of having such wounded nucleons are evaluated for proton-proton, proton-nucleus, and nucleus-nucleus collisions. After examining our model in proton-proton and proton-nucleus collisions and fixing the hadronization functions, it is extended to nucleus-nucleus collisions. It is used to calculate the rapidity distribution and the rapidity shift of final-state protons in nucleus-nucleus collisions. The computed results are in good agreement with the experimental data on 32S+32S at Elab=200A GeV and 208Pb+208Pb at Elab=160A GeV. Theoretical predictions are also given for proton rapidity distribution in 197Au+197Au at s=200A GeV (BNL-RHIC). We predict that the nearly baryon-free region will appear in the midrapidity region and the rapidity shift is ??y?=2.24.

T. K. Choi; M. Maruyama; F. Takagi

1997-02-01T23:59:59.000Z

93

PC Electronic Data Reporting Option (PEDRO) System  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

System Released: February 22, 2011 Download Pedro Application Patch Archive Background The PC Electronic Data Reporting Option, or PEDRO, system enables users to enter Energy...

94

Model of a nuclear - optically - pumped liquid laser  

SciTech Connect (OSTI)

The model of a nuclear - optically - pumped liquid laser is constructed and the laser characteristics are analysed for different parameters of the setup and pump pulse, compositions of the converter media and active elements. The lasing parameters of the liquid laser using heavy-water solution of {sup 245}Cm as the converter medium and neodymium-containing phosphorous oxychloride (phosphoryl chloride) as the active element are calculated. It follows from the results of calculations that lasing can be achieved in these media pumped by neutrons from the BARS-6 reactor. (lasers)

Seregin, A A; D'yachenko, P P; Seregina, E A [State Scientific Center of the Russian Federation 'A.I. Leipunski Institute for Physics and Power Engineering', Obninsk, Kaluga Region (Russian Federation)

2003-06-30T23:59:59.000Z

95

Hybrid reliability model for nuclear reactor safety system  

Science Journals Connector (OSTI)

The dependability of critical safety systems needs to be quantitatively determined in order to verify their effectiveness, e.g. with regard to regulatory requirements. Since modular redundant safety systems are not required for normal operation, their reliability is strongly dependent on periodic inspection. Several modeling methods for the quantitative assessment of dependability are described in the literature, with a broad variation in complexity and modeling power. Static modeling techniques such as fault tree analysis (FTA) or reliability block diagrams (RBD) are not capable of capturing redundancy and repair or test activities. Dynamic state space based models such as continuous time Markov chains (CTMC) are more powerful but often result in very large, intractable models. Moreover, exponentially distributed state residence times are not a correct representation of actual residence times associated with repair activities or periodic inspection. In this study, a hybrid model combines a system level RBD with a CTMC to describe the dynamics. The effects of periodic testing are modeled by redistributing state probabilities at deterministic test times. Applying the method to the primary safety shutdown system of the BR2(Belgian Reactor 2)—nuclear research reactor, resulted in a quantitative as well as a qualitative assessment of its reliability.

Steven Verlinden; Geert Deconinck; Bernard Coupé

2012-01-01T23:59:59.000Z

96

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants |  

Broader source: Energy.gov (indexed) [DOE]

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants January 31, 2012 - 2:09pm Addthis The Electric Power Research Institute (EPRI), the U.S. Department of Energy (DOE), and the U.S. Nuclear Regulatory Commission (NRC) released a new seismic study today that will help U.S. nuclear facilities in the central and eastern United States reassess seismic hazards. The Central and Eastern United States Seismic Source Characterization for Nuclear Facilities model and report is the culmination of a four-year effort among the participating organizations and replaces previous seismic source models used by industry and government since the late 1980s. The NRC is requesting U.S. nuclear power plants to reevaluate seismic

97

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants |  

Broader source: Energy.gov (indexed) [DOE]

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants January 31, 2012 - 2:09pm Addthis The Electric Power Research Institute (EPRI), the U.S. Department of Energy (DOE), and the U.S. Nuclear Regulatory Commission (NRC) released a new seismic study today that will help U.S. nuclear facilities in the central and eastern United States reassess seismic hazards. The Central and Eastern United States Seismic Source Characterization for Nuclear Facilities model and report is the culmination of a four-year effort among the participating organizations and replaces previous seismic source models used by industry and government since the late 1980s. The NRC is requesting U.S. nuclear power plants to reevaluate seismic

98

Analysis of the Independent Particle Model approach to Nuclear Densities  

E-Print Network [OSTI]

We present an analysis of the use of the Darwin-Fowler approximation in connection with the statistical IPM, by comparing the results of our recent studies with the occupation number approach (OCN) and some traditional statistical independent particle model (IPM) approaches. The analysis of level density works based on the statistical IPM reveals that the use of the the Darwin-Fowler approximation, in some of them, is theoretically inconsistent and some of their results should rather be considered as theoretical coincidences with other consistent approaches, than proofs of their validity. We conclude that, in general, the use of the Darwin-Fowler approximation with the statistical IPM should be used criteriously or, if possible, avoided altogether and suggest that the combinatorial IPM approaches have important advantages over the other models and formalisms analyzed in this paper, especially regarding the consistency of the microscopic description of the nuclear structure and dynamics of non highly excited systems.

F. B. Guimaraes

2012-08-31T23:59:59.000Z

99

MODELING ATMOSPHERIC RELEASES OF TRITIUM FROM NUCLEAR INSTALLATIONS  

SciTech Connect (OSTI)

Tritium source term analysis and the subsequent dispersion and consequence analyses supporting the safety documentation of Department of Energy nuclear facilities are especially sensitive to the applied software analysis methodology, input data and user assumptions. Three sequential areas in tritium accident analysis are examined in this study to illustrate where the analyst should exercise caution. Included are: (1) the development of a tritium oxide source term; (2) use of a full tritium dispersion model based on site-specific information to determine an appropriate deposition scaling factor for use in more simplified, broader modeling, and (3) derivation of a special tritium compound (STC) dose conversion factor for consequence analysis, consistent with the nature of the originating source material. It is recommended that unless supporting, defensible evidence is available to the contrary, the tritium release analyses should assume tritium oxide as the species released (or chemically transformed under accident's environment). Important exceptions include STC situations and laboratory-scale releases of hydrogen gas. In the modeling of the environmental transport, a full phenomenology model suggests that a deposition velocity of 0.5 cm/s is an appropriate value for environmental features of the Savannah River Site. This value is bounding for certain situations but non-conservative compared to the full model in others. Care should be exercised in choosing other factors such as the exposure time and the resuspension factor.

Okula, K

2007-01-17T23:59:59.000Z

100

Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach  

E-Print Network [OSTI]

Medical Nuclear Supply Chain Design: A Tractable Network Model and Computational Approach Anna of medical nuclear supply chains. Our focus is on the molybdenum supply chain, which is the most commonly is of special relevance to healthcare given the medical nuclear product's widespread use as well as the aging

Nagurney, Anna

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Resonances in Complex-Scaled Orthogonality Condition Model of Nuclear Cluster System  

Science Journals Connector (OSTI)

......Orthogonality Condition Model of Nuclear Cluster System Andras...Kiyoshi Kato * Institute of Nuclear Research of the Hungarian...It is shown that the energy and width of various...Mechanism of the Anomalous Energy Shift between \\voldmaths-States...Recent Developments in Nuclear Cluster Physics Hisashi......

András T. Kruppa; Kiyoshi Kato

1990-12-01T23:59:59.000Z

102

Seismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain, Nevada  

E-Print Network [OSTI]

was heated to replicate the effects of long-term storage of decaying nuclear waste and to study the effects for the long- term storage of high-level nuclear waste from reactors and decom- missioned atomic weaponsSeismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain

Snieder, Roel

103

THERMODYNAMIC MODEL FOR URANIUM DIOXIDE BASED NUCLEAR FUEL  

SciTech Connect (OSTI)

Many projects involving nuclear fuel rest on a quantitative understanding of the co-existing phases at various stages of burnup. Since the many fission products have considerably different abilities to chemically associate with oxygen, and the oxygen-to-metal molar ratio is slowly changing, the chemical potential of oxygen is a function of burnup. Concurrently, well-recognized small fractions of new phases such as inert gas, noble metals, zirconates, etc. also develop. To further complicate matters, the dominant UO2 fuel phase may be non-stoichiometric and most of the minor phases themselves have a variable composition dependent on temperature and possible contact with the coolant in the event of a sheathing breach. A thermodynamic fuel model to predict the phases in partially burned CANDU (CANada Deuterium Uranium) nuclear fuel containing many major fission products has been under development. The building blocks of the model are the standard Gibbs energies of formation of the many possible compounds expressed as a function of temperature. To these data are added mixing terms associated with the appearance of the component species in particular phases. In operational terms, the treatment rests on the ability to minimize the Gibbs energy in a multicomponent system, in our case using the algorithms developed by Eriksson. The model is capable of handling non-stoichiometry in the UO2 fluorite phase, dilute solution behaviour of significant solute oxides, noble metal inclusions, a second metal solid solution U(Pd-Rh-Ru)3, zirconate, molybdate, and uranate solutions as well as other minor solid phases, and volatile gaseous species.

Thompson, Dr. William T. [Royal Military College of Canada; Lewis, Dr. Brian J [Royal Military College of Canada; Corcoran, E. C. [Royal Military College of Canada; Kaye, Dr. Matthew H. [Royal Military College of Canada; White, S. J. [Royal Military College of Canada; Akbari, F. [Atomic Energy of Canada Limited, Chalk River Laboratories; Higgs, Jamie D. [Atomic Energy of Canada Limited, Point Lepreau; Thompson, D. M. [Praxair Inc.; Besmann, Theodore M [ORNL; Vogel, S. C. [Los Alamos National Laboratory (LANL)

2007-01-01T23:59:59.000Z

104

Model nuclear matter calculations in several Brueckner and Green's function theories  

Science Journals Connector (OSTI)

Model nuclear matter calculations are performed using two versions of the Brueckner theory (standard lowest order theory and a...? 00,? 10 and Galitskii's ladder approximation). Gr...

P. Haensel; C. Marville

1978-01-01T23:59:59.000Z

105

Development of nuclear models for higher energy calculations  

SciTech Connect (OSTI)

Two nuclear models for higher energy calculations have been developed in the regions of high and low energy transfer, respectively. In the former, a relativistic hybrid-type preequilibrium model is compared with data ranging from 60 to 800 MeV. Also, the GNASH exciton preequilibrium-model code with higher energy improvements is compared with data at 200 and 318 MeV. In the region of low energy transfer, nucleon-nucleus scattering is predominately a direct reaction involving quasi-elastic collisions with one or more target nucleons. We discuss various aspects of quasi-elastic scattering which are important in understanding features of cross sections and spin observables. These include (1) contributions from multi-step processes; (2) damping of the continuum response from 2p-2h excitations; (3) the ''optimal'' choice of frame in which to evaluate the nucleon-nucleon amplitudes; and (4) the effect of optical and spin-orbit distortions, which are included in a model based on the RPA the DWIA and the eikonal approximation. 33 refs., 15 figs.

Bozoian, M.; Siciliano, E.R.; Smith, R.D.

1988-01-01T23:59:59.000Z

106

Heavy oil characterization method for PC-SAFT  

Science Journals Connector (OSTI)

Abstract Oil characterization is a crucial step in modeling heavy oil systems. Since heavy oil consists of thousands of components, for modeling purpose it is required to lump hydrocarbons into pseudocomponents. New generation equation of state (EoS), Perturbed-Chain Statistical Associating Fluid Theory (PC-SAFT), has shown promising results for modeling heavy oil systems. However, single carbon number type characterization approach has been lacking for PC-SAFT until now. The characterization method presented in this paper is based on sorting the pseudocomponents according to their boiling points. Further, each boiling point cut is split into saturate, aromatic and polyaromatic fractions. Asphaltenes are treated as a single pseudocomponent. For calculations, the PC-SAFT parameters were obtained for each pseudocomponent. The characterization procedure was validated by predicting densities for two heavy oils, three heavy oil cuts and propane + Athabasca bitumen (AB) and CO2 + propane + AB systems and comparing the results with measured data (109 data points). The relative average deviation was at its highest 2.1 % for density. In addition, saturation pressures were predicted for propane + AB and CO2 + propane + AB systems (57 data points). The saturation pressure predictions were as good as predicted earlier in the literature with Peng–Robinson EoS (in this work: the relative average deviations were 7.2 % and 2.0 % for propane + AB and CO2 + propane + AB systems). The calculations demonstrated that densities and gas solubilities for heavy oil systems can be accurately predicted with PC-SAFT without any adjustable PC-SAFT parameters if the distillation curve is available.

Meri Saajanlehto; Ville Alopaeus

2014-01-01T23:59:59.000Z

107

Summary of "Materials Modeling and Simulations for Nuclear Fuels"  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Summary of "Materials Modeling and Simulations for Nuclear Fuels" Summary of "Materials Modeling and Simulations for Nuclear Fuels" (MMSNF 2013) workshop Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share "Materials Modeling and Simulations for Nuclear Fuels" (MMSNF 2013) workshop Workshop Summary Presentation during MMSNF Workshop in Chicago

108

Prediction of nuclear proteins using SVM and HMM models  

Science Journals Connector (OSTI)

All modules were trained and tested on a non-redundant dataset and evaluated using five-fold cross-validation ... based module/profile was developed for searching exclusively nuclear and non-nuclear domains in a ...

Manish Kumar; Gajendra PS Raghava

2009-01-01T23:59:59.000Z

109

Development of a computational model for nuclear electric orbital transfer vehicles  

E-Print Network [OSTI]

DEVELOPMENT OF A COMPUTATIONAL MODEL FOR NUCLEAR ELECTRIC ORBITAL TRANSFER VEHICLES A Thesis by WILLIAM FOUNTAIN LYON III Submitted to the Office of Graduate Studies of Texas ARM University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE August 1989 Major Subject: Nuclear Engineering DEVELOPMENT OF A COMPUTATIONAL MODEL FOR NUCLEAR ELECTRIC ORBITAL TRANSFER VEHICLES A Thesis by WILLIAM FOUNTAIN LYON III Approved as to style and content by: K. L...

Lyon, William Fountain

2012-06-07T23:59:59.000Z

110

Shell model nuclear matrix elements for competing mechanisms contributing to double beta decay  

SciTech Connect (OSTI)

Recent progress in the shell model approach to the nuclear matrix elements for the double beta decay process are presented. This includes nuclear matrix elements for competing mechanisms to neutrionless double beta decay, a comparison between closure and non-closure approximation for {sup 48}Ca, and an updated shell model analysis of nuclear matrix elements for the double beta decay of {sup 136}Xe.

Horoi, Mihai [Department of Physics, Central Michigan University, Mount Pleasant, Michigan, 48859 (United States)

2013-12-30T23:59:59.000Z

111

DOE/PC/88921--5  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

DOE/PC/88921--5 DOE/PC/88921--5 _)/ DE91 004343 DOE Technical Report No. DOE/PC/88921-5 Filth Quarterly Report on Research Grant No. DE-FG22-88PC88921 Title: SPIN-MAPPING OF COAL STRUCTURES WITH ESE AND ENDOR #._; Principal Investigators: R. L. Bellord and R. B. Clarkson ct"_, _' Institution: University of Illinois at Urbana-Champaign Date: December 1, 1989 t. US/DOE Patent Clearance is _ required prior to publication o! this document, " ABSTRACT The broad goals oi this project are Lodetermine by nondestructive magnetic resonance methods chemical and physical structural characteristics of organic parts of native and treated coals. In this project period, we have begun Lo explore a technique which promises to enable us Lofollow the course of coal cleaning processes with microscopic spatial resolution. For the past five years, our laboratory has worked on extensions oi the EPR

112

Wilson Engineering Services, PC | Open Energy Information  

Open Energy Info (EERE)

Services, PC Services, PC Jump to: navigation, search Logo: Wilson Engineering Services, PC Name Wilson Engineering Services, PC Address 9006 Mercer Pike Place Meadville, Pennsylvania Zip 16335 Sector Biomass Product Engineering Consulting Services Year founded 2008 Number of employees 1-10 Website [www.wilsonengineeringservices.com www.wilsonengineeringservices. ] Coordinates 41.5885016°, -80.1569891° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":41.5885016,"lon":-80.1569891,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

113

Sensitivity of economic performance of the nuclear fuel cycle to simulation modeling assumptions  

E-Print Network [OSTI]

Comparing different nuclear fuel cycles and assessing their implications require a fuel cycle simulation model as complete and realistic as possible. In this thesis, methodological implications of modeling choices are ...

Bonnet, Nicéphore

2007-01-01T23:59:59.000Z

114

METHANE de-NOX FOR UTILITY PC BOILERS  

SciTech Connect (OSTI)

The project seeks to develop and validate a new pulverized coal combustion system to reduce utility PC boiler NO{sub x} emissions to 0.15 lb per million Btu or less without post-combustion flue gas cleaning. Work during previous reporting periods completed the design, installation, shakedown and initial PRB coal testing of a 3-million Btu/h pilot system at BBP's Pilot-Scale Combustion Facility (PSCF) in Worcester, MA. Based on these results, modifications to the gas-fired preheat combustor and PC burner were defined, along with a modified testing plan and schedule. A revised subcontract was executed with BBP to reflect changes in the pilot testing program. Modeling activities were continued to develop and verify revised design approaches for both the Preheat gas combustor and PC burner. Reactivation of the pilot test system was then begun with BBP personnel. During the current reporting period, reactivation of the pilot test system was completed with the modified Preheat gas combustor. Following shakedown of the modified gas combustor alone, a series of successful tests of the new combustor with PRB coal using the original PC burner were completed. NO{sub x} at the furnace exit was reduced significantly with the modified gas combustor, to as low as 150 ppm with only 36 ppm CO (both corrected to 3% O{sub 2}). Concurrent with testing, GTI and BBP collaborated on development of two modified designs for the PC burner optimized to fire preheated char and pyrolysis products from the Preheat gas combustor.

Joseph Rabovitser; Bruce Bryan; Serguei Nester; Stan Wohadlo

2002-10-29T23:59:59.000Z

115

On the asymptotic methods for nuclear collective models  

E-Print Network [OSTI]

Contractions of orthogonal groups to Euclidean groups are applied to analytic descriptions of nuclear quantum phase transitions. The semiclassical asymptotic of multipole collective Hamiltonians are also investigated.

A. C. Gheorghe; A. A. Raduta

2009-03-26T23:59:59.000Z

116

Utility of Social Modeling in Assessment of a State’s Propensity for Nuclear Proliferation  

SciTech Connect (OSTI)

This report is the third and final report out of a set of three reports documenting research for the U.S. Department of Energy (DOE) National Security Administration (NASA) Office of Nonproliferation Research and Development NA-22 Simulations, Algorithms, and Modeling program that investigates how social modeling can be used to improve proliferation assessment for informing nuclear security, policy, safeguards, design of nuclear systems and research decisions. Social modeling has not to have been used to any significant extent in a proliferation studies. This report focuses on the utility of social modeling as applied to the assessment of a State's propensity to develop a nuclear weapons program.

Coles, Garill A.; Brothers, Alan J.; Whitney, Paul D.; Dalton, Angela C.; Olson, Jarrod; White, Amanda M.; Cooley, Scott K.; Youchak, Paul M.; Stafford, Samuel V.

2011-06-01T23:59:59.000Z

117

Heterogeneous nuclear reactor models for optimal xenon control  

SciTech Connect (OSTI)

In this study a thermal nuclear reactor is modeled as a two-dimensional lattice of fuel and control rods placed in an infinite-moderator in plane geometry. The two-group diffusion theory approximation is used for neutron transport. Space-time neutron balance equations are written for two groups and reduced to one space-time algebraic equation by using the two-dimensional Fourier transform. This equation is written at all fuel and control rod locations. Iodine-xenon and promethium-samarium dynamic equations are also written at fuel rod locations only. These equations are then linearized about an equilibrium point which is determined from the steady-state form of the original nonlinear system equations. After studying poisonless criticality, with and without control, and the stability of the open-loop system and after checking its controllability, a performance criterion is defined for the xenon-induced spatial flux oscillation problem in the form of a functional to be minimized. Linear-quadratic optimal control theory is then applied to solve the problem.

Gondal, I.A.

1984-01-01T23:59:59.000Z

118

Using Direct Sub-Level Entity Access to Improve Nuclear Stockpile Simulation Modeling  

SciTech Connect (OSTI)

Direct sub-level entity access is a seldom-used technique in discrete-event simulation modeling that addresses the accessibility of sub-level entity information. The technique has significant advantages over more common, alternative modeling methods--especially where hierarchical entity structures are modeled. As such, direct sub-level entity access is often preferable in modeling nuclear stockpile, life-extension issues, an area to which it has not been previously applied. Current nuclear stockpile, life-extension models were demonstrated to benefit greatly from the advantages of direct sub-level entity access. In specific cases, the application of the technique resulted in models that were up to 10 times faster than functionally equivalent models where alternative techniques were applied. Furthermore, specific implementations of direct sub-level entity access were observed to be more flexible, efficient, functional, and scalable than corresponding implementations using common modeling techniques. Common modeling techniques (''unbatch/batch'' and ''attribute-copying'') proved inefficient and cumbersome in handling many nuclear stockpile modeling complexities, including multiple weapon sites, true defect analysis, and large numbers of weapon and subsystem types. While significant effort was required to enable direct sub-level entity access in the nuclear stockpile simulation models, the enhancements were worth the effort--resulting in more efficient, more capable, and more informative models that effectively addressed the complexities of the nuclear stockpile.

Robert Y. Parker

1999-08-01T23:59:59.000Z

119

PC-ATOMIC Final Report 1 Joseph D. Touch1  

E-Print Network [OSTI]

. This document describes the PC-ATOMIC interface, its design, capabilities, and performance. The board design@isi.edu ABSTRACT: PC-ATOMIC is a PC interface for the ATOMIC LAN. PC- ATOMIC is implemented as a VL-Bus (VESA) short-form card for Intel i486 PCs, providing an interface for low-cost workstations to a 640 Mbps LAN

Touch, Joe

120

Prediction of Asphaltene Instability under Gas Injection with the PC-SAFT Equation of State  

Science Journals Connector (OSTI)

Prediction of Asphaltene Instability under Gas Injection with the PC-SAFT Equation of State† ... In this work, the applicability of simple and recombined live oil models using the PC-SAFT equation of state to predict the onset of asphaltene precipitation is demonstrated by studying pressure depletion and gas injection (carbon dioxide (CO2), nitrogen (N2), methane, and ethane) in oil reservoirs. ... The pure component PC-SAFT parameters are fitted to the saturated liquid density and vapor pressure data, and the oil/gas pseudocomponent parameters are estimated from molecular-weight-based correlations. ...

Doris L. Gonzalez; P. David Ting; George J. Hirasaki; Walter G. Chapman

2005-03-17T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

ccsd00001474, Model-independent tracking of criticality signals in nuclear multifragmentation data  

E-Print Network [OSTI]

parameter, de#28;ning two di#27;erent regimes at low and high incident energy, respectively, according of nuclear mul- tifragmentation reactions as observed in intermediate en- ergy heavy-ion collisions [1ccsd­00001474, version 2 ­ 6 Sep 2004 Model-independent tracking of criticality signals in nuclear

122

TAMCN: a tool for aggregate modeling of civil nuclear materials  

E-Print Network [OSTI]

involved in the creation, storage, and utilization of potentially destructive nuclear material. Western Europe and Japan, namely France, Belgium, the United Kingdom, Germany, Switzerland, and Japan, were chosen as a starting point because the issues...

Watson, Aaron Michael

2002-01-01T23:59:59.000Z

123

Dynamical Modeling of Economy in Global Nuclear Energy Market  

Science Journals Connector (OSTI)

Non-linear dynamical analysis for the global nuclear energy market is investigated. Currently, the market means a different characteristics comparing to the ... between two countries, which depends on the energy ...

Taeho Woo

2012-01-01T23:59:59.000Z

124

Modelling Power Output at Nuclear Power Plant by Neural Networks  

Science Journals Connector (OSTI)

In this paper, we propose two different neural network (NN) approaches for industrial process signal forecasting. Real data is available for this research from boiling water reactor type nuclear power reactors. N...

Jaakko Talonen; Miki Sirola; Eimontas Augilius

2010-01-01T23:59:59.000Z

125

High-energy nuclear quasielastic reactions: Decisive tests of nuclear-binding/pion models of the European Muon Collaboration effect  

Science Journals Connector (OSTI)

The light-cone nucleon momentum distributions obtained from nonrelativistic spectral functions or given by nuclear-binding/pion models are often used to analyze high-Q2 quasielastic and deep-inelastic (e,e’) reactions. We demonstrate that in such models the presence of non-nucleonic components causes the scattering from forward and backward moving target protons to be significantly different. Other models do not have this property. The sensitivity of current (e,e’p) and (p,pp) color transparency experiments is sufficient to observe these differences.

L. Frankfurt; G. A. Miller; M. Strikman

1992-01-06T23:59:59.000Z

126

High energy nuclear quasielastic reactions: Decisive tests of nuclear binding/pion models of the EMC effect  

SciTech Connect (OSTI)

The light-cone nucleon momentum distributions obtained from non- relativistic spectral functions or given by nuclear binding/pion models are often used to analyze high Q{sup 2} quasi-elastic and deep-inelastic (e,e{prime}) reactions. We demonstrate that in such models the presence of non-nucleonic components causes the scattering from forward and backward moving target protons to be significantly different. Other models do not have this property. The sensitivity of current (e,e{prime}p) and (p,pp) color transparency experiments is sufficient to observe these differences.

Frankfurt, L; Strikman, M [Washington Univ., Seattle, WA (United States). Inst. for Nuclear Theory AN SSSR, Leningrad (USSR). Inst. Yadernoj Fiziki; Miller, G A [Washington Univ., Seattle, WA (United States). Inst. for Nuclear Theory

1991-01-01T23:59:59.000Z

127

Optimization Online - Augmented L1 and Nuclear-Norm Models with ...  

E-Print Network [OSTI]

Jan 22, 2012 ... Augmented L1 and Nuclear-Norm Models with a Globally Linearly Convergent Algorithm. Ming-Jun Lai (mjlai ***at*** math.uga.edu) Wotao Yin ...

Ming-Jun Lai

2012-01-22T23:59:59.000Z

128

Deproletarianizing Agriculture Lemmens, P.C.  

E-Print Network [OSTI]

Deproletarianizing Agriculture Lemmens, P.C. ISDA 2010, Montpellier, June 28-30, 2010 1 DEPROLETARIANIZING AGRICULTURE RECOVERING AGRICULTURE FROM AGRIBUSINESS AND THE NEED FOR A COMMONS-BASED, OPEN SOURCE AGRICULTURE Dr. Pieter LEMMENS Wageningen University Centre for Methodical Ethics and Technology Assessment

Boyer, Edmond

129

A Model-Based Signal Processing Approach to Nuclear Explosion Monitoring  

SciTech Connect (OSTI)

This report describes research performed under Laboratory Research and Development Project 05-ERD-019, entitled ''A New Capability for Regional High-Frequency Seismic Wave Simulation in Realistic Three-Dimensional Earth Models to Improve Nuclear Explosion Monitoring''. A more appropriate title for this project is ''A Model-Based Signal Processing Approach to Nuclear Explosion Monitoring''. This project supported research for a radically new approach to nuclear explosion monitoring as well as allowed the development new capabilities in computational seismology that can contribute to NNSA/NA-22 Programs.

Rodgers, A; Harris, D; Pasyanos, M

2007-03-14T23:59:59.000Z

130

Model-Based Calculations of the Probability of a Country's Nuclear Proliferation Decisions  

SciTech Connect (OSTI)

The first nuclear weapon was detonated in August 1945 over Japan to end World War II. During the past six decades, the majority of the world's countries have abstained from acquiring nuclear weapons. However, a number of countries have explored the nuclear weapons option, 23 in all. Among them, 14 countries have dropped their interest in nuclear weapons after initiating some efforts. And nine of them today possess nuclear weapons. These countries include the five nuclear weapons states - U.S., Russia, U.K., France, and China - and the four non- NPT member states - Israel, India, Pakistan, and North Korea. Many of these countries initially used civilian nuclear power technology development as a basis or cover for their military program. Recent proliferation incidents in Iraq, Iran, and North Korea brought the world together to pay much attention to nuclear nonproliferation. With the expected surge in the use of nuclear energy for power generation by developing countries, the world's nuclear nonproliferation regime needs to be better prepared for potential future challenges. For the world's nuclear nonproliferation regime to effectively cope with any future proliferation attempts, early detection of potentially proliferation-related activities is highly desirable. Early detection allows the international community to respond and take necessary actions - ideally using political and diplomatic influences without resorting to harsh measures such as sanctions or military actions. In this regard, a capability to quantitatively predict the chance of a country's nuclear proliferation intent or activities is of significant interest. There have been various efforts in the research community to understand the determinants of nuclear proliferation and develop quantitative tools to predict nuclear proliferation events. These efforts have shown that information about the political issues surrounding a country's security along with economic development data can be useful to explain the occurrences of proliferation decisions. However, predicting major historical proliferation events using model-based predictions has been unreliable. Nuclear proliferation decisions by a country is affected by three main factors: (1) technology; (2) finance; and (3) political motivation [1]. Technological capability is important as nuclear weapons development needs special materials, detonation mechanism, delivery capability, and the supporting human resources and knowledge base. Financial capability is likewise important as the development of the technological capabilities requires a serious financial commitment. It would be difficult for any state with a gross national product (GNP) significantly less than that of about $100 billion to devote enough annual governmental funding to a nuclear weapon program to actually achieve positive results within a reasonable time frame (i.e., 10 years). At the same time, nuclear proliferation is not a matter determined by a mastery of technical details or overcoming financial constraints. Technology or finance is a necessary condition but not a sufficient condition for nuclear proliferation. At the most fundamental level, the proliferation decision by a state is controlled by its political motivation. To effectively address the issue of predicting proliferation events, all three of the factors must be included in the model. To the knowledge of the authors, none of the exiting models considered the 'technology' variable as part of the modeling. This paper presents an attempt to develop a methodology for statistical modeling and predicting a country's nuclear proliferation decisions. The approach is based on the combined use of data on a country's nuclear technical capability profiles economic development status, security environment factors and internal political and cultural factors. All of the information utilized in the study was from open source literature. (authors)

Li, Jun; Yim, Man-Sung; McNelis, David N. [Department of Nuclear Engineering North Carolina State University (United States)

2007-07-01T23:59:59.000Z

131

A modeling and control approach to advanced nuclear power plants with gas turbines  

Science Journals Connector (OSTI)

Abstract Advanced nuclear power plants are currently being proposed with a number of various designs. However, there is a lack of modeling and control strategies to deal with load following operations. This research investigates a possible modeling approach and load following control strategy for gas turbine nuclear power plants in order to provide an assessment way to the concept designs. A load frequency control strategy and average temperature control mechanism are studied to get load following nuclear power plants. The suitability of the control strategies and concept designs are assessed through linear stability analysis methods. Numerical results are presented on an advanced molten salt reactor concept as an example nuclear power plant system to demonstrate the validity and effectiveness of the proposed modeling and load following control strategies.

Günyaz Ablay

2013-01-01T23:59:59.000Z

132

BATMAN—an R package for the automated quantification of metabolites from nuclear magnetic resonance spectra using a Bayesian model  

Science Journals Connector (OSTI)

......methods and its results on an example dataset fitting 26 metabolites are comparable...automated quantification of metabolites from nuclear magnetic resonance spectra using a Bayesian model. | Nuclear Magnetic Resonance (NMR) spectra are......

Jie Hao; William Astle; Maria De Iorio; Timothy M D Ebbels

2012-08-01T23:59:59.000Z

133

Three-Dimensional Inversion of Magnetotelluric Data on a PC, Methodology  

Open Energy Info (EERE)

Dimensional Inversion of Magnetotelluric Data on a PC, Methodology Dimensional Inversion of Magnetotelluric Data on a PC, Methodology and Applications to the Coso Geothermal Field Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Conference Proceedings: Three-Dimensional Inversion of Magnetotelluric Data on a PC, Methodology and Applications to the Coso Geothermal Field Details Activities (1) Areas (1) Regions (0) Abstract: We describe here efforts in technology development to invert magnetotelluric (MT) data collected in geothermal settings for three-dimensional resistivity models using desktop PC's or small clusters. A finite difference scheme is utilized for the forward problem, with various options to compute the parameter Jacobians, and parameter step estimates are defined using an explicit Gauss-Newton step. The paper

134

Modeling Nuclear Fusion with an Ultracold Nonneutral Plasma  

SciTech Connect (OSTI)

In the hot dense interiors of stars and giant planets, nuclear fusion reactions are predicted to occur at rates that are greatly enhanced compared to those at low densities. The enhancement is caused by plasma screening of the repulsive Coulomb potential between nuclei, which increases the probability of the rare close collisions that are responsible for fusion. This screening enhancement is a small effect in the Sun, but is predicted to be much larger in dense objects such as white dwarf stars and giant planet interiors where the plasma is strongly correlated (i.e. where the Debye screening length is smaller than a mean interparticle spacing). However, strongly enhanced fusion reaction rates caused by plasma screening have never been definitively observed in the laboratory. This talk discusses a method for observing the enhancement using an analogy between nuclear energy and cyclotron energy in a cold nonneutral plasma in a strong magnetic field. In such a plasma, the cyclotron frequency is higher than other dynamical frequencies, so the kinetic energy of cyclotron motion is an adiabatic invariant. This energy is not shared with other degrees of freedom except through rare close collisions that break this invariant and couple the cyclotron motion to the other degrees of freedom. Thus, the cyclotron energy of an ion, like nuclear energy, can be considered to be an internal degree of freedom that is released only via rare close collisions. Furthermore, it has recently been shown that the rate of release of cyclotron energy is enhanced through plasma screening by precisely the same factor as that for the release of nuclear energy, because both processes rely on close collisions that are enhanced by plasma screening in the same way. Simulations and experiments measuring large plasma screening enhancements for the first time will be discussed, and the possibility of exciting and studying cyclotron burn fronts will also be considered.

Dubin, Daniel H. E. [Physics Dept., UCSD, 9500 Gilman Drive, La Jolla CA 92093-0319 (United States)

2007-08-02T23:59:59.000Z

135

Transient modeling of thermionic space nuclear power systems  

E-Print Network [OSTI]

Thermionic Core-Converter 18 Neutron Kinetics . Active Length of the Core Inactive Length of the Core . . . Plena Inlet and Outlet to Core. . . . . . . . 21 . . . 22 . . . . . 22 Radiator Assembly. Radiator 23 23 Headers Inlet and Outlet... Temperature for the Loss of Flow Transient 37 tx Figure 13. Efficiency of the Thermionic Converters for the Loss of Flow Transient. . Page 38 14. Core Thermal Power Profile for the Power Start-up of the TOPAZ II Space Nuclear Power System. 15. Pump...

Berge, Francoise M

1991-01-01T23:59:59.000Z

136

Anonymous nuclear loci in non-model organisms: making the most of high-throughput genome surveys  

Science Journals Connector (OSTI)

......de novo and anonymous nuclear loci (ANL) are proving...produce robust multilocus datasets. Results: By successively...129-142. Anonymous nuclear loci in non-model...de novo and anonymous nuclear loci (ANL) are proving...produce robust multilocus datasets. RESULTS: By successively......

Terry Bertozzi; Kate L. Sanders; Mark J. Sistrom; Michael G. Gardner

2012-07-15T23:59:59.000Z

137

Two novel procedures for aggregating randomized model ensemble outcomes for robust signal reconstruction in nuclear power plants monitoring systems  

E-Print Network [OSTI]

reconstruction in nuclear power plants monitoring systems P. Baraldi1 , E. Zio1,* , G. Gola2 , D. Roverso2 , M importance for the safe and reliable operation of nuclear power plants. Auto-associative regression models of nuclear power plants for it allows the timely detection of malfunctions and anomalies during operation

Paris-Sud XI, Université de

138

Antiferromagnet-based nuclear spin model of scalable quantum register with inhomogeneous magnetic field  

E-Print Network [OSTI]

As a nuclear spin model of scalable quantum register, the one-dimensional chain of the magnetic atoms with nuclear spins 1/2 substituting the basic atoms in the plate of nuclear spin free easy-axis 3D antiferromagnet is considered. It is formulated the generalized antiferromagnet Hamiltonian in spin-wave approximation (low temperatures) considering the inhomogeneous external magnetic field, which is directed along the easy axis normally to plane of the plate and has a constant gradient along the nuclear spin chain. Assuming a weak gradient, the asymptotic expression for coefficients of unitary transformations to the diagonal form of antiferromagnet Hamiltonian is found. With this result the expression for indirect interspin coupling, which is due to hyperfine nuclear electron coupling in atoms and the virtual spin wave propagation in antiferromagnet ground state, was evaluated. It is shown that the inhomogeneous magnetic field essentially modifies the characteristics of indirect interspin coupling. The indirect interaction essentially grows and even oscillates in relation to the interspin distance when the local field value in the middle point of two considered nuclear spin is close to the critical field for quantum phase transition of spin-flop type in bulk antiferromagnet or close to antiferromagnetic resonance. Thus, the external magnetic field, its gradient, microwave frequency and power can play the role of control parameters for qubit states. Finally, the one and two qubit states decoherence and longitudinal relaxation rate are caused by the interaction of nuclear spins with virtual spin waves in antiferromagnet ground state are calculated.

A. A. Kokin; V. A. Kokin

2008-12-01T23:59:59.000Z

139

Nano-Continuum Modeling of a Nuclear Glass Specimen Altered for 25 Years  

SciTech Connect (OSTI)

The purpose of this contribution is to report on preliminary nano-continuum scale modeling of nuclear waste glass corrosion. The focus of the modeling is an experiment involving a French glass SON68 specimen leached for 25 years in a granitic environment. In this report, we focus on capturing the nano-scale concentration profiles. We use a high resolution continuum model with a constant grid spacing of 1 nanometer to investigate the glass corrosion mechanisms.

Steefel, Carl

2014-01-06T23:59:59.000Z

140

Accurate shell-model nuclear matrix elements for neutrinoless double-beta decay  

E-Print Network [OSTI]

We investigate a novel method of accurate calculation of the neutrinoless double-$\\beta$ decay shell-model nuclear matrix elements for the experimentally relevant case of $^{76}$Ge. We demonstrate that with the new method the nuclear matrix elements have perfect convergence properties and, using only the first 100 intermediate states of each spin, the matrix elements can be calculated with better than 1% accuracy. Based on the analysis of neutrinoless double-beta decays of $^{48}$Ca, $^{82}$Se, and $^{76}$Ge isotopes, we propose a new method to estimate the optimal values of the average closure energies at which the closure approximation gives the most accurate nuclear matrix elements. We also analyze the nuclear matrix elements for the heavy-neutrino-exchange mechanism, and we show that our method can be used to quench contributions from different intermediate spin states.

R. A. Sen'kov; M. Horoi

2014-11-06T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Comparative study of three-nucleon force models in nuclear matter  

E-Print Network [OSTI]

We calculate the energy per particle of symmetric nuclear matter and pure neutron matter using the microscopic many-body Brueckner-Hartree-Fock (BHF) approach and employing the Argonne V18 (AV18) nucleon-nucleon (NN) potential supplemented with two different three-nucleon force models recently constructed to reproduce the binding energy of $^3$H, $^3$He and $^4$He nuclei as well as the neutron-deuteron doublet scattering length. We find that none of these new three-nucleon force models is able to reproduce simultaneously the empirical saturation point of symmetric nuclear matter and the properties of three- and four-nucleon systems.

Logoteta, Domenico; Bombaci, Ignazio; Kievsky, Alejandro

2015-01-01T23:59:59.000Z

142

Fuel cycle modelling of open cycle thorium-fuelled nuclear energy systems  

Science Journals Connector (OSTI)

Abstract In this study, we have sought to determine the advantages, disadvantages, and viability of open cycle thorium–uranium-fuelled (Th–U-fuelled) nuclear energy systems. This has been done by assessing three such systems, each of which requires uranium enriched to ?20% 235U, in comparison to a reference uranium-fuelled (U-fuelled) system over various performance indicators, spanning material flows, waste composition, economics, and proliferation resistance. The values of these indicators were determined using the UK National Nuclear Laboratory’s fuel cycle modelling code ORION. This code required the results of lattice-physics calculations to model the neutronics of each nuclear energy system, and these were obtained using various nuclear reactor physics codes and burn-up routines. In summary, all three Th–U-fuelled nuclear energy systems required more separative work capacity than the equivalent benchmark U-fuelled system, with larger levelised fuel cycle costs and larger levelised cost of electricity. Although a reduction of ?6% in the required uranium ore per kWh was seen for one of the Th–U-fuelled systems compared to the reference U-fuelled system, the other two Th–U-fuelled systems required more uranium ore per kWh than the reference. Negligible advantages and disadvantages were observed for the amount and the properties of the spent nuclear fuel (SNF) generated by the systems considered. Two of the Th–U-fuelled systems showed some benefit in terms of proliferation resistance of the SNF generated. Overall, it appears that there is little merit in incorporating thorium into nuclear energy systems operating with open nuclear fuel cycles.

S.F. Ashley; B.A. Lindley; G.T. Parks; W.J. Nuttall; R. Gregg; K.W. Hesketh; U. Kannan; P.D. Krishnani; B. Singh; A. Thakur; M. Cowper; A. Talamo

2014-01-01T23:59:59.000Z

143

A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty  

E-Print Network [OSTI]

A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty@csam.ucl.ac.be, Gevers@csam.ucl.ac.be 2 Electricite de France, Direction des Etudes et Recherches, 6 Quai Watier, F-78041 of a controller for the secondary circuit of a nu- clear Pressurized Water Reactor, leading to the conclu- sions

Gevers, Michel

144

Correlated basis function results for the Argonne models of nuclear matter  

Science Journals Connector (OSTI)

Correlated basis function calculations of the binding energy, the optical potential and the self-energy of nuclear matter models based on the Argonne ?14 interaction are presented. The results obtained are compared with the existing correlated basis calculations performed for corresponding models based on the Urbana ?14 potential. The two potentials lead to significative differences in the self-energy and related quantities. The results show an overall agreement with calculations based on Brueckner-Hartree-Fock theory.

A. Fabrocini; S. Fantoni

1993-01-01T23:59:59.000Z

145

Caloric Curves for small systems in the Nuclear Lattice Gas Model  

E-Print Network [OSTI]

For pedagogical reasons we compute the caloric curve for 11 particles in a $3^3$ lattice. Monte-Carlo simulation can be avoided and exact results are obtained. There is no back-bending in the caloric curve and negative specific heat does not appear. We point out that the introduction of kinetic energy in the nuclear Lattice Gas Model modifies the results of the standard Lattice Gas Model in a profound way.

C. B. Das; S. Das Gupta

2000-09-27T23:59:59.000Z

146

High-energy nuclear collisions in the geometrical branching model  

Science Journals Connector (OSTI)

The geometrical branching model, which has been successful in describing multiparticle production in hadron-hadron and hadron-nucleus collisions, is extended to the case of nucleus-nucleus collisions at high energy. We discuss the issue related to the collision between broken nucleons. The calculated result is in good agreement with the data. We show that the multiplicity and transverse-energy distributions of the produced particles are insensitive to the detail properties of hadronization. Measurable quantities that could reveal relevant information on them are suggested.

Rudolph C. Hwa and Xin-Nian Wang

1990-09-01T23:59:59.000Z

147

Monte Carlo methods for the nuclear shell model  

E-Print Network [OSTI]

We present novel Monte Carlo methods for treating the interacting shell model that allow exact calculations much larger than those heretofore possible. The two-body interaction is linearized by an auxiliary field; Monte Carlo evaluation of the resulting functional integral gives ground-state or thermal expectation values of few-body operators. The ``sign problem'' generic to quantum Monte Carlo calculations is absent in a number of cases. We discuss the favorable scaling of these methods with nucleon numb er and basis size and their suitability to parallel computation.

C. W. Johnson; S. E. Koonin; G. H. Lang; W. E. Ormand

1992-10-20T23:59:59.000Z

148

Illicit trafficking of radiological & nuclear materials : modeling and analysis of trafficking trends and risks.  

SciTech Connect (OSTI)

Concerns over the illicit trafficking of radiological and nuclear materials were focused originally on the lack of security and accountability of such material throughout the former Soviet states. This is primarily attributed to the frequency of events that have occurred involving the theft and trafficking of critical material components that could be used to construct a Radiological Dispersal Device (RDD) or even a rudimentary nuclear device. However, with the continued expansion of nuclear technology and the deployment of a global nuclear fuel cycle these materials have become increasingly prevalent, affording a more diverse inventory of dangerous materials and dual-use items. To further complicate the matter, the list of nuclear consumers has grown to include: (1) Nation-states that have gone beyond the IAEA agreed framework and additional protocols concerning multiple nuclear fuel cycles and processes that reuse the fuel through reprocessing to exploit technologies previously confined to the more industrialized world; (2) Terrorist organizations seeking to acquire nuclear and radiological material due to the potential devastation and psychological effect of their use; (3) Organized crime, which has discovered a lucrative market in trafficking of illicit material to international actors and/or countries; and (4) Amateur smugglers trying to feed their families in a post-Soviet era. An initial look at trafficking trends of this type seems scattered and erratic, localized primarily to a select group of countries. This is not necessarily the case. The success with which other contraband has been smuggled throughout the world suggests that nuclear trafficking may be carried out with relative ease along the same routes by the same criminals or criminal organizations. Because of the inordinately high threat posed by terrorist or extremist groups acquiring the ingredients for unconventional weapons, it is necessary that illicit trafficking of these materials be better understood as to prepare for the sustained global development of the nuclear fuel cycle. Conversely, modeling and analyses of this activity must not be limited in their scope to loosely organized criminal smuggling, but address the problem as a commercial, industrial project for the covert development of nuclear technologies and unconventional weapon development.

York, David L.; Love, Tracia L.; Rochau, Gary Eugene

2005-01-01T23:59:59.000Z

149

A cellular automaton model for the change of public attitude regarding nuclear energy  

Science Journals Connector (OSTI)

A model was constructed to investigate how the public opinion on nuclear energy varies depending upon information environment and personal communication between people. Here the nuclear risk informed of by the newsmedia and the frequency of anti-nuclear movements are treated as exogenous variables. The information environment is assumed to be represented in terms of public opinion as well as those exogenous variables, and the public are assumed to vary, randomly but homogeneously in a global sense, their attitude regarding nuclear energy in accordance with the strength of information environment. Personal communication begins round some opinion leaders who were excited by the information environment, and the attitude of the public who are affected by the opinion leaders are secondarily changed to anti-nuclear or pronuclear states. Moreover the public attitude is also changed naturally in an exponential way with time. Public opinion is supposed to appear as a superposed result of these three modes of attitudinal change. Such public opinion is fed back to the information environment. All the treatments are discretized and the process of personal communication is modeled by the cellular automaton method. Each cell in this approach is assumed to take one discrete state of six possible states which represent the status of public opinion. Model constants are determined by fitting calculations to the actual fraction of opinion in Japan. From simulation with this model, the following become clear: (i) The society is a highly non-linear system with a self-organizing potential: (ii) In the society composed of one type of constituent members with a homogeneous characteristic, the trend of public opinion is catastrophically turned over only when the effort for ameliorating the public acceptance extended over a long period of time, such as education, persuasion and advertisement, exceeds a certain threshold, and (iii) in the case when the amount of information on nuclear risk released from the newsmedia is reduced continuously from now on, the acceptability of nuclear energy is remarkably improved so far as the extent of the reduction exceeds a certain threshold.

Teruaki Ohnishi

1991-01-01T23:59:59.000Z

150

Magnetic moment of hyperons in nuclear matter by using quark-meson coupling models  

E-Print Network [OSTI]

We calculate the magnetic moments of hyperons in dense nuclear matter by using relativistic quark models. Hyperons are treated as MIT bags, and the interactions are considered to be mediated by the exchange of scalar and vector mesons which are approximated as mean fields. Model dependence is investigated by using the quark-meson coupling model and the modified quark-meson coupling model; in the former the bag constant is independent of density and in the latter it depends on density. Both models give us the magnitudes of the magnetic moments increasing with density for most octet baryons. But there is a considerable model dependence in the values of the magnetic moments in dense medium. The magnetic moments at the nuclear saturation density calculated by the quark meson coupling model are only a few percents larger than those in free space, but the magnetic moments from the modified quark meson coupling model increase more than 10% for most hyperons. The correlations between the bag radius of hyperons and the magnetic moments of hyperons in dense matter are discussed.

C. Y. Ryu; C. H. Hyun; T. -S. Park; S. W. Hong

2008-06-06T23:59:59.000Z

151

$?$-mass Modification in $He^3$ - a Signal of Restoration of Chiral Symmetry or Test for Nuclear Matter Models ?  

E-Print Network [OSTI]

Two recent experiments have demonstrated that the effective $\\rho$-mass in nuclear medium, as extracted from the $^3He(\\gamma, \\pi^+ \\pi^-)$ reaction, is substantially reduced. This has been advocated as an indication of partial restoration of chiral symmetry in nuclear matter. We show that even in the absence of chiral symmetry, effective mean field nuclear matter models can explain these findings quantitatively.

Abhijit Bhattacharyya; Sanjay K. Ghosh; Sibaji Raha

1999-02-23T23:59:59.000Z

152

Coulomb energy of a proton in the relativistic nuclear shell model  

Science Journals Connector (OSTI)

We examine the Dirac equation for a proton in a nucleus, with a shell-model potential consisting of nuclear and Coulomb parts. When the Dirac equation is reduced to a Schrödinger-like equation, the effective potential W in it exhibits two Coulomb-related effects that are absent in the usual nonrelativistic treatment: (I) W contains a Coulomb-nuclear interference term; (II) W depends strongly on the proton energy, which in turn depends on the Coulomb energy. If the shell-model potential consists of a strongly attractive Lorentz scalar and a strongly repulsive Lorentz vector, effect I by itself is very large. However, effect II counteracts effect I, leaving a small yet significant decrease in the Coulomb energy as compared with its nonrelativistic counterpart.

Y. Nogami and F. M. Toyama

1990-12-01T23:59:59.000Z

153

Nuclear modification factors of pion and light nuclei in a framework of thermal model  

E-Print Network [OSTI]

The particle yields and the nuclear modification factor ($R_{cp}$) for $\\pi^\\pm$, $p(\\bar p)$, $d(\\bar d)$, $t(\\bar t)$ and $^3He(\\bar{^3He})$ are studied in Au + Au collisions at $\\sqrt{S_{NN}}$ = 200 GeV/c based on the blast-wave model and nucleonic coalescence model. The influences of resonance decay on $p(\\bar p)$ and $\\pi$ yields, $p/\\pi$-ratio and nuclear modification factors have been discussed. An apparent number-of-constituent-quark scaling of $R_{cp}$ for $p(\\bar p)$ and $\\pi$ is presented. Similarly, the number-of-nucleon scaling of $R_{cp}$ for $p(\\bar p)$, $d(\\bar d)$, $t(\\bar t)$ and $^3He(\\bar{^3He})$ is also addressed.

Zhou, C S; Zhang, S

2015-01-01T23:59:59.000Z

154

The impact of global nuclear mass model uncertainties on $r$-process abundance predictions  

E-Print Network [OSTI]

Rapid neutron capture or `$r$-process' nucleosynthesis may be responsible for half the production of heavy elements above iron on the periodic table. Masses are one of the most important nuclear physics ingredients that go into calculations of $r$-process nucleosynthesis as they enter into the calculations of reaction rates, decay rates, branching ratios and Q-values. We explore the impact of uncertainties in three nuclear mass models on $r$-process abundances by performing global monte carlo simulations. We show that root-mean-square (rms) errors of current mass models are large so that current $r$-process predictions are insufficient in predicting features found in solar residuals and in $r$-process enhanced metal poor stars. We conclude that the reduction of global rms errors below $100$ keV will allow for more robust $r$-process predictions.

Mumpower, M; Aprahamian, A

2014-01-01T23:59:59.000Z

155

Analytical expressions of the dispersive contributions of the nuclear optical model  

E-Print Network [OSTI]

Analytical solutions of dispersion relations in the nuclear optical model have been found for both imaginary volume and surface potentials. A standard Brown-Rho shape has been assumed for the volume imaginary term and a Brown-Rho shape multiplied by a decreasing exponential for the surface contribution. The analytical solutions are valid for any even value of the exponent appearing in these functional forms.

J. M. Quesada; R. Capote; J. Raynal; A. Molina; M. Lozano

2002-10-23T23:59:59.000Z

156

Consequence modeling for nuclear weapons probabilistic cost/benefit analyses of safety retrofits  

SciTech Connect (OSTI)

The consequence models used in former studies of costs and benefits of enhanced safety retrofits are considered for (1) fuel fires; (2) non-nuclear detonations; and, (3) unintended nuclear detonations. Estimates of consequences were made using a representative accident location, i.e., an assumed mixed suburban-rural site. We have explicitly quantified land- use impacts and human-health effects (e.g. , prompt fatalities, prompt injuries, latent cancer fatalities, low- levels of radiation exposure, and clean-up areas). Uncertainty in the wind direction is quantified and used in a Monte Carlo calculation to estimate a range of results for a fuel fire with uncertain respirable amounts of released Pu. We define a nuclear source term and discuss damage levels of concern. Ranges of damages are estimated by quantifying health impacts and property damages. We discuss our dispersal and prompt effects models in some detail. The models used to loft the Pu and fission products and their particle sizes are emphasized.

Harvey, T.F.; Peters, L.; Serduke, F.J.D.; Hall, C.; Stephens, D.R.

1998-01-01T23:59:59.000Z

157

Proceedings of the Numerical Modeling for Underground Nuclear Test Monitoring Symposium  

SciTech Connect (OSTI)

The purpose of the meeting was to discuss the state-of-the-art in numerical simulations of nuclear explosion phenomenology with applications to test ban monitoring. We focused on the uniqueness of model fits to data, the measurement and characterization of material response models, advanced modeling techniques, and applications of modeling to monitoring problems. The second goal of the symposium was to establish a dialogue between seismologists and explosion-source code calculators. The meeting was divided into five main sessions: explosion source phenomenology, material response modeling, numerical simulations, the seismic source, and phenomenology from near source to far field. We feel the symposium reached many of its goals. Individual papers submitted at the conference are indexed separately on the data base.

Taylor, S.R.; Kamm, J.R. [eds.

1993-11-01T23:59:59.000Z

158

Microsoft Word - S06970_2010PC  

Office of Legacy Management (LM)

NDEP Correspondence and Record of Review NDEP Correspondence and Record of Review This page intentionally left blank This page intentionally left blank Library Distribution List Copies U.S. Department of Energy 1 (Uncontrolled) National Nuclear Security Administration Nevada Site Office Technical Library P.O. Box 98518, M/S 505 Las Vegas, NV 89193-8518 (702) 295-3521 U.S. Department of Energy 1 (Uncontrolled, electronic copy) Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 (865) 576-8401 Southern Nevada Public Reading Facility 2 (Uncontrolled, electronic copies) c/o Nuclear Testing Archive P.O. Box 98521, M/S 400 Las Vegas, NV 89193-8521 Manager, Northern Nevada FFACO 1 (Uncontrolled, electronic copy) Public Reading Facility c/o Nevada State Library and Archives

159

A general numerical solution of dispersion relations for the nuclear optical model  

E-Print Network [OSTI]

A general numerical solution of the dispersion integral relation between the real and the imaginary parts of the nuclear optical potential is presented. Fast convergence is achieved by means of the Gauss-Legendre integration method, which offers accuracy, easiness of implementation and generality for dispersive optical model calculations. The use of this numerical integration method in the optical-model parameter search codes allows for a fast and accurate dispersive analysis. PACS number(s): 11.55.Fv, 24.10.Ht, 02.60.Jh

Roberto Capote; Alberto Molina; Jose Manuel Quesada

2001-05-09T23:59:59.000Z

160

Low density instabilities in asymmetric nuclear matter within the quark-meson coupling (QMC) model with the {delta} meson  

SciTech Connect (OSTI)

In the present work we include the isovector-scalar {delta} meson in the quark-meson coupling (QMC) model and study the properties of asymmetric nuclear within QMC without and with the {delta} meson. Recent constraints set by isospin diffusion on the slope parameter of the nuclear symmetry energy at saturation density are used to adjust the model parameters. The thermodynamical spinodal surfaces are obtained and the instability region at subsaturation densities within QMC and QMC{delta} models are compared with mean-field relativistic models. The distillation effect in the QMC model is discussed.

Santos, Alexandre M.; Providencia, Constanca; Panda, Prafulla K. [Centro de Fisica Computacional, Department of Physics, University of Coimbra, P-3004-516 Coimbra (Portugal); Indian Association for the Cultivation of Science, Jadavpur, Kolkata-700 032, India and Centro de Fisica Computacional, Department of Physics, University of Coimbra, P-3004-516 Coimbra (Portugal)

2009-04-15T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Recent developments of the cascade-exciton model of nuclear reactions  

SciTech Connect (OSTI)

Recent developments of the Cascade-Exciton Model (CEM) of nuclear reactions are described. The improved cascade-exciton model as implemented in the code CEM97 differs from the CEM95 version by incorporating new approximations for the elementary cross sections used in the cascade, using more precise values for nuclear masses and pairing energies, using corrected systematics for the level-density parameters, and several other refinements. We have improved algorithms used in many subroutines, decreasing the computing time by up to a factor of 6 for heavy targets. We describe a number of further improvements and changes to CEM97, motivated by new data on isotope production measured at GSI. This leads us to CEM2k, a new version of the CEM code. CEM2k has a longer cascade stage, less preequilibrium emission, and evaporation from more highly excited compound nuclei compared to earlier versions. CEM2k also has other improvements and allows us to better model neutron, radionuclide, and gas production in ATW spallation targets. The increased accuracy and predictive power of the code CEM2k are shown by several examples. Further necessary work is outlined. KEYWORDS: Intranuclear cascade, preequilibrium, evaporation, and fission reactions, Monte Carlo simulations, cascade-exciton model, particle spectra, spallation and fission cross sections, GSI data

Mashnik, S. G. (Stepan G.); Sierk, A. J. (Arnold J.)

2001-01-01T23:59:59.000Z

162

Nuclear Physics: A Key Ingredient in Astrophysical Modeling F.-K. Thielemann, D. Argast, F. Brachwitz, J.L. Fisker, C. Frohlich, R. Hirschi, E.  

E-Print Network [OSTI]

1 Nuclear Physics: A Key Ingredient in Astrophysical Modeling F.-K. Thielemann, D. Argast, F of Physics & Astronomy, Univ. of Basel, Klingelbergstrasse 82, CH-4056 Basel, Switzerland Nuclear physics. In this review we will survey how these aspects of nuclear physics enter the modeling of astrophysical objects. 1

Rauscher, Thomas

163

THE STRUCTURAL CHEMISTRY OF MOLYBDENUM IN MODEL HIGH LEVEL NUCLEAR WASTE GLASSES, INVESTIGATED BY MO K-EDGE X-RAY ABSORPTION  

E-Print Network [OSTI]

THE STRUCTURAL CHEMISTRY OF MOLYBDENUM IN MODEL HIGH LEVEL NUCLEAR WASTE GLASSES, INVESTIGATED of molybdenum in model UK high level nuclear waste glasses was investigated by X-ray Absorption Spectroscopy (XAS). Molybdenum K-edge XAS data were acquired from several inactive simulant high level nuclear waste

Sheffield, University of

164

Theory of nuclear reactions  

SciTech Connect (OSTI)

The book presents a theory of nuclear reaction. An account is given of the nonrelativistic nuclear reaction theory. The R - matrix description of nuclear reactions is considered and the dispersion method is formulated. Mechanisms of nuclear reactions and their relationship are studied in detail. Attention is paid to nuclear reactions involving the compound nuclear formation and to direct nuclear processes. The optical model the diffraction approach and high - energy diffraction nuclear processes involving composite particles are discussed.

Sitenko, A.G.

1990-01-01T23:59:59.000Z

165

Nuclear tools for characterising radiological dispersion in complex terrain: evaluation of regulatory and emergency response models  

Science Journals Connector (OSTI)

Routine operations of a nuclear research reactor and its facilities offer opportunities for collection of rare environmental tracer datasets which can be used for atmospheric dispersion model evaluation studies. The HIFAR reactor near Sydney, Australia, routinely emits the radioactive noble gas 41Ar, and other radionuclides such as 133Xe and 135Xe are also emitted from nearby radiopharmaceutical production facilities. Despite extremely low emission levels of these gases, they are nevertheless detectable using state-of-the-art technology, and sensitive detectors have been placed at four locations in the surrounding region which features complex terrain. The high research potential of this unique dataset is illustrated in the current study, in which predictions from two atmospheric dispersion models used for emergency response are compared with 41Ar peak observations from the detector network under a range of stability conditions, and long-term integrated data is also compared with a routine impact assessment model.

Alastair G. Williams; Geoffrey H. Clark; Leisa Dyer; Richard Barton

2005-01-01T23:59:59.000Z

166

Uncertainty and sensitivity analysis of biokinetic models for radiopharmaceuticals used in nuclear medicine  

Science Journals Connector (OSTI)

......who undergo the diagnosis in nuclear medicine. Table-2. The...radiopharmaceuticals used in nuclear medicine. As an example...1976) New York: Society of Nuclear Medicine. MIRD pamphlet no...Uncertainty in Quantitative Risk and Policy Analysis. (1990) New York......

W. B. Li; C. Hoeschen

2010-01-01T23:59:59.000Z

167

Nuclear magnetic resonance characterization of peptide models of collagen–folding diseases  

Science Journals Connector (OSTI)

...Dobson, R. J. Ellis and A. R. Fersht Nuclear magnetic resonance characterization of...disease such as osteogenesis imperfecta. Nuclear magnetic resonance (NMR) studies of...can lead to pathological conditions. nuclear magnetic resonance|collagen|osteogenesis...

2001-01-01T23:59:59.000Z

168

An adaptive simulation model for analysis of nuclear material shipping operations  

SciTech Connect (OSTI)

Los Alamos has developed an advanced simulation environment designed specifically for nuclear materials operations. This process-level simulation package, the Process Modeling System (ProMoS), is based on high-fidelity material balance criteria and contains intrinsic mechanisms for waste and recycle flows, contaminant estimation and tracking, and material-constrained operations. Recent development efforts have focused on coupling complex personnel interactions, personnel exposure calculations, and stochastic process-personnel performance criteria to the material-balance simulation. This combination of capabilities allows for more realistic simulation of nuclear material handling operations where complex personnel interactions are required. They have used ProMoS to assess fissile material shipping performance characteristics at the Los Alamos National Laboratory plutonium facility (TA-55). Nuclear material shipping operations are ubiquitous in the DOE complex and require the largest suite of varied personnel interacting in a well-timed manner to accomplish the task. They have developed a baseline simulation of the present operations and have estimated the operational impacts and requirement of the pit production mission at TA-55 as a result of the SSM-PEIS. Potential bottlenecks have been explored and mechanisms for increasing operational efficiency are identified.

Boerigter, S.T.; Sena, D.J.; Fasel, J.H.

1998-12-31T23:59:59.000Z

169

Site-specific parameter values for the Nuclear Regulatory Commission's food pathway dose model  

SciTech Connect (OSTI)

Routine operations at the Savannah River Site (SRS) in Western South Carolina result in radionuclide releases to the atmosphere and to the Savannah River. The resulting radiation doses to the off-site maximum individual and the off-site population within 80 km of the SRS are estimated on a yearly basis. These estimates are currently generated using dose models prescribed for the commercial nuclear power industry by the Nuclear Regulatory Commission (NRC). The NRC provides default values for dose-model parameters for facilities without resources to develop site-specific values. A survey of land- and water-use characteristics for the Savannah River area has been conducted to determine site-specific values for water recreation, consumption, and agricultural parameters used in the NRC Regulatory Guide 1.109 (1977) dosimetric models. These site parameters include local characteristics of meat, milk, and vegetable production; recreational and commercial activities on the Savannah River; and meat, milk, vegetable, and seafood consumption rates. This paper describes how parameter data were obtained at the Savannah River Site and the impacts of such data on off-site dose. Dose estimates using site-specific parameter values are compared to estimates using the NRC default values.

Hamby, D.M. (Westinghouse Savannah River Company, Savannah River Laboratory, Aiken, SC (United States))

1992-02-01T23:59:59.000Z

170

System modeling for the advanced thermionic initiative single cell thermionic space nuclear reactor  

SciTech Connect (OSTI)

Incore thermionic space reactor design concepts which operate in a nominal power output range of 20 to 40 kWe are described. Details of the neutronics, thermionic, shielding, and heat rejection performance are presented. Two different designs, ATI-Driven and ATI-Driverless, are considered. Comparison of the core overall performance of these two configurations are described. The comparison of these two cores includes the overall conversion efficiency, reactor mass, shield mass, and heat rejection mass. An overall system design has been developed to model the advanced incore thermionic energy conversion based nuclear reactor systems for space applications in this power range.

Lee, H.H.; Lewis, B.R.; Klein, A.C. (Department of Nuclear Engineering, Oregon State University, Radiation Center, C116, Corvallis, Oregon 97331-5902 (United States)); Pawlowski, R.A. (Battelle Pacific Northwest Laboratories, Richland, Washington 99352 (United States))

1993-01-15T23:59:59.000Z

171

Heat pipe cooled heat rejection subsystem modelling for nuclear electric propulsion. Final report  

SciTech Connect (OSTI)

NASA LeRC is currently developing a FORTRAN based computer model of a complete nuclear electric propulsion (NEP) vehicle that can be used for piloted and cargo missions to the Moon or Mars. Proposed designs feature either a Brayton or a K-Rankine power conversion cycle to drive a turbine coupled with rotary alternators. Both ion and magnetoplasmodynamic (MPD) thrusters will be considered in the model. In support of the NEP model, Rocketdyne is developing power conversion, heat rejection, and power management and distribution (PMAD) subroutines. The subroutines will be incorporated into the NEP vehicle model which will be written by NASA LeRC. The purpose is to document the heat pipe cooled heat rejection subsystem model and its supporting subroutines. The heat pipe cooled heat rejection subsystem model is designed to provide estimate of the mass and performance of the equipment used to reject heat from Brayton and Rankine cycle power conversion systems. The subroutine models the ductwork and heat pipe cooled manifold for a gas cooled Brayton; the heat sink heat exchanger, liquid loop piping, expansion compensator, pump and manifold for a liquid loop cooled Brayton; and a shear flow condenser for a K-Rankine system. In each case, the final heat rejection is made by way of a heat pipe radiator. The radiator is sized to reject the amount of heat necessary.

Moriarty, M.P.

1993-11-01T23:59:59.000Z

172

Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).  

SciTech Connect (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste 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. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

Schultz, Peter Andrew

2011-12-01T23:59:59.000Z

173

Nano-Continuum Modeling of a Nuclear Glass Specimen Altered for 25 Years  

E-Print Network [OSTI]

Insight into silicate-glass corrosion mechanisms. NatureSantarini (2008). SON68 nuclear glass dissolution kinetics:B. (2006). Nuclear waste glasses – How durable? Elements, 2,

Steefel, Carl

2014-01-01T23:59:59.000Z

174

METHANE de-NOX for Utility PC Boilers  

SciTech Connect (OSTI)

Preparations for conducting large-scale combustion tests with caking bituminous coal continued during the start of this quarter. Major project accomplishments related to bituminous coal testing included: a CFD preheat model and evaluation, an update of the process flow diagram and a detailed preheat burner mechanical design (suitable for construction) for firing bituminous coal. Installation and testing of the 85 MMBtu/h bituminous coal preheating system was planned to take place before the end of December. Based on the inability to conduct testing in Riley's Commercial Burner Test Facility (CBTF) during freezing weather, a schedule review indicated required site work for testing bituminous coal at the CBTF could not be completed before freezing weather set in at the site. Further bituminous preheat modification work was put on hold and efforts turned to securing the test facility over the winter season. Bituminous coal tests are therefore delayed; April-May 2005 is earliest estimate of when testing can resume. A request for a time extension was submitted to DOE to extend the project through September 2005 to allow time to secure additional funding and complete the bituminous coal testing. Removal of the PRB PC Preheater from the CBTF burner deck was completed. Decommissioning of the CBTF for the winter was also completed.

Bruce Bryan; Joseph Rabovitser; Serguei Nester; Stan Wohadlo

2004-12-31T23:59:59.000Z

175

Use of PC-SAFT for Global Phase Diagrams in Binary Mixtures Relevant to Natural Gases. 2. n-Alkane + Other Hydrocarbons  

Science Journals Connector (OSTI)

Use of PC-SAFT for Global Phase Diagrams in Binary Mixtures Relevant to Natural Gases. ... In this work, we extend the previously reported study of global phase diagrams in binary mixtures relevant for the description of natural gases using the perturbed-chain statistical associating fluid theory (PC-SAFT) model to systems containing n-alkanes + other nonlinear hydrocarbons. ... The PC-SAFT model usually describes properly the previously reported n-alkane + n-alkane binary mixtures, including their varied and complex phase behavior. ...

Santiago Aparicio-Martínez; Kenneth R. Hall

2006-12-06T23:59:59.000Z

176

An evaluation of commercial IBM PC software for the analysis of low-level environmental gamma-ray spectra  

SciTech Connect (OSTI)

A comparative evaluation of seven commercial gamma-ray analysis software packages, written for the IBM PC, was performed. Four software packages were supplied by US nuclear instrument manufacturers. A fifth package was supplied by a French nuclear instrument manufacturer. Two additional packages were supplied by software companies in the United States and Finland. For this evaluation emphasis was given to accuracy, peak detection, noise and phantom peak rejection for low level environmental sample analysis. System requirements, nuclide identification, ease of operation and other optional utilities were also considered. Of the seven software packages evaluated, two contained the most desirable features required for environmental applications. 9 tabs.

Sanderson, C.G. (International Atomic Energy Agency (Monaco))

1988-01-01T23:59:59.000Z

177

Nuclear Data Program - Nuclear Engineering Division (Argonne)  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Data Program Data Program Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program We contribute to the development of comprehensive nuclear reactions and nuclear structure databases, including nuclear data measurement, analysis, modeling and evaluation methodologies, that are implemented in basic science research and advanced nuclear technologies. Bookmark and Share Recent Events Nuclear Structure 2012 Conference Argonne National Laboratory hosted the

178

Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels  

SciTech Connect (OSTI)

Advanced fast reactor systems being developed under the DOE's Advanced Fuel Cycle Initiative are designed to destroy TRU isotopes generated in existing and future nuclear energy systems. Over the past 40 years, multiple experiments and demonstrations have been completed using U-Zr, U-Pu-Zr, U-Mo and other metal alloys. As a result, multiple empirical and semi-empirical relationships have been established to develop empirical performance modeling codes. many mechamistic questions about fission as mobility, bubble coalescience, and gas release have been answered through industrial experience, reearch, and empirical understanding. The advent of modern computational materials science, however, opens new doors of development such that physics-based multi-scale models may be developed to enable a new generation of predictive fuel performance codes that are not limited by empiricism.

McDeavitt, Sean; Shao, Lin; Tsvetkov, Pavel; Wirth, Brian; Kennedy, Rory

2014-04-07T23:59:59.000Z

179

Recommendations for damping and treatment of modeling uncertainty in seismic analysis of CANDU nuclear power plant  

SciTech Connect (OSTI)

The seismic analysis of the CANDU nuclear power plant is governed by Canadian Standard series N289. However, the dynamic analysis of some equipment and system such as the CANDU reactor and fueling machine must treat unique components not directly covered by the broad recommendations of these standards. This paper looks at the damping values and treatment of modeling uncertainty recommended by CSA N289.3, the current state of knowledge and expert opinion as reflected in several current standards, testing results, and the unique aspects of the CANDU system. Damping values are recommended for the component parts of the CANDU reactor and fueling machine system: reactor building, calandria vault, calandria, fuel channel, pressure tube, fueling machine and support structure. Recommendations for treatment of modeling and other uncertainties are also presented.

Usmani, S.A. [Atomic Energy of Canada, Ltd., Mississauga, Ontario (Canada); Baughman, P.D. [EQE International, Stratham, NH (United States)

1996-12-01T23:59:59.000Z

180

FATE Unified Modeling Method for Spent Nuclear Fuel and Sludge Processing, Shipping and Storage - 13405  

SciTech Connect (OSTI)

A unified modeling method applicable to the processing, shipping, and storage of spent nuclear fuel and sludge has been incrementally developed, validated, and applied over a period of about 15 years at the US DOE Hanford site. The software, FATE{sup TM}, provides a consistent framework for a wide dynamic range of common DOE and commercial fuel and waste applications. It has been used during the design phase, for safety and licensing calculations, and offers a graded approach to complex modeling problems encountered at DOE facilities and abroad (e.g., Sellafield). FATE has also been used for commercial power plant evaluations including reactor building fire modeling for fire PRA, evaluation of hydrogen release, transport, and flammability for post-Fukushima vulnerability assessment, and drying of commercial oxide fuel. FATE comprises an integrated set of models for fluid flow, aerosol and contamination release, transport, and deposition, thermal response including chemical reactions, and evaluation of fire and explosion hazards. It is one of few software tools that combine both source term and thermal-hydraulic capability. Practical examples are described below, with consideration of appropriate model complexity and validation. (authors)

Plys, Martin; Burelbach, James; Lee, Sung Jin; Apthorpe, Robert [Fauske and Associates, LLC, 16W070 83rd St., Burr Ridge, IL, 60527 (United States)] [Fauske and Associates, LLC, 16W070 83rd St., Burr Ridge, IL, 60527 (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Compressor and Turbine Models of Brayton Units for Space Nuclear Power Systems  

SciTech Connect (OSTI)

Closed Brayton Cycles with centrifugal flow, single-shaft turbo-machines are being considered, with gas cooled nuclear reactors, to provide 10's to 100's of electrical power to support future space exploration missions and Lunar and Mars outposts. Such power system analysis is typically based on the cycle thermodynamics, for given operating pressures and temperatures and assumed polytropic efficiencies of the compressor and turbine of the Brayton energy conversion units. Thus the analysis results not suitable for modeling operation transients such as startup and changes in the electric load. To simulate these transients, accurate models of the turbine and compressor in the Brayton rotating unit, which calculate the changes in the compressor and turbine efficiencies with system operation are needed. This paper presents flow models that account for the design and dimensions of the compressor impeller and diffuser, and the turbine stator and rotor blades. These models calculate the various enthalpy losses and the polytropic efficiencies along with the pressure ratios of the turbine and compressor. The predictions of these models compare well with reported performance data of actual hardware. In addition, the results of a parametric analysis to map the operations of the compressor and turbine, as functions of the rotating shaft speed and inlet Mach number of the gas working fluid, are presented and discussed. The analysis used a binary mixture of He-Xe with a molecular weight of 40 g/mole as the working fluid.

Gallo, Bruno M.; El-Genk, Mohamed S.; Tournier, Jean-Michel [Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM, 87131 (United States); Chemical and Nuclear Engineering Department, University of New Mexico, Albuquerque, NM, 87131 (United States)

2007-01-30T23:59:59.000Z

182

Soft-Sphere Model for Nuclear Quadrupole Resonance: Rare-Earth Trichlorides under Hydrostatic Pressure  

Science Journals Connector (OSTI)

Nuclear quadrupole resonance of Cl35 in five hexagonal rare-earth trichlorides under hydro-static pressure up to 5×103 kg/cm2 showed a decrease in frequency ? with increase in pressure. The normalized pressure coefficients ?0-1 (???P)T varied smoothly between the extremes (-5.586 ± 0.020) × (10-6 cm2/kg) and (-3.855 ± 0.016) × (10-6 cm2/kg) for CeCl3 and GdCl3, respectively. The negative sign suggested a model with a significant overlap contribution to the electric field gradient and a soft-sphere model was developed in analogy to the Born-Mayer model of inter-ionic repulsive forces. This model proved adequate to explain the systematic variations in ?Q with compound and was consistent with the pressure dependence of ?. The use of pressure data as a critical test for the model must await reliable compressibility data for the compounds. Pressure data for monoclinic ErCl3 and YbCl3 are also presented.

David H. Current; C. L. Foiles; Edward H. Carlson

1972-08-01T23:59:59.000Z

183

Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant  

SciTech Connect (OSTI)

The Containment Technology Test Facility (CTTF) and the Surtsey Test Facility at Sandia National Laboratories are used to perform scaled experiments that simulate High Pressure Melt Ejection accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effects of direct containment heating (DCH) phenomena on the containment load. High-temperature, chemically reactive melt (thermite) is ejected by high-pressure steam into a scale model of a reactor cavity. Debris is entrained by the steam blowdown into a containment model where specific phenomena, such as the effect of subcompartment structures, prototypic air/steam/hydrogen atmospheres, and hydrogen generation and combustion, can be studied. Four Integral Effects Tests (IETs) have been performed with scale models of the Surry NPP to investigate DCH phenomena. The 1/61{sup th} scale Integral Effects Tests (IET-9, IET-10, and IET-11) were conducted in CTRF, which is a 1/6{sup th} scale model of the Surry reactor containment building (RCB). The 1/10{sup th} scale IET test (IET-12) was performed in the Surtsey vessel, which had been configured as a 1/10{sup th} scale Surry RCB. Scale models were constructed in each of the facilities of the Surry structures, including the reactor pressure vessel, reactor support skirt, control rod drive missile shield, biological shield wall, cavity, instrument tunnel, residual heat removal platform and heat exchangers, seal table room and seal table, operating deck, and crane wall. This report describes these experiments and gives the results.

Blanchat, T.K.; Allen, M.D.; Pilch, M.M. [Sandia National Labs., Albuquerque, NM (United States); Nichols, R.T. [Ktech Corp., Albuquerque, NM (United States)

1994-06-01T23:59:59.000Z

184

Relation of PC index to the geomagnetic storm Dst variation  

Science Journals Connector (OSTI)

Relationships between the polar cap magnetic activity index PC and the magnetic storm Dst index have been studied for the magnetic storms with duration more 12 h and peak value Dst2 mV/m. In particular, the “anomalous” magnetic storm on January 21–22, 2005 occurring under conditions of northward IMF BZ (Du et al., 2008) is usual phenomena fitted well with the threshold restriction owing to the large IMF By component input. The maximal storm depression (the peak value of Dst) is linearly related to the quantities Em and PC, averaged for the time interval from the storm beginning to the storm maximum. The correlation between Dst and PC is more steady and larger than correlation between Dst and Em, the latter being dependent on Em value (effect of “Dst saturation”). The moment of the firm descent of the Em and PC quantities below the threshold level ?2 mV/m is indicative of the depression damping and transition to the recovery phase. The results are consistent with the similar peculiarities revealed for substorms development (Troshichev and Janzhura, 2009) and support the conclusion that the PC index is a reliable proxy characterizing the solar wind energy having been entered into the magnetosphere.

O. Troshichev; D. Sormakov; A. Janzhura

2011-01-01T23:59:59.000Z

185

Use of CAP88 PC to infer differences in the chemical form of I-129 emitted from a fuel reprocessing facility  

SciTech Connect (OSTI)

Emissions of 129I from nuclear fuel separations conducted at the Hanford Site in Washington State have been occurring since the 1940’s. Fuel separation on the Hanford Site stopped in 1988, but emissions of 129I have continued as venting of the building occurred. In this study, atmospheric measurements of 129I concentrations were coupled with an EPA approved plume dispersion model (CAP-88PC) to evaluate the effectiveness of the dispersion model for estimating ambient concentrations at the Hanford Site. This evaluation led to the hypothesis of different chemical forms of iodine being emitted over the years; this hypothesis was developed as an explanation for the model agreeing with measurements over some time periods, but not over all time periods. The model was then run with modified emissions to simulate the short atmospheric half-life of the suspected reactive chemical form of iodine being emitted. This modification resulted in good agreement between the modeled and measured concentrations over the entire 20 year study period, and provided evidence that the hypothesis of a reactive form of iodine being emitted was correct.

Fritz, Brad G.; Phillips, Nathan RJ

2013-06-17T23:59:59.000Z

186

Modeling of UF{sub 6} enrichment with gas centrifuges for nuclear safeguards activities  

SciTech Connect (OSTI)

The physical modeling of uranium isotopes ({sup 235}U, {sup 238}U) separation process by centrifugation of is a key aspect for predicting the nuclear fuel enrichment plant performances under surveillance by the Nuclear Safeguards Authorities. In this paper are illustrated some aspects of the modeling of fast centrifuges for UF{sub 6} gas enrichment and of a typical cascade enrichment plant with the Theoretical Centrifuge and Cascade Simulator (TCCS). The background theory for reproducing the flow field characteristics of a centrifuge is derived from the work of Cohen where the separation parameters are calculated using the solution of a differential enrichment equation. In our case we chose to solve the hydrodynamic equations for the motion of a compressible fluid in a centrifugal field using the Berman - Olander vertical velocity radial distribution and the solution was obtained using the Matlab software tool. The importance of a correct estimation of the centrifuge separation parameters at different flow regimes, lies in the possibility to estimate in a reliable way the U enrichment plant performances, once the separation external parameters are set (feed flow rate and feed, product and tails assays). Using the separation parameters of a single centrifuge allow to determine the performances of an entire cascade and, for this purpose; the software Simulink was used. The outputs of the calculation are the concentrations (assays) and the flow rates of the enriched (product) and depleted (tails) gas mixture. These models represent a valid additional tool, in order to verify the compliance of the U enrichment plant operator declarations with the 'on site' inspectors' measurements.

Mercurio, G.; Peerani, P.; Richir, P.; Janssens, W.; Eklund, G. [European Commission, Joint Research Centre, Institute for Transuranium Elements Via Fermi, 2749-TP181,20127 Ispra (Italy)

2012-09-26T23:59:59.000Z

187

Asymmetric nuclear matter and neutron-skin in extended relativistic mean field model  

E-Print Network [OSTI]

The density dependence of the symmetry energy, instrumental in understanding the behaviour of the asymmetric nuclear matter, is investigated within the extended relativistic mean field (ERMF) model which includes the contributions from the self and mixed interaction terms for the scalar-isoscalar ($\\sigma$), vector-isoscalar ($\\omega$) and vector-isovector ($\\rho$) mesons upto the quartic order. Each of the 26 different parameterizations of the ERMF model employed are compatible with the bulk properties of the finite nuclei. The behaviour of the symmetry energy for several parameter sets are found to be consistent with the empirical constraints on them as extracted from the analyses of the isospin diffusion data. The neutron-skin thickness in the $^{208}$Pb nucleus for these parameter sets of the ERMF model lie in the range of $\\sim 0.20 - 0.24$ fm which is in harmony with the ones predicted by the Skyrme Hartree-Fock model. We also investigate the role of various mixed interaction terms which are crucial for the density dependence of the symmetry energy.

B. K. Agrawal

2010-03-17T23:59:59.000Z

188

METHANE de-NOX FOR UTILITY PC BOILERS  

SciTech Connect (OSTI)

During the current quarter, pilot scale testing was continued with the modified combustor and modified channel burner using the new PRB coal delivered in late December. Testing included benchmark testing to determine whether the system performance was comparable to that with the previous batch of PRB coal, baseline testing to characterize performance of the PC Burner without coal preheating, and parametric testing to evaluate the effect of various preheat combustor and PC burner operating variables, including reduced gas usage in the preheat combustor. A second version of the PC burner in which the secondary air channels were closed and replaced with six air nozzles was then tested with PRB coal. Plans were developed with RPI for the next phase of testing at the 100 million Btu/h scale using RPI's Coal Burner Test Facility (CBTF). A cost estimate for preparation of the CBTF and preheat burner system design, installation and testing was then prepared by RPI.

Joseph Rabovitser; Bruce Bryan; Serguei Nester; Stan Wohadlo

2003-04-01T23:59:59.000Z

189

Model evaluation of geochemically induced swelling/shrinkage in argillaceous formations for nuclear waste disposal  

Science Journals Connector (OSTI)

Abstract Argillaceous formations are being considered as host rocks for geologic disposal of nuclear waste in a number of countries. One advantage of emplacing nuclear waste in such formations is the potential self-sealing capability of clay due to swelling, which is of particular importance for the sealing and healing of disturbed rock zones (DRZ). It is therefore necessary to understand and be able to predict the changes in swelling properties within clay rock near the waste-emplacement tunnel. In this paper, considering that the clay rock formation is mostly under saturated conditions and the swelling property changes are mostly due to geochemical changes, we propose a modeling method that links a THC simulator with a swelling module that is based on diffuse double layer theory. Simulations were conducted to evaluate the geochemically induced changes in the swelling properties of the clay rock. Our findings are as follows: (1) geochemically induced swelling/shrinkage occurs exclusively in the EBS–clay formation interface, within a few meters from the waste-emplacement tunnels; (2) swelling/shrinkage-induced porosity changes are generally much smaller than those caused by mineral precipitation/dissolution processes; (3) geochemically induced swelling/shrinkage of the host clay rock is affected by variations in the pore water chemistry, exchangeable cations, and smectite abundance. Neglecting any of these three factors might lead to a miscalculation of the geochemically induced swelling pressure.

Liange Zheng; Jonny Rutqvist; Hui-Hai Liu; Jens T. Birkholzer; Eric Sonnenthal

2014-01-01T23:59:59.000Z

190

Aromatic hydrocarbon receptor inhibits lysophosphatidic acid-induced vascular endothelial growth factor-A expression in PC-3 prostate cancer cells  

SciTech Connect (OSTI)

Highlights: •LPA-induced VEGF-A expression was regulated by HIF-1? and ARNT. •PI3K mediated LPA-induced VEGF-A expression. •AHR signaling inhibited LPA-induced VEGF-A expression in PC-3 cells. -- Abstract: Lysophosphatidic acid (LPA) is a lipid growth factor with multiple biological functions and has been shown to stimulate cancer cell secretion of vascular endothelial growth factor-A (VEGF-A) and trigger angiogenesis. Hypoxia-inducible factor-1 (HIF-1), a heterodimer consisting of HIF-1? and HIF-1? (also known as aromatic hydrocarbon receptor nuclear translocator (ARNT)) subunits, is an important regulator of angiogenesis in prostate cancer (PC) through the enhancement of VEGF-A expression. In this study, we first confirmed the ability of LPA to induce VEGF-A expression in PC-3 cells and then validated that LPA-induced VEGF-A expression was regulated by HIF-1? and ARNT through phosphatidylinositol 3-kinase activation. Aromatic hydrocarbon receptor (AHR), a receptor for dioxin-like compounds, functions as a transcription factor through dimerization with ARNT and was found to inhibit prostate carcinogenesis and vanadate-induced VEGF-A production. Since ARNT is a common dimerization partner of AHR and HIF-1?, we hypothesized that AHR might suppress LPA-induced VEGF-A expression in PC-3 cells by competing with HIF-1? for ARNT. Here we demonstrated that overexpression and ligand activation of AHR inhibited HIF-1-mediated VEGF-A induction by LPA treatment of PC-3 cells. In conclusion, our results suggested that AHR activation may inhibit LPA-induced VEGF-A expression in PC-3 cells by attenuating HIF-1? signaling, and subsequently, suppressing angiogenesis and metastasis of PC. These results suggested that AHR presents a potential therapeutic target for the prevention of PC metastasis.

Wu, Pei-Yi; Lin, Yueh-Chien; Lan, Shun-Yan [Institute of Zoology, National Taiwan University, Taipei, Taiwan (China)] [Institute of Zoology, National Taiwan University, Taipei, Taiwan (China); Huang, Yuan-Li [Department of Biotechnology, Asia University, Taichung, Taiwan (China)] [Department of Biotechnology, Asia University, Taichung, Taiwan (China); Lee, Hsinyu, E-mail: hsinyu@ntu.edu.tw [Institute of Zoology, National Taiwan University, Taipei, Taiwan (China) [Institute of Zoology, National Taiwan University, Taipei, Taiwan (China); Department of Life Science, National Taiwan University, Taipei, Taiwan (China)

2013-08-02T23:59:59.000Z

191

began at the PC4 facility, which is located  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

began at the PC4 facility, which is located at the Alabama Power Gaston began at the PC4 facility, which is located at the Alabama Power Gaston Power Plant Unit 5 (an 880-megawatt [MW] supercritical pulverized coal unit), when researchers used a monoethanolamine (MEA) solvent to capture CO 2 from a slipstream of flue gas from the plant. To date, the MEA solvent has exceeded the expected 90 percent CO 2 capture; the unit is now in steady operation, capturing approximately 10 tons

192

METHANE DE-NOX FOR UTILITY PC BOILERS  

SciTech Connect (OSTI)

The project seeks to develop and validate a new pulverized coal combustion system to reduce utility PC boiler NO{sub x} emissions to 0.15 lb/million Btu or less without post-combustion flue gas cleaning. Work during the quarter included completion of the equipment fabrication and installation efforts for the 3-million Btu/h pilot system at BBP's Pilot-Scale Combustion Facility (PSCF) in Worcester, MA. Selection and procurement of the first two test coals and preliminary selection of the final two test coals were completed. Shakedown and commissioning activities were finished and PC Preheat pilot scale tests commenced with PRB coal.

Joseph Rabovitser; Bruce Bryan; Serguei Nester; Stan Wohadlo

2002-01-31T23:59:59.000Z

193

METHANE de-NOX for Utility PC Boilers  

SciTech Connect (OSTI)

Large-scale combustion tests with caking bituminous coal has stopped. This stoppage has come about due to limitations in current funding available to continue large scale research and development activities at Riley's Commercial Burner Test Facility (CBTF) of the PC Preheat technology. The CBTF was secured and decommissioned in the previous quarter; work this quarter has focused on disposition of PC Preheat experimental equipment at the CBTF as well as methods for disposal of about 100 tons of residual PRB test coal in storage. GTI was granted a no-cost time extension through September 2005; a final report is due in December 2005.

Bruce Bryan; Joseph Rabovitser; Serguei Nester; Stan Wohadlo

2005-06-30T23:59:59.000Z

194

Radiation Damage in Nuclear Fuel for Advanced Burner Reactors: Modeling and Experimental Validation  

SciTech Connect (OSTI)

The consortium has completed its existence and we are here highlighting work and accomplishments. As outlined in the proposal, the objective of the work was to advance the theoretical understanding of advanced nuclear fuel materials (oxides) toward a comprehensive modeling strategy that incorporates the different relevant scales involved in radiation damage in oxide fuels. Approaching this we set out to investigate and develop a set of directions: 1) Fission fragment and ion trajectory studies through advanced molecular dynamics methods that allow for statistical multi-scale simulations. This work also includes an investigation of appropriate interatomic force fields useful for the energetic multi-scale phenomena of high energy collisions; 2) Studies of defect and gas bubble formation through electronic structure and Monte Carlo simulations; and 3) an experimental component for the characterization of materials such that comparisons can be obtained between theory and experiment.

Niels Gronbech Jensen; Mark Asta; Nigel Browning'Vidvuds Ozolins; Axel van de Walle; Christopher Wolverton

2011-12-29T23:59:59.000Z

195

Deep sub-threshold $?$ and $?$ production in nuclear collisions with the UrQMD transport model  

E-Print Network [OSTI]

We present results on deep sub threshold hyperon production in nuclear collisions, with the UrQMD transport model. Introducing anti-kaon+baryon and hyperon+hyperon strangeness exchange reactions we obtain a good description of experimental data on single strange hadron production in Ar+KCl reactions at $E_{lab}=1.76$ A GeV. We find that the hyperon strangeness exchange is the dominant process contributing to the $\\Xi^-$ yield, however remains short of explaining the $\\Xi^-/\\Lambda$ ratio measured with the HADES experiment. We also discuss possible reasons for the discrepancy with previous studies and the experimental results, finding that many details of the transport simulation may have significant effects on the final $\\Xi^-$ yield.

G. Graef; J. Steinheimer; Feng Li; Marcus Bleicher

2014-09-28T23:59:59.000Z

196

Abstract LB-521: Expression profile of nuclear receptor superfamily in a lung cancer pathogenesis model  

Science Journals Connector (OSTI)

...Abstract 2296: Identification of novel nuclear receptor targets in estrogen receptor...subtype. Aims and Methods: To identify nuclear receptor (NR) targets, we did microarray...using previously published breast cancer datasets. Results and Conclusion: The 41 NRs...

Yangsik Jeong; Jihye Kim; Mitsuo Sato; Woochang Lee; Woochang Lee; Jonathan M. Kurie; John D. Minna; and David J. Mangelsdorf

2012-04-15T23:59:59.000Z

197

Nuclear interactions in a heterokaryon: insight from the model Neurospora tetrasperma  

Science Journals Connector (OSTI)

...reserved. July 7, 2014 research-article Research articles 1001 70 197 200 Nuclear interactions in a heterokaryon...29 Dodge, BO . 1927 Nuclear phenomena associated with...Perkins. 1994 Diverse programs of ascus development in...

2014-01-01T23:59:59.000Z

198

PC3Q510NIP0F1/4 PC3Q510NIP0F1/4  

E-Print Network [OSTI]

+5V+5V +5V +5V +5V +5V +5V +5V +5V +5V LM3391/4 LM3391/4 LM3391/4 LM3391/4 LM3391/4 LM3391/4 LM3391/4 red led +5V+5V red led red led +5V+5V+5V red led +5V+5V red led +2V LM3391/4 LM3391/4 LM3391/4 LM3391/4 LM3391/4 LM3391/4 LM3391/4 +5V LM3391/4 red led red led red led PC3Q510NIP0F1/4 PC3Q510NIP0F1/4 PC3Q

Evans, Hal

199

Comparative study of Dutch and German emergency-management models for near border nuclear accidents  

Science Journals Connector (OSTI)

......Dutch-German commission for nuclear facilities in the border region...radiological situation following a nuclear accident in the border region...compared or validated using datasets of experimental field campaigns...institutes are engaged in the nuclear-emergency response organisations......

Y. S. Kok; H. Eleveld; H. Schnadt; F. Gering; J. Gregor; H. Böttger; C. Salfeld; C. J. W. Twenhöfel; H. A. J. M. Reinen

2005-05-01T23:59:59.000Z

200

Nuclear Collective Rotation in the SU3 Model. II: Quantal Rotation for a Triaxial Configuration  

Science Journals Connector (OSTI)

......The collective rotation of a nuclear system with the S U 3 Hamiltonian...described by the quantal dynamical nuclear field theory. An angular frequency...compared with the exact S U 3 energy and the rotor's angular momentum...4 (1990) pp. 766-778 Nuclear Collective Rotation in the......

Shin-ichi Kinouchi; Tetsuo Kammuri; Teruo Kishimoto

1990-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Nuclear Collective Rotation in the SU3 Model. III: Quantal Rotation for an Axially Symmetric Configuration  

Science Journals Connector (OSTI)

......Quantal form of the dynamical nuclear field theory is used for the...the collective rotation of a nuclear system with the S U 3 Hamiltonian...coincides with the exact S U 3 energy; the E2-matrix elements...Bohr A. , Mottelson B. R. Nuclear Structure (1975) New York......

Shin-ichi Kinouchi; Tetsuo Kammuri; Teruo Kishimoto

1990-04-01T23:59:59.000Z

202

PHYSICAL REVIEW C 87, 064608 (2013) Nuclear meson transparency in a relativistic Glauber model  

E-Print Network [OSTI]

interactions (FSI) between the tagged hadron and the nuclear environment vanish. The SSC can also be produced be of the order of the nuclear radius (lf RA). Observation of the onset of CT at a certain energy scale can teach traditional nuclear-physics calculations. The measurement of the onset and magnitude of the CT effect allows

Gent, Universiteit

203

Nuclear interactions in a heterokaryon: insight from the model Neurospora tetrasperma  

Science Journals Connector (OSTI)

...research-article Research articles 1001 70 197 200 Nuclear interactions in a heterokaryon: insight...heterokaryons to demonstrate that the nuclear ratio is consistently biased for mat A-nuclei...we investigated the association between nuclear ratio and expression of alleles of mat-linked...

2014-01-01T23:59:59.000Z

204

Nuclear Physics B (Proc. Suppl.) 77 (1999) 64--72 Standard Solar Models  

E-Print Network [OSTI]

reactions. Thirty­nine experts in low energy nuclear ex­ periments and theory, representing many di#er­ ent In this section, I will first summarize the new and relevant results on nuclear fusion reactions and on the screening of nuclear reactions and then summarize the situation with respect to neu­ trino cross sections

Bahcall, John

205

Modeling nuclear fusion in dense plasmas using a cryogenic non-neutral plasmaa...  

E-Print Network [OSTI]

the nuclear reaction rate in a dense neutral plasma and the energy equipartition rate in a strongly magnetized and at low temperatures, cyclotron energy, like nuclear energy, is released only through rare close as for nuclear reactions. Rate enhancements of up to 1010 are measured in simulations of equipartition

California at San Diego, University of

206

Towards New Widgets to Reduce PC Power Consumption  

E-Print Network [OSTI]

1 Towards New Widgets to Reduce PC Power Consumption Abstract We present a study which describes document) were compared for power consumption across both a desktop and a laptop computer and across two in the power consumption of the interac- tion technique is the number of screen updates in- volved. Keywords

Williamson, John

207

Hydralazine Rescues PC12 Cells From Acrolein-Mediated Death  

E-Print Network [OSTI]

Hydralazine Rescues PC12 Cells From Acrolein-Mediated Death Peishan Liu-Snyder,1 Richard Ben, College of Engineering, Purdue University, West Lafayette, Indiana Acrolein, a major lipid peroxidation half-life, acrolein is a potent endogenous toxin capable of killing healthy cells during the secondary

Shi, Riyi

208

Nuclear matrix elements for 0??{sup ?}?{sup ?} decays: Comparative analysis of the QRPA, shell model and IBM predictions  

SciTech Connect (OSTI)

In this work we report on general properties of the nuclear matrix elements involved in the neutrinoless double ?{sup ?} decays (0??{sup ?}?{sup ?} decays) of several nuclei. A summary of the values of the NMEs calculated along the years by the Jyväskylä-La Plata collaboration is presented. These NMEs, calculated in the framework of the quasiparticle random phase approximation (QRPA), are compared with those of the other available calculations, like the Shell Model (ISM) and the interacting boson model (IBA-2)

Civitarese, Osvaldo [Department of Physics, University of La Plata, c.c. 67 1900, La Plata Argentina (Argentina); Suhonen, Jouni [Department of Physics, University of Jyväskylä, PO Box 35, FIN-40014 (Finland)

2013-12-30T23:59:59.000Z

209

GAUAGHER AND GALLAGHER ATTORmYS AT LAW, P.C. Ot4ECONWRJTIONPUtA  

Office of Legacy Management (LM)

j ; ij 7 iir I,::? ir s1: 141 TL-2 j ; ij 7 iir I,::? ir s1: 141 TL-2 tj .> Ii el)sTorl GAUAGHER AND GALLAGHER ATTORmYS AT LAW, P.C. Ot4ECONWRJTIONPUtA BOSTON. MASS. 02129 March 7, 1990 (617) 241.8aoo ?AX. (617) 141*?6W VIA TELEFAX Park Owen USDOE: Nuclear Facility De commissioning and site Remedial hotion oak Ridge National Laboratory P. 0. Box 2008 Building 2001-6050 Oak Ridge, TN 37831-6050 Re: Wesaahouse, Bloomfield, NJ Our File No.: 15094 (09) near M r. Owen: Pursuant to our telephone conversation of March 7, 1990, P1ca.w fincl the following documents enclo6e.A fnr yot~r perusfil: 1. Report on Radiological Status Building 7 Westinghouse Electric Corp. (Source NJDEP-DHWM-ECRA); 2. Cover Letter and Attachment (NRC to Westinghouse): Report on Radiological status on Westinghouse Building

210

National Nuclear Data Center  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Internal Radiation Dose Evaluated Nuclear (reaction) Data File Experimental nuclear reaction data Sigma Retrieval & Plotting Nuclear structure & decay Data Nuclear Science References Experimental Unevaluated Nuclear Data List Evaluated Nuclear Structure Data File NNDC databases Ground and isomeric states properties Nuclear structure & decay data journal Nuclear reaction model code Tools and Publications US Nuclear Data Program Cross Section Evaluation Working Group Nuclear data networks Basic properties of atomic nuclei Parameters & thermal values Basic properties of atomic nuclei Internal Radiation Dose Evaluated Nuclear (reaction) Data File Experimental nuclear reaction data Sigma Retrieval & Plotting Nuclear structure & decay Data Nuclear Science References Experimental Unevaluated Nuclear Data List Evaluated Nuclear Structure Data File NNDC databases Ground and isomeric states properties Nuclear structure & decay data journal Nuclear reaction model code Tools and Publications US Nuclear Data Program Cross Section Evaluation Working Group Nuclear data networks Basic properties of atomic nuclei Parameters & thermal values Basic properties of atomic nuclei Homepage BNL Home Site Index - Go USDNP and CSEWG November 18-22! USNDP CSEWG Agenda Thanks for attending! EXFOR 20,000 Milestone EXFOR Milestone 20,000 experimental works are now in the EXFOR database!

211

METHANE de-NOX for Utility PC Boilers  

SciTech Connect (OSTI)

The overall project objective is the development and validation of an innovative combustion system, based on a novel coal preheating concept prior to combustion, that can reduce NO{sub x} emissions to 0.15 lb/million Btu or less on utility pulverized coal (PC) boilers. This NO{sub x} reduction should be achieved without loss of boiler efficiency or operating stability, and at more than 25% lower levelized cost than state-of-the-art SCR technology. A further objective is to ready technology for full-scale commercial deployment to meet the market demand for NO{sub x} reduction technologies. Over half of the electric power generated in the U.S. is produced by coal combustion, and more than 80% of these units utilize PC combustion technology. Conventional measures for NOx reduction in PC combustion processes rely on combustion and post-combustion modifications. A variety of combustion-based NO{sub x} reduction technologies are in use today, including low-NO{sub x} burners (LNBs), flue gas recirculation (FGR), air staging, and natural gas or other fuel reburning. Selective non-catalytic reduction (SNCR) and selective catalytic reduction (SCR) are post-combustion techniques. NO{sub x} reduction effectiveness from these technologies ranges from 30 to 60% and up to 90-93% for SCR. Typically, older wall-fired PC burner units produce NO{sub x} emissions in the range of 0.8-1.6 lb/million Btu. Low-NO{sub x} burner systems, using combinations of fuel staging within the burner and air staging by introduction of overfire air in the boiler, can reduce NO{sub x} emissions by 50-60%. This approach alone is not sufficient to meet the desired 0.15 lb/million Btu NO{sub x} standard with a range of coals and boiler loads. Furthermore, the heavy reliance on overfire air can lead to increased slagging and corrosion in furnaces, particularly with higher-sulfur coals, when LNBs are operated at sub-stoichiometric conditions to reduce fuel-derived NOx in the flame. Therefore, it is desirable to minimize the need for overfire air by maximizing NO{sub x} reduction in the burner. The proposed combustion concept aims to greatly reduce NO{sub x} emissions by incorporating a novel modification to conventional or low-NO{sub x} PC burners using gas-fired coal preheating to destroy NO{sub x} precursors and prevent NO{sub x} formation. A concentrated PC stream enters the burner, where flue gas from natural gas combustion is used to heat the PC up to about 1500 F prior to coal combustion. Secondary fuel consumption for preheating is estimated to be 3 to 5% of the boiler heat input. This thermal pretreatment releases coal volatiles, including fuel-bound nitrogen compounds into oxygen-deficient atmosphere, which converts the coal-derived nitrogen compounds to molecular N{sub 2} rather than NO. Design, installation, shakedown, and testing on Powder River Basin (PRB) coal at a 3-million Btu/h pilot system at RPI's (Riley Power, Inc.) pilot-scale combustion facility (PSCF) in Worcester, MA demonstrated that the PC PREHEAT process has a significant effect on final O{sub x} formation in the coal burner. Modifications to both the pilot system gas-fired combustor and the PC burner led to NO{sub x} reduction with PRB coal to levels below 0.15 lb/million Btu with CO in the range of 35-112 ppmv without any furnace air staging.

Bruce Bryan; Serguei Nester; Joseph Rabovitser; Stan Wohadlo

2005-09-30T23:59:59.000Z

212

Nuclear Forces and Nuclear Systems  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Forces and Nuclear Systems Forces and Nuclear Systems Our goal is to achieve a description of nuclear systems ranging in size from the deuteron to nuclear matter and neutron stars using a single parameterization of the nuclear forces. Our work includes both the construction of two- and three-nucleon potentials and the development of many-body techniques for computing nuclear properties with these interactions. Detailed quantitative, computationally intense studies are essential parts of this work. In the last decade we have constructed several realistic two- and three-nucleon potential models. The NN potential, Argonne v18, has a dominant charge-independent piece plus additional charge-dependent and charge-symmetry-breaking terms, including a complete electromagnetic interaction. It fits 4301 pp and np elastic scattering data with a chi**2

213

Nuclear Energy  

Science Journals Connector (OSTI)

Nuclear Energy ... A brief summary of the history and key concepts of nuclear energy. ... Nuclear / Radiochemistry ...

Charles D. Mickey

1980-01-01T23:59:59.000Z

214

Nuclear batteries  

Science Journals Connector (OSTI)

Nuclear batteries ... Describes the structure, operation, and application of nuclear batteries. ... Nuclear / Radiochemistry ...

Alfred B. Garrett

1956-01-01T23:59:59.000Z

215

Modeling nuclear fusion in dense plasmas using a cryogenic non-neutral plasma  

SciTech Connect (OSTI)

An analogy between the nuclear reaction rate in a dense neutral plasma and the energy equipartition rate in a strongly magnetized non-neutral plasma is discussed. This analogy allows the first detailed measurements of plasma screening enhancements in the strong screening and pycnonuclear regimes. In strong magnetic fields and at low temperatures, cyclotron energy, like nuclear energy, is released only through rare close collisions between charges. The probability of such collisions is enhanced by plasma screening, just as for nuclear reactions. Rate enhancements of up to 10{sup 10} are measured in simulations of equipartition, and are compared to theories of screened nuclear reactions.

Dubin, Daniel H. E. [Department of Physics, University of California at San Diego, La Jolla, California 92093 (United States)

2008-05-15T23:59:59.000Z

216

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network  

SciTech Connect (OSTI)

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

2010-10-28T23:59:59.000Z

217

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multimodal transportation network  

SciTech Connect (OSTI)

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, and focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

218

Nuclear Quadrupole Moments and Nuclear Shell Structure  

DOE R&D Accomplishments [OSTI]

Describes a simple model, based on nuclear shell considerations, which leads to the proper behavior of known nuclear quadrupole moments, although predictions of the magnitudes of some quadrupole moments are seriously in error.

Townes, C. H.; Foley, H. M.; Low, W.

1950-06-23T23:59:59.000Z

219

TYBO/BENHAM: Model Analysis of Groundwater Flow and Radionuclide Migration from Underground Nuclear Tests in Southwestern Pahute Mesa, Nevada  

SciTech Connect (OSTI)

Recent field studies have led to the discovery of trace quantities of plutonium originating from the BENHAM underground nuclear test in two groundwater observation wells on Pahute Mesa at the Nevada Test Site. These observation wells are located 1.3 km from the BENHAM underground nuclear test and approximately 300 m from the TYBO underground nuclear test. In addition to plutonium, several other conservative (e.g. tritium) and reactive (e.g. cesium) radionuclides were found in both observation wells. The highest radionuclide concentrations were found in a well sampling a welded tuff aquifer more than 500m above the BENHAM emplacement depth. These measurements have prompted additional investigations to ascertain the mechanisms, processes, and conditions affecting subsurface radionuclide transport in Pahute Mesa groundwater. This report describes an integrated modeling approach used to simulate groundwater flow, radionuclide source release, and radionuclide transport near the BENHAM and TYBO underground nuclear tests on Pahute Mesa. The components of the model include a flow model at a scale large enough to encompass many wells for calibration, a source-term model capable of predicting radionuclide releases to aquifers following complex processes associated with nonisothermal flow and glass dissolution, and site-scale transport models that consider migration of solutes and colloids in fractured volcanic rock. Although multiple modeling components contribute to the methodology presented in this report, they are coupled and yield results consistent with laboratory and field observations. Additionally, sensitivity analyses are conducted to provide insight into the relative importance of uncertainty ranges in the transport parameters.

Andrew Wolfsberg; Lee Glascoe; Guoping Lu; Alyssa; Olson; Peter Lichtner; Maureen McGraw; Terry Cherry; ,; Guy Roemer

2002-09-01T23:59:59.000Z

220

Building Energy Software Tools Directory: Tools by Platform - PC  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

PC PC 1 3 A B C D E F G H I J K L M N O P Q R S T U V W Z ¡ Tool Applications Free Recently Updated 1D-HAM heat, air, moisture transport, walls Software has been updated. 3E Plus insulation, insulation thickness Free software. Software has been updated. AAMASKY skylights, daylighting, commercial buildings ABACODE Residential code compliance, IECC Free software. ACOUSALLE acoustics, codes and standards AcousticCalc HVAC acoustics, sound level prediction, noise level Acoustics Program HVAC acoustics, sound level prediction, noise level Software has been updated. Acuity Energy Platform energy efficiency software; customized business recommendation; commercial and industrial energy use comparisons Software has been updated. ADELINE

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

METHANE de-NOX for Utility PC Boilers  

SciTech Connect (OSTI)

Large-scale combustion tests with caking bituminous coal has stopped. This stoppage has come about due to limitations in current funding available to continue large scale research and development activities at Riley Power's Commercial Burner Test Facility (CBTF) of the PC Preheat technology. The CBTF was secured and decommissioned in the previous quarter; work this quarter work completed the securing the proper disposition of all PC Preheat experimental equipment at the PSCF and CBTF and completing negotiations with AES Westover (a power plant in Johnson City, New York) to accept 130 tons of residual PRB test coal in storage. The coal transport to Westover occurred at the end of August. GTI was granted a no-cost time extension through September 2005; immediate efforts are focused on completing a draft final report, which is due in October 31, 2005 and the final report in December.

Joseph Rabovitser; Serguei Nester; Stan Wohadlo

2005-09-30T23:59:59.000Z

222

Conversion from 8800 to 8800PC -- Evaluation and experience  

SciTech Connect (OSTI)

Though a final version of the software is pending the 8800PC operating system host computer is a welcomed change from the old Digital (DEC) host computer. The 8800PC host computer uses the Windows NT operating system and has proven to be very user friendly. Descriptive window messages replace the cryptic coding of the DEC host. Though numerous electrical components were replaced, system calibration remained constant. Calibrated Thermoluminescent (TL) output from a randomly selected 8815 field card was measured before and after the upgrade. The % difference, when comparing calibrated output from an upgraded reader to the non upgraded reader, ranged from 0.2 to 3%. The most disappointing aspect of the upgrade experience was the lag time between hardware installation and software completion.

Miner, A.E.; Lawson, B.J. [Lockheed Martin, Schenectady, NY (United States)

1998-03-20T23:59:59.000Z

223

BPM: A tool to predict boiler performance on a PC  

SciTech Connect (OSTI)

The Department of energy has developed and made available to the public a PC-based software package (BPM 3.0) to help engineers predict the performance of utility boilers in non-standard modes of operation for power generation systems. This package is especially useful for analyzing changes in boiler performance resulting from fuel switching, changes in operating modes (e.g., constant versus variable pressure), and physical changes to the boiler. The report discusses the use of the program.

Lagomarsino, J. [Burns and Roe, Inc., Oradell, NJ (United States); Ramezan, M. [Burns and Roe Services Corp., Pittsburgh, PA (United States); Winslow, J. [USDOE Pittsburgh Energy Technology Center, PA (United States)

1994-06-01T23:59:59.000Z

224

Current Understanding and Remaining Challenges in Modeling Long-Term Degradation of Borosilicate Nuclear Waste Glasses  

SciTech Connect (OSTI)

Chemical durability is not a single material property that can be uniquely measured. Instead it is the response to a host of coupled material and environmental processes whose rates are estimated by a combination of theory, experiment, and modeling. High-level nuclear waste (HLW) glass is perhaps the most studied of any material yet there remain significant technical gaps regarding their chemical durability. The phenomena affecting the long-term performance of HLW glasses in their disposal environment include surface reactions, transport properties to and from the reacting glass surface, and ion exchange between the solid glass and the surrounding solution and alteration products. The rates of these processes are strongly influenced and are coupled through the solution chemistry, which is in turn influenced by the reacting glass and also by reaction with the near-field materials and precipitation of alteration products. Therefore, those processes must be understood sufficiently well to estimate or bound the performance of HLW glass in its disposal environment over geologic time-scales. This article summarizes the current state of understanding of surface reactions, transport properties, and ion exchange along with the near-field materials and alteration products influences on solution chemistry and glass reaction rates. Also summarized are the remaining technical gaps along with recommended approaches to fill those technical gaps.

Vienna, John D. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ryan, Joseph V. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Gin, Stephane [CEA Marcoule, DTCD SECM, Bagnols-sur-Ceze (France); Inagaki, Yaohiro [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoda (Japan)

2013-12-05T23:59:59.000Z

225

Nuclear Forensics  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

nuclear forensics Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear...

226

Photovoltaic characteristics of TCNQ-incorporated CuPc-poly(p-phenylene) composite films  

Science Journals Connector (OSTI)

Composite films (CuPc–PPP–TCNQ) were produced by simultaneous deposition using copper phthalocyanine (CuPc) as a carrier generation material, poly(p-phenylene) (PPP) as a hole transport material, and tetracyan...

Takayuki Iwase; Yutaka Haga

2004-09-01T23:59:59.000Z

227

ALMA FOLLOWS STREAMING OF DENSE GAS DOWN TO 40 pc FROM THE SUPERMASSIVE BLACK HOLE IN NGC 1097  

SciTech Connect (OSTI)

We present a kinematic analysis of the dense molecular gas in the central 200 pc of the nearby galaxy NGC 1097, based on Cycle 0 observations with the Atacama Large Millimeter/submillimeter Array (ALMA). We use the HCN(4-3) line to trace the densest interstellar molecular gas (n{sub H{sub 2}}{approx}10{sup 8} cm{sup -3}), and quantify its kinematics, and estimate an inflow rate for the molecular gas. We find a striking similarity between the ALMA kinematic data and the analytic spiral inflow model that we have previously constructed based on ionized gas velocity fields on larger scales. We are able to follow dense gas streaming down to 40 pc distance from the supermassive black hole in this Seyfert 1 galaxy. In order to fulfill marginal stability, we deduce that the dense gas is confined to a very thin disk, and we derive a dense gas inflow rate of 0.09 M{sub Sun} yr{sup -1} at 40 pc radius. Combined with previous values from the H{alpha} and CO gas, we calculate a combined molecular and ionized gas inflow rate of {approx}0.2 M{sub Sun} yr{sup -1} at 40 pc distance from the central supermassive black hole of NGC 1097.

Fathi, Kambiz; Pinol-Ferrer, Nuria [Stockholm Observatory, Department of Astronomy, Stockholm University, AlbaNova Centre, 106 91 Stockholm (Sweden); Lundgren, Andreas A.; Wiklind, Tommy [Joint ALMA Observatory, Alonso de Cordova 3107, Vitacura, Santiago (Chile); Kohno, Kotaro; Izumi, Takuma [Institute of Astronomy, The University of Tokyo, 2-21-1 Osawa, Mitaka, Tokyo 181-0015 (Japan); Martin, Sergio [ESO, Alonso de Cordova 3107, Vitacura, Santiago (Chile); Espada, Daniel [National Astronomical Observatory of Japan (NAOJ), 2-21-1 Osawa, Mitaka, Tokyo 181-8588 (Japan); Hatziminaoglou, Evanthia [ESO, Karl-Schwarzschild-Str. 2, D-85748 Garching bei Muenchen (Germany); Imanishi, Masatoshi [Subaru Telescope, National Astronomical Observatory of Japan, 650 North A'ohoku Place, Hilo, HI 96720 (United States); Krips, Melanie [Institute for Radio-Astronomy at Millimeter Wavelengths, Domaine University, 300 Rue de la Piscine, F-38406 Saint Martin d'Heres (France); Matsushita, Satoki [Academia Sinica, Institute of Astronomy and Astrophysics, P.O. Box 23-141, Taipei 10617, Taiwan (ROC) (China); Meier, David S. [Department of Physics, New Mexico Institute of Mining and Technology, 801 Leroy Place, Socorro, NM 87801 (United States); Nakai, Naomasa [Division of Physics, Faculty of Pure and Applied Science, University of Tsukuba, Tsukuba, Ibaraki 305-8571 (Japan); Sheth, Kartik [National Radio Astronomy Observatory, 520 Edgemont Road, Charlottesville, VA 22903 (United States); Turner, Jean [Department of Physics and Astronomy, UCLA, Los Angeles, CA 90095-1547 (United States); Van de Ven, Glenn [Max Planck Institute for Astronomy, Koenigstuhl 17, D-69117 Heidelberg (Germany)

2013-06-20T23:59:59.000Z

228

Uncertainties in nuclear transition matrix elements for neutrinoless ?? decay within the projected-Hartree-Fock-Bogoliubov model  

Science Journals Connector (OSTI)

The nuclear transition matrix elements M(0?) for the neutrinoless ?? decay of Zr94,96, Mo98,100, Ru104, Pd110, Te128,130, and Nd150 isotopes in the case of 0+?0+ transition are calculated using the projected-Hartree-Fock-Bogoliubov wave functions, which are eigenvectors of four different parametrizations of a Hamiltonian with pairing plus multipolar effective two-body interaction. Employing two (three) different parametrizations of Jastrow-type short-range correlations, a set of eight (twelve) different nuclear transition matrix elements M(0?) is built for each decay, whose averages in conjunction with their standard deviations provide an estimate of the model’s uncertainties.

P. K. Rath, R. Chandra, K. Chaturvedi, P. K. Raina, and J. G. Hirsch

2010-12-17T23:59:59.000Z

229

Approach to Improve Speed of Sound Calculation within PC-SAFT Framework  

Science Journals Connector (OSTI)

Approach to Improve Speed of Sound Calculation within PC-SAFT Framework ... An extensive comparison of SRK, CPA, and PC-SAFT for the speed of sound in normal alkanes has been performed. ... The results reveal that PC-SAFT captures the curvature of the speed of sound better than cubic EoS, but the accuracy is not satisfactory. ...

Xiaodong Liang; Bjørn Maribo-Mogensen; Kaj Thomsen; Wei Yan; Georgios M. Kontogeorgis

2012-10-18T23:59:59.000Z

230

Advanced Modeling and Evaluation of the Response of Base-Isolated Nuclear Facility Structures to Vertical Earthquake Excitation  

E-Print Network [OSTI]

Structures . iii 3 Nuclear Power Plants 3.1 Nuclear FacilityKashiwazaki-Kariwa Nuclear Power Plant 3.3.1 2004 Ch¯ uetsuKashiwazaki-Kariwa nuclear power plant in response to the

Keldrauk, Eric Scott

2012-01-01T23:59:59.000Z

231

Effects of $?$ hyperons on the nuclear equation of state in a Dirac-Brueckner-Hartree-Fock model  

E-Print Network [OSTI]

We predict the energy per baryon in nuclear matter with non-zero fraction of $\\Lambda$ hyperons. We include Dirac effects on the nucleons as well as the $\\Lambda$ and describe how the latter is implemented. We use the nucleon-hyperon meson-exchange potentials from the Juelich group, the latest as well as an earlier version. The dependence of the results on the many-body framework and on the nucleon-hyperon interaction model is discussed.

Francesca Sammarruca

2009-02-05T23:59:59.000Z

232

Prediction of refrigerant-lubricant viscosity using the general PC-SAFT friction theory  

Science Journals Connector (OSTI)

Abstract In this work, a friction theory (f-theory) viscosity model founded on the perturbed-chain statistical associating fluid theory (PC-SAFT) equation of state (EoS) was used to calculate the viscosity of refrigerant-oil mixtures. The model, which links viscosity to the repulsive and attractive pressure terms of the PC-SAFT EoS, can provide satisfactory viscosity predictions of mixtures of carbon dioxide (R-744) and two synthetic lubricants, namely, a polyolester (POE) ISO VG 68 and an alkylbenzene (AB) ISO VG 32, as well as mixtures of isobutane (R-600a) and two other synthetic lubricants, a POE ISO VG 7 and an AB ISO VG 5. The root-mean square (RMS) deviations related to the viscosity prediction were 0.69% (R-600a/POE ISO 7), 0.99% (R-600a/AB ISO VG 5), 3.16% (R-744/POE ISO VG 68) and 3.18% (R-744/AB ISO VG 32).

Moisés A. Marcelino Neto; Jader R. Barbosa Jr.

2014-01-01T23:59:59.000Z

233

A Explanatory Model of Public Acceptance for Nuclear Power Technology: From Low-Carbon Perspective  

Science Journals Connector (OSTI)

There are not so many literature about nuclear power technology of public acceptance in China, but different scholars have different opinions about the determinants of public acceptance. Xi and Xue studied that w...

Yuan-hua Yang; Li Li; Guo-hua Niu

2013-01-01T23:59:59.000Z

234

Simulation and Optimization Models for Scheduling Multi-step Sequential Procedures in Nuclear Medicine  

E-Print Network [OSTI]

The rise in demand for specialized medical services in the U.S has been recognized as one of the contributors to increased health care costs. Nuclear medicine is a specialized service that uses relatively new technologies and radiopharmaceuticals...

Perez Roman, Eduardo

2011-08-08T23:59:59.000Z

235

Time-Dependent Reliability Analysis of Nuclear Reactor Operators Using Probabilistic Network Models  

Science Journals Connector (OSTI)

Human factors are very important for the reliability of a nuclear power plant. Human behavior has essentially time-dependent nature. The details of thinking and decision making processes are important for deta...

Yoshiaki Oka; Kenji Miyata; Hideki Kodaira…

1988-01-01T23:59:59.000Z

236

GASFLOW: A computational model to analyze accidents in nuclear containment and facility buildings  

SciTech Connect (OSTI)

GASFLOW is a finite-volume computer code that solves the time-dependent, compressible Navier-Stokes equations for multiple gas species. The fluid-dynamics algorithm is coupled to the chemical kinetics of combusting liquids or gases to simulate diffusion or propagating flames in complex geometries of nuclear containment or confinement and facilities` buildings. Fluid turbulence is calculated to enhance the transport and mixing of gases in rooms and volumes that may be connected by a ventilation system. The ventilation system may consist of extensive ductwork, filters, dampers or valves, and fans. Condensation and heat transfer to walls, floors, ceilings, and internal structures are calculated to model the appropriate energy sinks. Solid and liquid aerosol behavior is simulated to give the time and space inventory of radionuclides. The solution procedure of the governing equations is a modified Los Alamos ICE`d-ALE methodology. Complex facilities can be represented by separate computational domains (multiblocks) that communicate through overlapping boundary conditions. The ventilation system is superimposed throughout the multiblock mesh. Gas mixtures and aerosols are transported through the free three-dimensional volumes and the restricted one-dimensional ventilation components as the accident and fluid flow fields evolve. Combustion may occur if sufficient fuel and reactant or oxidizer are present and have an ignition source. Pressure and thermal loads on the building, structural components, and safety-related equipment can be determined for specific accident scenarios. GASFLOW calculations have been compared with large oil-pool fire tests in the 1986 HDR containment test T52.14, which is a 3000-kW fire experiment. The computed results are in good agreement with the observed data.

Travis, J.R. [Science Applications International Corp., Albuquerque, NM (United States); Nichols, B.D.; Wilson, T.L.; Lam, K.L.; Spore, J.W.; Niederauer, G.F. [Los Alamos National Lab., NM (United States)

1993-07-01T23:59:59.000Z

237

GASFLOW: A computational model to analyze accidents in nuclear containment and facility buildings  

SciTech Connect (OSTI)

GASFLOW is a finite-volume computer code that solves the time-dependent, compressible Navier-Stokes equations for multiple gas species. The fluid-dynamics algorithm is coupled to the chemical kinetics of combusting liquids or gases to simulate diffusion or propagating flames in complex geometries of nuclear containment or confinement and facilities' buildings. Fluid turbulence is calculated to enhance the transport and mixing of gases in rooms and volumes that may be connected by a ventilation system. The ventilation system may consist of extensive ductwork, filters, dampers or valves, and fans. Condensation and heat transfer to walls, floors, ceilings, and internal structures are calculated to model the appropriate energy sinks. Solid and liquid aerosol behavior is simulated to give the time and space inventory of radionuclides. The solution procedure of the governing equations is a modified Los Alamos ICE'd-ALE methodology. Complex facilities can be represented by separate computational domains (multiblocks) that communicate through overlapping boundary conditions. The ventilation system is superimposed throughout the multiblock mesh. Gas mixtures and aerosols are transported through the free three-dimensional volumes and the restricted one-dimensional ventilation components as the accident and fluid flow fields evolve. Combustion may occur if sufficient fuel and reactant or oxidizer are present and have an ignition source. Pressure and thermal loads on the building, structural components, and safety-related equipment can be determined for specific accident scenarios. GASFLOW calculations have been compared with large oil-pool fire tests in the 1986 HDR containment test T52.14, which is a 3000-kW fire experiment. The computed results are in good agreement with the observed data.

Travis, J.R. (Science Applications International Corp., Albuquerque, NM (United States)); Nichols, B.D.; Wilson, T.L.; Lam, K.L.; Spore, J.W.; Niederauer, G.F. (Los Alamos National Lab., NM (United States))

1993-01-01T23:59:59.000Z

238

System modeling and reactor design studies of the Advanced Thermionic Initiative space nuclear reactor  

SciTech Connect (OSTI)

In-core thermionic space reactor design concepts that operate at a nominal power output range of 20 to 50 kW(electric) are described. Details of the neutronic, thermionic, thermal hydraulics, and shielding performance are presented. Because of the strong absorption of thermal neutrons by natural tungsten and the large amount of natural tungsten within the reactor core, two designs are considered. An overall system design code has been developed at Oregon State University to model advanced in-core thermionic energy conversion-based nuclear reactor systems for space applications. The results show that the driverless single-cell Advanced Thermionic Initiative (ATI) configuration, which does not have driver fuel rods, proved to be more efficient than the driven core, which has driver rods. The results also show that the inclusion of the true axial and radial power distribution decrease the overall conversion efficiency. The flattening of the radial power distribution by three different methods would lead to a higher efficiency. The results show that only one TFE works at the optimum emitter temperature; all other TFEs are off the optimum performance and result in a 40% decrease of the efficiency of the overall system. The true axial profile is significantly different as there is a considerable amount of neutron leakage out of the top and bottom of the reactor. The analysis reveals that the axial power profile actually has a chopped cosine shape. For this axial profile, the reactor core overall efficiency for the driverless ATI reactor version is found to be 5.84% with a total electrical power of 21.92 kW(electric). By considering the true axial power profile instead of the uniform power profile, each TFE loses {approximately}80 W(electric).

Lee, H.H.; Abdul-Hamid, S.; Klein, A.C. [Oregon State Univ., Corvallis, OR (United States). Dept. of Nuclear Engineering Radiation Center] [Oregon State Univ., Corvallis, OR (United States). Dept. of Nuclear Engineering Radiation Center

1996-07-01T23:59:59.000Z

239

Implementation of a Low Cost Robot Controller PC-ROBOCONT on Hydraulic Robot for Spray Painting G-201  

Science Journals Connector (OSTI)

The paper describes the implementation of the low cost robot controller PC-ROBOCONT on hydraulic spray painting robot G-201. PC-ROBOCONT is a low cost robot controller based on popular PC 386. For use with the sp...

B. Nemec; L. Zlajpah; S. Mrak

1994-01-01T23:59:59.000Z

240

Long-Term Planning for Nuclear Energy Systems Under Deep Uncertainty  

E-Print Network [OSTI]

5.3.2 Nuclear Energy System Model . . . . . . . . . . .Brief History of Nuclear Energy . . . . . . . . Nuclear FuelModeling . . . . . . . . . . . . . 5.3 Nuclear Energy System

Kim, Lance Kyungwoo

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

DOE/DHS INDUSTRIAL CONTROL SYSTEM CYBER SECURITY PROGRAMS: A MODEL FOR USE IN NUCLEAR FACILITY SAFEGUARDS AND SECURITY  

SciTech Connect (OSTI)

Many critical infrastructure sectors have been investigating cyber security issues for several years especially with the help of two primary government programs. The U.S. Department of Energy (DOE) National SCADA Test Bed and the U.S. Department of Homeland Security (DHS) Control Systems Security Program have both implemented activities aimed at securing the industrial control systems that operate the North American electric grid along with several other critical infrastructure sectors (ICS). These programs have spent the last seven years working with industry including asset owners, educational institutions, standards and regulating bodies, and control system vendors. The programs common mission is to provide outreach, identification of cyber vulnerabilities to ICS and mitigation strategies to enhance security postures. The success of these programs indicates that a similar approach can be successfully translated into other sectors including nuclear operations, safeguards, and security. The industry regulating bodies have included cyber security requirements and in some cases, have incorporated sets of standards with penalties for non-compliance such as the North American Electric Reliability Corporation Critical Infrastructure Protection standards. These DOE and DHS programs that address security improvements by both suppliers and end users provide an excellent model for nuclear facility personnel concerned with safeguards and security cyber vulnerabilities and countermeasures. It is not a stretch to imagine complete surreptitious collapse of protection against the removal of nuclear material or even initiation of a criticality event as witnessed at Three Mile Island or Chernobyl in a nuclear ICS inadequately protected against the cyber threat.

Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

2011-07-01T23:59:59.000Z

242

Nuclear Physics for Nuclear Fusion  

SciTech Connect (OSTI)

The nuclear fusion data for deuteron-triton resonance near 100 keV are found to be consistent with the selective resonant tunneling model. The feature of this selective resonant tunneling is the selectivity. It selects not only the energy level, but also the damping rate (nuclear reaction rate). When the Coulomb barrier is thin and low, the resonance selects the fast reaction channel; however, when the Coulomb barrier is thick and high, the resonance selects the slow reaction channel. This mechanism might open an approach toward fusion energy with no strong nuclear radiation.

Li Xingzhong [Tsinghua University (China)

2002-01-15T23:59:59.000Z

243

OC)elRM(o-T/^ DOE/PC/60810-TIO TITLE: Superacid Catalyzed Coal Conversion Chemistry DE86 015045  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

OC)elRM(o-T/^ OC)elRM(o-T/^ DOE/PC/60810-TIO TITLE: Superacid Catalyzed Coal Conversion Chemistry DE86 015045 PIs(Authors): George A. Olah INSTITUTION/ORGANIZATION UNIVERSITY OF SOUTHERN CALIFORNIA HYDROCARBON RESEARCH INSTITUTE CONTRACT NO.: FINAL TECHNICAL REPORT (213)743-5277 DE-FG22-83PC60810 September 1,1983-September 1,1986 The basis of our studies was a novel, low temperature, mild coal conversion process developed in our laboratory. It involves the use of a superacidic system consisting of HF and BF, in the presence of hydrogen and/or a hydrogen donor solvent. In order to understand the chemistry involved in the process of hydrodepolyme- rization of coal by HF:BF2:H2 system a systematic study of a number of coal model compounds was carried out under identical conditions. The model compounds studied

244

Microsoft Word - PC-000587_0_rel.doc  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Plant (NGNP) with Hydrogen Production Assessment of Russian Federation Test Facilities Capabilities to Support NGNP R&D Prepared by General Atomics for the...

245

Why Model-Based Engineering and Manufacturing Makes Sense for the Plants and Laboratories of the Nuclear Weapon Complex  

SciTech Connect (OSTI)

The purpose of this White Paper is to outline the benefits we expect to receive from Model-Based Engineering and Manufacturing (MBE/M) for the design, analysis, fabrication, and assembly of nuclear weapons for upcoming Life Extension Programs (LEPs). Industry experiences with model-based approaches and the NNSA/DP investments and experiences, discussed in this paper, indicate that model-based methods can achieve reliable refurbished weapons for the stockpile with less cost and time. In this the paper, we list both general and specific benefits of MBE/M for the upcoming LEPs and the metrics for determining the success of model-based approaches. We also present some outstanding issues and challenges to deploying and achieving long-term benefit from the MBE/M. In conclusion, we argue that successful completion of the upcoming LEPs--with very aggressive schedule and funding restrictions--will depend on electronic model-based methods. We ask for a strong commitment from LEP managers throughout the Nuclear Weapons Complex to support deployment and use of MBE/M systems to meet their program needs.

Franklin, K W; Howell, L N; Lewis, D G; Neugebauer, C A; O'Brien, D W; Schilling, S A

2001-05-15T23:59:59.000Z

246

Application of a 2-D particle tracking model to simulate entrainment of winter flounder larvae at the Millstone Nuclear Power Station  

E-Print Network [OSTI]

A 2-D random walk model, developed by Dimou (1989) as part of this research project, was used to simulate entrainment at the Millstone Nuclear Power Station of winter flounder larvae hatched within Niantic River.

Dimou, Nadia K.

1989-01-01T23:59:59.000Z

247

Cognitive decision errors and organization vulnerabilities in nuclear power plant safety management: Modeling using the TOGA meta-theory framework  

SciTech Connect (OSTI)

In the field of nuclear power plant (NPP) safety modeling, the perception of the role of socio-cognitive engineering (SCE) is continuously increasing. Today, the focus is especially on the identification of human and organization decisional errors caused by operators and managers under high-risk conditions, as evident by analyzing reports on nuclear incidents occurred in the past. At present, the engineering and social safety requirements need to enlarge their domain of interest in such a way to include all possible losses generating events that could be the consequences of an abnormal state of a NPP. Socio-cognitive modeling of Integrated Nuclear Safety Management (INSM) using the TOGA meta-theory has been discussed during the ICCAP 2011 Conference. In this paper, more detailed aspects of the cognitive decision-making and its possible human errors and organizational vulnerability are presented. The formal TOGA-based network model for cognitive decision-making enables to indicate and analyze nodes and arcs in which plant operators and managers errors may appear. The TOGA's multi-level IPK (Information, Preferences, Knowledge) model of abstract intelligent agents (AIAs) is applied. In the NPP context, super-safety approach is also discussed, by taking under consideration unexpected events and managing them from a systemic perspective. As the nature of human errors depends on the specific properties of the decision-maker and the decisional context of operation, a classification of decision-making using IPK is suggested. Several types of initial situations of decision-making useful for the diagnosis of NPP operators and managers errors are considered. The developed models can be used as a basis for applications to NPP educational or engineering simulators to be used for training the NPP executive staff. (authors)

Cappelli, M. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Gadomski, A. M. [ECONA, Centro Interuniversitario Elaborazione Cognitiva Sistemi Naturali e Artificiali, via dei Marsi 47, Rome (Italy); Sepiellis, M. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Wronikowska, M. W. [UTFISST, ENEA Casaccia, via Anguillarese 301, Rome (Italy); Poznan School of Social Sciences (Poland)

2012-07-01T23:59:59.000Z

248

Health effects models for nuclear power plant accident consequence analysis. Modification of models resulting from addition of effects of exposure to alpha-emitting radionuclides: Revision 1, Part 2, Scientific bases for health effects models, Addendum 2  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission (NRC) has sponsored several studies to identify and quantify, through the use of models, the potential health effects of accidental releases of radionuclides from nuclear power plants. The Reactor Safety Study provided the basis for most of the earlier estimates related to these health effects. Subsequent efforts by NRC-supported groups resulted in improved health effects models that were published in the report entitled {open_quotes}Health Effects Models for Nuclear Power Plant Consequence Analysis{close_quotes}, NUREG/CR-4214, 1985 and revised further in the 1989 report NUREG/CR-4214, Rev. 1, Part 2. The health effects models presented in the 1989 NUREG/CR-4214 report were developed for exposure to low-linear energy transfer (LET) (beta and gamma) radiation based on the best scientific information available at that time. Since the 1989 report was published, two addenda to that report have been prepared to (1) incorporate other scientific information related to low-LET health effects models and (2) extend the models to consider the possible health consequences of the addition of alpha-emitting radionuclides to the exposure source term. The first addendum report, entitled {open_quotes}Health Effects Models for Nuclear Power Plant Accident Consequence Analysis, Modifications of Models Resulting from Recent Reports on Health Effects of Ionizing Radiation, Low LET Radiation, Part 2: Scientific Bases for Health Effects Models,{close_quotes} was published in 1991 as NUREG/CR-4214, Rev. 1, Part 2, Addendum 1. This second addendum addresses the possibility that some fraction of the accident source term from an operating nuclear power plant comprises alpha-emitting radionuclides. Consideration of chronic high-LET exposure from alpha radiation as well as acute and chronic exposure to low-LET beta and gamma radiations is a reasonable extension of the health effects model.

Abrahamson, S. [Wisconsin Univ., Madison, WI (United States); Bender, M.A. [Brookhaven National Lab., Upton, NY (United States); Boecker, B.B.; Scott, B.R. [Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (United States). Inhalation Toxicology Research Inst.; Gilbert, E.S. [Pacific Northwest Lab., Richland, WA (United States)

1993-05-01T23:59:59.000Z

249

PC-SAFT parameters from ab initio calculations  

Science Journals Connector (OSTI)

Abstract We use highly accurate ab initio calculations of binding enthalpies and entropies of gas phase clusters of alcohols to demonstrate how they can be used to obtain association parameters for PC-SAFT. The thermochemical results demonstrate that cooperativity effects and state dependent cluster distributions cause a strongly varying average enthalpy and entropy per bond as function of temperature and density for alcohols. In contrast to this, the two association parameters of PC-SAFT lead to density independent bond enthalpy and entropy and are thus effective parameters. Therefore, we choose to compute the cluster distribution at a universal state point and show that the thus obtained association parameters can be used to reduce the number of adjustable parameters from 5 to 3 with only a marginal loss of accuracy for most of the studied systems, and even an estimation of thermodynamic properties without adjusted parameters is possible. The ab initio calculations suggest that the 2B association scheme is more appropriate for 1-alkanols than the 3B one.

Muhammad Umer; Katja Albers; Gabriele Sadowski; Kai Leonhard

2014-01-01T23:59:59.000Z

250

Natural Circulation in Water Cooled Nuclear Power Plants Phenomena, models, and methodology for system reliability assessments  

SciTech Connect (OSTI)

In recent years it has been recognized that the application of passive safety systems (i.e., those whose operation takes advantage of natural forces such as convection and gravity), can contribute to simplification and potentially to improved economics of new nuclear power plant designs. In 1991 the IAEA Conference on ''The Safety of Nuclear Power: Strategy for the Future'' noted that for new plants the use of passive safety features is a desirable method of achieving simplification and increasing the reliability of the performance of essential safety functions, and should be used wherever appropriate''.

Jose Reyes

2005-02-14T23:59:59.000Z

251

Nuclear Models and Nuclear Fission  

Science Journals Connector (OSTI)

The hindrance to spontaneous fission by the odd nucleon in the fissioning nucleus may be explained as due to the pairing energy of the odd nucleon at the saddle-point deformation.

Peter Fong

1961-06-01T23:59:59.000Z

252

A Neural Network Model for the Tomographic Analysis of Irradiated Nuclear Fuel Rods  

SciTech Connect (OSTI)

A tomographic method based on a multilayer feed-forward artificial neural network is proposed for the reconstruction of gamma-radioactive fission product distribution in irradiated nuclear fuel rods. The quality of the method is investigated as compared to a conventional technique on experimental results concerning a Canada deuterium uranium reactor (CANDU)-type fuel rod irradiated in a TRIGA reactor.

Craciunescu, Teddy [National Institute of Nuclear Physics and Engineering (Romania)

2004-04-15T23:59:59.000Z

253

7 - Assessing and modelling the performance of nuclear waste and associated packages for long-term management  

Science Journals Connector (OSTI)

Abstract: Examples of analytical approaches and methodologies for modelling the behaviour of waste forms and waste package metals in long-term management of spent nuclear fuel (SNF) and high level waste (HLW) are presented. Two cases, long-term geological disposal and interim extended dry storage, are considered. The integrity of the waste package (or canister) that serves as a barrier is dependent upon the performance of construction metals. Corrosion degradation modes of the construction metals are evaluated. The waste behaviour during SNF degradation is also evaluated. In each mode of corrosion or degradation, the associated risk insights are discussed in the system performance of disposal or storage.

T.M. Ahn

2013-01-01T23:59:59.000Z

254

METHANE de-NOX FOR UTILITY PC BOILERS  

SciTech Connect (OSTI)

The overall project objective is the development and validation of an innovative combustion system, based on a novel coal preheating concept prior to combustion, that can reduce NO{sub x} emissions to 0.15 lb/million Btu or less on utility pulverized coal (PC) boilers. This NO{sub x} reduction should be achieved without loss of boiler efficiency or operating stability, and at more than 25% lower levelized cost than state-of-the-art SCR technology. A further objective is to make this technology ready for full-scale commercial deployment by 2002-2003 in order to meet an anticipated market demand for NO{sub x} reduction technologies resulting from the EPA's NO{sub x} SIP call.

Joseph Rabovitser

2000-07-05T23:59:59.000Z

255

METHANE de-NOX for Utility PC Boilers  

SciTech Connect (OSTI)

The overall project objective is the development and validation of an innovative coal combustion system, based on a novel coal preheating concept prior to combustion, that can reduce NO{sub x} emissions to 0.15 lb/million Btu or less on utility pulverized coal (PC) boilers without the need for post-combustion cleaning. Work during the quarter included initiation of the equipment fabrication effort for all pilot system components. Fabrication of the gas-fired combustor was started and completed by IGT during the quarter. The combustor was then installed in IGT's combustion laboratory for proof-of-performance testing prior to shipping to BBP for installation in the pilot-scale test system. A testing procedure and performance goals were developed for the combustor testing.

Joseph Rabovitser; Bruce Bryan; Stan Wohadlo

2001-03-31T23:59:59.000Z

256

METHANE de-NOX for Utility PC Boilers  

SciTech Connect (OSTI)

The project seeks to develop and validate a new pulverized coal combustion system to reduce utility PC boiler NO{sub x} emissions to 0.15 lb/million Btu or less without post-combustion flue gas cleaning. Work during the quarter included continuation of the equipment fabrication effort for pilot system components. Successful proof-of-performance testing of the IGT-designed pilot-scale natural gas-fired coal preheat combustor was completed by IGT during the quarter. The combustor was then disassembled and shipped for installation in the pilot-scale test system in BBP's Coal Burner Test Facility (CBTF) in Worcester, MA. Delivery of the balance of the pilot system components from the fabricator began near the end of the quarter, with components being installed in the pilot test facility as they were received.

Joseph Rabovitser; Bruce Bryan; Serguei Nester; Stan Wohadlo

2001-06-30T23:59:59.000Z

257

Proceedings of a symposium on the occasion of the 40th anniversary of the nuclear shell model  

SciTech Connect (OSTI)

This report contains papers on the following topics: excitation of 1p-1h stretched states with the (p,n) reaction as a test of shell-model calculations; on Z=64 shell closure and some high spin states of {sup 149}Gd and {sup 159}Ho; saturating interactions in {sup 4}He with density dependence; are short-range correlations visible in very large-basis shell-model calculations ; recent and future applications of the shell model in the continuum; shell model truncation schemes for rotational nuclei; the particle-hole interaction and high-spin states near A-16; magnetic moment of doubly closed shell +1 nucleon nucleus {sup 41}Sc(I{sup {pi}}=7/2{sup {minus}}); the new magic nucleus {sup 96}Zr; comparing several boson mappings with the shell model; high spin band structures in {sup 165}Lu; optical potential with two-nucleon correlations; generalized valley approximation applied to a schematic model of the monopole excitation; pair approximation in the nuclear shell model; and many-particle, many-hole deformed states.

Lee, T.S.H.; Wiringa, R.B. (eds.)

1990-03-01T23:59:59.000Z

258

A global investigation of phase equilibria using the Perturbed-Chain Statistical-Associating-Fluid-Theory (PC-SAFT) approach  

E-Print Network [OSTI]

The recently developed Perturbed-Chain Statistical Associating Fluid Theory (PC-SAFT) is investigated for a wide range of model parameters including the parameter m representing the chain length and the thermodynamic temperature T and pressure p. This approach is based upon the first-order thermodynamic perturbation theory for chain molecules developed by Wertheim and Chapman et al. and includes dispersion interactions via the second-order perturbation theory of Barker and Henderson. We systematically study a hierarchy of models which are based on the PC-SAFT approach using analytical model calculations and Monte Carlo simulations. For one-component systems we find that the analytical model in contrast to the simulation results exhibits two phase-separation regions in addition to the common gas-liquid coexistence region: One phase separation occurs at high density and low temperature. The second demixing takes place at low density and high temperature where usually the ideal gas phase is expected in the phase diagram. These phenomena, which are referred to as "liquid-liquid" and "gas-gas" equilibria, give rise to multiple critical points in one-component systems, as well as to critical end points (CEP) and equilibria of three fluid phases, which can usually be found in multicomponent mixtures only. Furthermore, it is shown that the "liquid-liquid" demixing in this model is not a consequence of a "softened" repulsive interaction as assumed in the theoretical derivation of the model. Experimental data for the melt density of polybutadiene with molecular mass Mw=45000g/mol are correlated here using the PC-SAFT equation. It is shown that the discrepancies in modeling the polymer density at ambient temperature and high pressure can be traced back to ...

L. Yelash; M. Mueller; W. Paul; K. Binder

2005-05-24T23:59:59.000Z

259

METHANE DE-NOX FOR UTILITY PC BOILERS  

SciTech Connect (OSTI)

During the current quarter, pilot-scale testing with the modified air nozzle version of the PC burner was completed with PRB coal at the Riley Power Inc. (RPI) test facility. A total of 8 different burner configurations were tested utilizing various burner air nozzle arrangements in place of the burner air channels. It was found that with the arrangements tested, a stable flame could not be maintained at coal feed rates above 100 lb/h. While it is felt that the air nozzle approach can ultimately be used effectively, in the interest of holding to the current project schedule it was decided to proceed with the balance of the project using the air channel design. The pilot-scale PC burner was therefore restored to the air-channel configuration and benchmark testing with PRB coal to confirmed previous operating results. A series of tests was then conducted with PRB and West Virginia caking coal to evaluate modifications to the gas combustor configuration and operation for improved performance with caking coal. Continuous operation was achieved with caking coal up to 50 lb/h vs. the full load target of 150 lb/h. Impingement and deposition of partially devolatilized coal occurred at various points within the combustor when the caking coal feed was increased above 50 lb/h. The 100 MMBtu/h commercial-scale prototype design was started with coal burner design input from both RPI and VTI. Based on typical burner installation layout considerations, it was that the preheat combustor should be oriented horizontally on the axial centerline of the coal burner. Accordingly, work was begun to relocate the pilot gas combustor to this orientation so that the pilot results with caking coal will be directly applicable to the preferred 100 MMBtu design. Inspection and repair of the 100 MMBtu/h Coal Burner Test Facility (CBTF) was initiated by RPI and as of 6/30, this activity was 70% complete.

Bruce Bryan; Joseph Rabovitser; Serguei Nester; Stan Wohadlo

2003-07-30T23:59:59.000Z

260

Progress in the Development of Compressible, Multiphase Flow Modeling Capability for Nuclear Reactor Flow Applications  

SciTech Connect (OSTI)

In nuclear reactor safety and optimization there are key issues that rely on in-depth understanding of basic two-phase flow phenomena with heat and mass transfer. Within the context of multiphase flows, two bubble-dynamic phenomena – boiling (heterogeneous) and flashing or cavitation (homogeneous boiling), with bubble collapse, are technologically very important to nuclear reactor systems. The main difference between boiling and flashing is that bubble growth (and collapse) in boiling is inhibited by limitations on the heat transfer at the interface, whereas bubble growth (and collapse) in flashing is limited primarily by inertial effects in the surrounding liquid. The flashing process tends to be far more explosive (and implosive), and is more violent and damaging (at least in the near term) than the bubble dynamics of boiling. However, other problematic phenomena, such as crud deposition, appear to be intimately connecting with the boiling process. In reality, these two processes share many details.

R. A. Berry; R. Saurel; F. Petitpas; E. Daniel; O. Le Metayer; S. Gavrilyuk; N. Dovetta

2008-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Bruce Nuclear Generating Station B rapid cooldown test and validation of simulation model  

SciTech Connect (OSTI)

The SOPHT code was assessed against Bruce Nuclear Generating Station B commissioning data from a heat transport system rapid cooldown. It was found that (a) under a rapid upstream depressurization, the steam relief valves, like orifices, had a lower discharge coefficient than the corresponding steadystate value and (b) the flashing of water in the steam generators during depressurization causes the at-power boiling heat transfer correlations to overpredict the steam generator heat transfer.

Chang, Y.F.; Langan, M.D.; Sermer, P.; Watson, P.C.

1985-09-01T23:59:59.000Z

262

An evaluation of thermal modeling techniques utilized for nuclear fuel rods  

E-Print Network [OSTI]

like to thank my graduate advisor, Dr. K. L. Peddicord, for his technical advice and guidance throughout this project and my studies in Nuclear Engineering at Texas AgiM University. Thanks are also extended to Dr. Hassan and Dr. Caton for reviewing.... Burnup Fission Gas Rdease Fuel Tltermal Conductivity Fuel Cracking Fuel Creep Rate Fuel Relocadon Fuel VIrermal Expansion Fuel Rod Tltermal Power Fuel Telltpelanaes Fuel Stress es Fuel Strains Fission Rate Fuel-Cladding Gap Heat...

Simmons, Jeffrey Warren

2012-06-07T23:59:59.000Z

263

Development of a techno-economic model to optimization DOE spent nuclear fuel disposition  

SciTech Connect (OSTI)

The purpose of the National Spent Nuclear Fuel (NSNF) Program conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL) is to evaluate what to do with the spent nuclear fuel (SNF) in the Department of Energy (DOE) complex. Final disposition of the SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on the fuel type and the current locations of the fuel. One of the first steps associated with selecting one or more sites for treating the SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the electrometallurgical treatment process for fuels at several locations. The set of questions addresses all issues associated with the design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs will be applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment techniques for treating spent nuclear fuel.

Ramer, R.J.; Plum, M.M.; Adams, J.P.; Dahl, C.A.

1997-11-01T23:59:59.000Z

264

NETL: IEP – Oxy-Combustion CO2 Emissions Control - Oxygen-Based PC Boiler  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

– Oxy-Combustion CO2 Emissions Control – Oxy-Combustion CO2 Emissions Control Oxygen-Based PC Boiler Project No.: FC26-04NT42207 & FC26-03NT41736 Spatial Comparison of an Air-Fired Furnace versus an Oxygen-Fired Furnace. Spatial Comparison of an Air-Fired Furnace versus an Oxygen-Fired Furnace. Foster Wheeler North America Corporation will conduct to two projects to improve carbon dioxide (CO2) capture technology by developing a conceptual pulverized coal-fired boiler system design using oxygen as the combustion medium. Using oxygen instead of air produces a flue gas with a high CO2 concentration, which will facilitate CO2 capture for subsequent sequestration. The first project will develop modeling simulations that will lead to a conceptual design that addresses costs, performance, and emissions, and

265

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

266

Modeling the Action of Protons and Heavier Ions in Biological Targets: Nuclear Interactions in Hadrontherapy and Space Radiation Protection  

Science Journals Connector (OSTI)

Tumor treatment with protons and Carbon ions can allow for a better optimization of Tumor Control Probability and Normal Tissue Complication Probability especially for radio?resistant tumors. Exposure to protons and heavier ions is also of concern for manned space missions such as future travels to the Moon and Mars. Nuclear reactions with the human body constituents the beam line components (for hadrontherapy) and the spacecraft walls and shielding (for space radiation protection) can significantly modify the characteristics of the primary radiation field and thus the dose distributions in the various target tissues. In this context the FLUKA Monte Carlo transport code integrated with radiobiological data and coupled with anthropomorphic phantoms was applied to the characterization of therapeutic proton beams and the calculation of space radiation organ doses with focus on the role of nuclear interactions. Besides absorbed and equivalent doses distributions of “biological” dose (modeled as the average number of DNA clustered lesions per cell induced in a given organ or tissue) were calculated as well. Concerning space radiation protection exposure to Galactic Cosmic Rays (GCR) and Solar Particle Events (SPE) under different shielding conditions was simulated. Both for hadrontherapy and for space radiation exposure nuclear reaction products were found to play a more important role for the equivalent and “biological” dose than for the absorbed dose. Furthermore while for SPEs the doses (both absorbed and equivalent/“biological”) decreased dramatically by increasing the shield thickness the GCR doses showed a slight shielding dependence. Overall these examples of application of FLUKA to radiotherapy and radiation protection problems emphasized the need of further models and data typically double?differential cross sections for nucleus?nucleus interactions at energies below a few hundred MeV/n.

F. Ballarini; G. Battistoni; F. Cerutti; E. Gadioli; M. V. Garzelli; A. Ottolenghi; V. Parini; M. Pelliccioni; P. Sala; D. Scannicchio

2005-01-01T23:59:59.000Z

267

Improved Reliability of PV Modules with Lexan PC Sheet-Front...  

Broader source: Energy.gov (indexed) [DOE]

Total gauge Partial Discharge Voltage (with without E layer) Corelayer gauge Primer layer gauge ELECTRICAL INSULATION AND WHY POLYCARBONATE AS HIGHLY WEATHERABLE PC FILM...

268

Application of the PC-SAFT Equation of State to Asphaltene Phase Behavior  

Science Journals Connector (OSTI)

A method to characterize crude oil including asphaltenes using the perturbed chain form of the statistical associating fluid theory (PC-SAFT) is presented. The theory accurately predicts...

P. David Ting; Doris L. Gonzalez…

2007-01-01T23:59:59.000Z

269

System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2  

SciTech Connect (OSTI)

The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors.

Ellis, R.J.

2000-11-01T23:59:59.000Z

270

Spent nuclear fuel as a waste form for geologic disposal: Assessment and recommendations on data and modeling needs  

SciTech Connect (OSTI)

This study assesses the status of knowledge pertinent to evaluating the behavior of spent nuclear fuel as a waste form in geologic disposal systems and provides background information that can be used by the DOE to address the information needs that pertain to compliance with applicable standards and regulations. To achieve this objective, applicable federal regulations were reviewed, expected disposal environments were described, the status of spent-fuel modeling was summarized, and information regarding the characteristics and behavior of spent fuel was compiled. This compiled information was then evaluated from a performance modeling perspective to identify further information needs. A number of recommendations were made concerning information still needed to enhance understanding of spent-fuel behavior as a waste form in geologic repositories. 335 refs., 22 figs., 44 tabs.

Van Luik, A.E.; Apted, M.J.; Bailey, W.J.; Haberman, J.H.; Shade, J.S.; Guenther, R.E.; Serne, R.J.; Gilbert, E.R.; Peters, R.; Williford, R.E.

1987-09-01T23:59:59.000Z

271

Discrete Element Model for Simulations of Early-Life Thermal Fracturing Behaviors in Ceramic Nuclear Fuel Pellets  

SciTech Connect (OSTI)

A discrete element Model (DEM) representation of coupled solid mechanics/fracturing and heat conduction processes has been developed and applied to explicitly simulate the random initiations and subsequent propagations of interacting thermal cracks in a ceramic nuclear fuel pellet during initial rise to power and during power cycles. The DEM model clearly predicts realistic early-life crack patterns including both radial cracks and circumferential cracks. Simulation results clearly demonstrate the formation of radial cracks during the initial power rise, and formation of circumferential cracks as the power is ramped down. In these simulations, additional early-life power cycles do not lead to the formation of new thermal cracks. They do, however clearly indicate changes in the apertures of thermal cracks during later power cycles due to thermal expansion and shrinkage. The number of radial cracks increases with increasing power, which is consistent with the experimental observations.

Hai Huang; Ben Spencer; Jason Hales

2014-10-01T23:59:59.000Z

272

Lysophosphatidic acid induces reactive oxygen species generation by activating protein kinase C in PC-3 human prostate cancer cells  

SciTech Connect (OSTI)

Highlights: •LPA induces ROS generation through LPA{sub 1} and LPA{sub 3}. •LPA induces ROS generation by activating PLC. •PKC? mediates LPA-induced ROS generation. -- Abstract: Prostate cancer is one of the most frequently diagnosed cancers in males, and PC-3 is a cell model popularly used for investigating the behavior of late stage prostate cancer. Lysophosphatidic acid (LPA) is a lysophospholipid that mediates multiple behaviors in cancer cells, such as proliferation, migration and adhesion. We have previously demonstrated that LPA enhances vascular endothelial growth factor (VEGF)-C expression in PC-3 cells by activating the generation of reactive oxygen species (ROS), which is known to be an important mediator in cancer progression. Using flow cytometry, we showed that LPA triggers ROS generation within 10 min and that the generated ROS can be suppressed by pretreatment with the NADPH oxidase (Nox) inhibitor diphenylene iodonium. In addition, transfection with LPA{sub 1} and LPA{sub 3} siRNA efficiently blocked LPA-induced ROS production, suggesting that both receptors are involved in this pathway. Using specific inhibitors and siRNA, phospholipase C (PLC) and protein kinase C (PKC) were also suggested to participate in LPA-induced ROS generation. Overall, we demonstrated that LPA induces ROS generation in PC-3 prostate cancer cells and this is mediated through the PLC/PKC/Nox pathway.

Lin, Chu-Cheng; Lin, Chuan-En; Lin, Yueh-Chien [Institute of Zoology, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China)] [Institute of Zoology, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China); Ju, Tsai-Kai [Instrumentation Center, National Taiwan University, Taipei, Taiwan, ROC (China) [Instrumentation Center, National Taiwan University, Taipei, Taiwan, ROC (China); Technology Commons, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China); Huang, Yuan-Li [Department of Biotechnology, Asia University, Taichung, Taiwan, ROC (China)] [Department of Biotechnology, Asia University, Taichung, Taiwan, ROC (China); Lee, Ming-Shyue [Institute of Biochemistry and Molecular Biology, College of Medicine, National Taiwan University, Taipei, Taiwan, ROC (China)] [Institute of Biochemistry and Molecular Biology, College of Medicine, National Taiwan University, Taipei, Taiwan, ROC (China); Chen, Jiun-Hong [Institute of Zoology, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China) [Institute of Zoology, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China); Department of Life Science, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China); Lee, Hsinyu, E-mail: hsinyu@ntu.edu.tw [Institute of Zoology, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China) [Institute of Zoology, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China); Department of Life Science, College of Life Science, National Taiwan University, Taipei, Taiwan, ROC (China); Center for Biotechnology, National Taiwan University, Taipei, Taiwan, ROC (China); Research Center for Developmental Biology and Regenerative Medicine, National Taiwan University, Taipei, Taiwan, ROC (China)

2013-11-01T23:59:59.000Z

273

Modeling Groundwater Flow and Transport of Radionuclides at Amchitka Island's Underground Nuclear Tests: Milrow, Long Shot, and Cannikin  

SciTech Connect (OSTI)

Since 1963, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive material in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site (NTS), but a limited number of experiments were conducted in other locations. One of these locations, Amchitka Island, Alaska is the subject of this report. Three underground nuclear tests were conducted on Amchitka Island. Long Shot was an 80-kiloton-yield test conducted at a depth of 700 meters (m) on October 29, 1965 (DOE, 2000). Milrow had an announced yield of about 1,000 kilotons, and was detonated at a depth of 1,220 m on October 2, 1969. Cannikin had an announced yield less than 5,000 kilotons, and was conducted at a depth of 1,790 m on November 6, 1971. The purpose of this work is to provide a portion of the information needed to conduct a human-health risk assessment of the potential hazard posed by the three underground nuclear tests on Amchitka Island. Specifically, the focus of this work is the subsurface transport portion, including the release of radionuclides from the underground cavities and their movement through the groundwater system to the point where they seep out of the ocean floor and into the marine environment. This requires a conceptual model of groundwater flow on the island using geologic, hydrologic, and chemical information, a numerical model for groundwater flow, a conceptual model of contaminant release and transport properties from the nuclear test cavities, and a numerical model for contaminant transport. Needed for the risk assessment are estimates of the quantity of radionuclides (in terms of mass flux) from the underground tests on Amchitka that could discharge to the ocean, the time of possible discharge, and the location in terms of distance from shoreline. The radionuclide data presented here are all reported in terms of normalized masses to avoid presenting classified information. As only linear processes are modeled, the results can be readily scaled by the true classified masses for use in the risk assessment. The modeling timeframe for the risk assessment was set at 1,000 years, though some calculations are extended to 2,000 years. This first section of the report endeavors to orient the reader with the environment of Amchitka and the specifics of the underground nuclear tests. Of prime importance are the geologic and hydrologic conditions of the subsurface. A conceptual model for groundwater flow beneath the island is then developed and paired with an appropriate numerical modeling approach in section 2. The parameters needed for the model, supporting data for them, and data uncertainties are discussed at length. The calibration of the three flow models (one for each test) is then presented. At this point the conceptual radionuclide transport model is introduced and its numerical approach described in section 3. Again, the transport parameters and their supporting data and uncertainties are the focus. With all of the processes and parameters in place, the first major modeling phase can be discussed in section 4. In this phase, a parametric uncertainty analysis is performed to determine the sensitivity of the transport modeling results to the uncertainties present in the parameters. This analysis is motivated by the recognition of substantial uncertainty in the subsurface conditions on the island and the need to incorporate that uncertainty into the modeling. The conclusion of the first phase determines the parameters to hold as uncertain through the main flow and transport modeling. This second, main phase of modeling is presented in section 5, with the contaminant breakthrough behavior of each test site addressed. This is followed by a sensitivity analysis in section 6, regarding the importance of additional processes that could not be supported in the main modeling effort due to lack of data. Finally, the results for the individual sites are compared, the sensitivities discussed,

Ahmed Hassan; Karl Pohlmann; Jenny Chapman

2002-11-19T23:59:59.000Z

274

Nuclear spirals in galaxies  

E-Print Network [OSTI]

Recent high-resolution observations indicate that nuclear spirals are often present in the innermost few hundred parsecs of disc galaxies. My models show that nuclear spirals form naturally as a gas response to non-axisymmetry in the gravitational potential. Some nuclear spirals take the form of spiral shocks, resulting in streaming motions in the gas, and in inflow comparable to the accretion rates needed to power local Active Galactic Nuclei. Recently streaming motions of amplitude expected from the models have been observed in nuclear spirals, confirming the role of nuclear spirals in feeding of the central massive black holes.

Witold Maciejewski

2006-11-08T23:59:59.000Z

275

Fully self-consistent mean-eld model of asymmetric nuclear matter  

E-Print Network [OSTI]

to be charge symmetric or invariant. This is theoretically realized in the Dirac-Brueckner-Hartree-Fock (DBHF) model [2-4]. (Precisely, this is also realized in the nonrelativistic Brueckner-Hartree-Fock model

276

Collective enhancement of nuclear state densities by the shell model Monte Carlo approach  

E-Print Network [OSTI]

The shell model Monte Carlo (SMMC) approach allows for the microscopic calculation of statistical and collective properties of heavy nuclei using the framework of the configuration-interaction shell model in very large model spaces. We present recent applications of the SMMC method to the calculation of state densities and their collective enhancement factors in rare-earth nuclei.

Özen, C; Nakada, H

2015-01-01T23:59:59.000Z

277

METHANE de-NOX for Utility PC Boilers  

SciTech Connect (OSTI)

During the current quarter, pilot-scale testing with the modified air nozzle version of the PC burner was completed with PRB coal at the Riley Power Inc. (RPI) test facility. A total of 8 different burner configurations were tested utilizing various burner air nozzle arrangements in place of the burner air channels. It was found that with the arrangements tested, a stable flame could not be maintained at coal feed rates above 100 lb/h. While it is felt that the air nozzle approach can ultimately be used effectively, in the interest of holding to the current project schedule it was decided to proceed with the balance of the project using the air channel design. The pilot-scale PC burner was therefore restored to the air-channel configuration and benchmark testing with PRB coal to confirmed previous operating results. A series of tests was then conducted with PRB and West Virginia caking coal to evaluate modifications to the gas combustor configuration and operation for improved performance with caking coal. Continuous operation was achieved with caking coal up to 50 lb/h vs. the full load target of 150 lb/h. Impingement and deposition of partially devolatilized coal occurred at various points within the combustor when the caking coal feed was increased above 50 lb/h. The 100 MMBtu/h commercial-scale prototype design was continued with coal burner design input from both RPI and VTI. Based on typical burner installation layout considerations, it was decided that the preheat combustor should be oriented horizontally on the axial centerline of the coal burner. Accordingly, the pilot gas combustor was changed to this orientation so that the pilot results with caking coal will be directly applicable to the preferred 100 MMBtu design. Testing with caking coal in the horizontal pilot combustor achieved feed rates up to 126 lb/h, although some deposition and LOI issues remain. Several promising approaches to further improve operation with caking coal were identified. NOx results with caking coal are promising, with NOx as low as 150 ppmv at exit oxygen levels of 4% and higher. The 100 MMBtu/h commercial-scale prototype design is nearing completion. Design of the caking coal version of the unit continues with additional pilot testing in support of this design expected. GTI and RPI are expediting the fabrication of the 100 MMBtu/h PRB unit in order to start testing in early- to mid-December. Inspection and repair of the 100 MMBtu/h Coal Burner Test Facility (CBTF) is nearing completion. As of mid-September, this activity was 95% complete.

Bruce Bryan; Joseph Rabovitser; Serguei Nester; Stan Wohadlo

2003-09-30T23:59:59.000Z

278

Development of a Techno-Economic Model to Optimize DOE Spent Nuclear Fuel Disposition  

SciTech Connect (OSTI)

The National Spent Nuclear Fuel (NSNF) Program is evaluating final disposition of spent nuclear fuel (SNE) in the Department of Energy (DOE) complex. Final disposition of SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the EMT process for fuels at several locations. The set of questions addresses all issues associated with design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs can be applied to determine the life cycle cost of each option. This technique can also be applied to other treatment techniques for treating SNF.

Ramer, R. J.; Plum, M. M.; Adams, J. P.; Dahl, C. A.

1998-02-01T23:59:59.000Z

279

[See overleaf for HiPC 2007 Organization] 14th IEEE International Conference on  

E-Print Network [OSTI]

on High Performance Computing (HiPC 2007) will be held in Goa, India, during December 18-21, 2007 to provide stimulating discussions and highlight high performance computing activities in AsiaPC 2007 will focus on the design and analysis of high performance computing and networking systems

Gavrilovska, Ada

280

Potassium-Rankine power conversion subsystem modeling for nuclear electric propulsion  

SciTech Connect (OSTI)

A potassium-Rankine power conversion system model was developed under Contract No. NAS3-25808 for the NASA-LeRC. This model predicts potassium-Rankine performance for turbine inlet temperatures (TIT) from 1200 - 1600 K, TIT to condenser temperature ratios from 1.25-1.6, power levels from 100 to 10,000 kWe, and lifetimes from 2-10 years. The model is for a Rankine cycle with reheat for turbine stage moisture control. The model assumes heat is supplied from a lithium heat transport loop. The model does not include a heat source or a condenser/heat rejection system model. These must be supplied by the user.

Johnson, G.A.

1993-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
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281

Coulomb reacceleration as a clock for nuclear reactions: A two-dimensional model  

Science Journals Connector (OSTI)

Reacceleration effects in the Coulomb breakup of nuclei are modeled with the two-dimensional time-dependent Schrödinger equation, extending a previous one-dimensional study. The present model better describes the individual contributions of longitudinal and transverse forces to the breakup and reacceleration. Reacceleration effects are found to preserve a strong memory of the pre-breakup phase of the reaction, as was concluded with the one-dimensional model.

C. A. Bertulani and G. F. Bertsch

1994-05-01T23:59:59.000Z

282

Modelling and Numerical Simulation of Gas Migration in a Nuclear Waste Repository  

E-Print Network [OSTI]

We present a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological radioactive waste repository. This model includes capillary effects and the gas diffusivity. The choice of the main variables in this model, Total or Dissolved Hydrogen Mass Concentration and Liquid Pressure, leads to a unique and consistent formulation of the gas phase appearance and disappearance. After introducing this model, we show computational evidences of its adequacy to simulate gas phase appearance and disappearance in different situations typical of underground radioactive waste repository.

Bourgeat, Alain; Smai, Farid

2010-01-01T23:59:59.000Z

283

Nuclear Energy  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Research Programs >> Nuclear Energy Error Error Nuclear Energy Home - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Energy Home - RCC * Increasing...

284

Robust nonlinear model predictive control for nuclear power plants in load following operations with bounded xenon oscillations  

Science Journals Connector (OSTI)

One of the important operations in nuclear power plants is load-following in which imbalance of axial power distribution induces xenon oscillations. These oscillations must be maintained within acceptable limits otherwise the nuclear power plant could become unstable. Therefore, bounded xenon oscillation considered to be a constraint for the load-following operation. In this paper, a robust nonlinear model predictive control for the load-following operation problem is proposed that ensures xenon oscillations are kept bounded within acceptable limits. The proposed controller uses constant axial offset (AO) strategy to maintain xenon oscillations to be bounded. The constant AO is a robust state constraint for load-following problem. The controller imposes restricted state constraints on the predicted trajectory during optimization which guarantees robust satisfaction of state constraints without restoring to a min–max optimization problem. Simulation results show that the proposed controller for the load-following operation is so effective so that the xenon oscillations kept bounded in the given region.

H. Eliasi; M.B. Menhaj; H. Davilu

2011-01-01T23:59:59.000Z

285

NUCLEAR FLUID DYNAMICS VERSUS INTRANUCLEAR CASCADE--POSSIBLE EVIDENCE FOR COLLECTIVE FLOW IN CENTRAL HIGH ENERGY NUCLEAR COLLISIONS  

E-Print Network [OSTI]

Flow in Central High Energy Nuclear Collisions H. Stockera,theoretical models of high energy nuclear collisions andunder Contract High energy nuclear collisions offer a unique

Stocker, H.

2012-01-01T23:59:59.000Z

286

U-088: Symantec pcAnywhere Bugs Let Remote Users Execute Arbitrary Code |  

Broader source: Energy.gov (indexed) [DOE]

8: Symantec pcAnywhere Bugs Let Remote Users Execute Arbitrary 8: Symantec pcAnywhere Bugs Let Remote Users Execute Arbitrary Code U-088: Symantec pcAnywhere Bugs Let Remote Users Execute Arbitrary Code January 25, 2012 - 6:00am Addthis PROBLEM: A remote user can execute arbitrary code on the target system. PLATFORM: Version(s): 12.5 SP3; pcAnywhere Solutions 7.1 GA, SP 1, and SP 2 ABSTRACT: Two vulnerabilities were reported in Symantec pcAnywhere. A remote user can execute arbitrary code on the target system. A local user can obtain elevated privileges on the target system. reference LINKS: Symantec Advisory Secunia Advisory SecurityTracker Alert ID:102576 IMPACT ASSESSMENT: Medium Discussion: A remote user can send specially crafted data to TCP port 5631 to trigger a but in the validation of authentication data and execute arbitrary code.

287

Monte Carlo Modeling of Photon Interrogation Methods for Characterization of Special Nuclear Material  

SciTech Connect (OSTI)

This work illustrates a methodology based on photon interrogation and coincidence counting for determining the characteristics of fissile material. The feasibility of the proposed methods was demonstrated using a Monte Carlo code system to simulate the full statistics of the neutron and photon field generated by the photon interrogation of fissile and non-fissile materials. Time correlation functions between detectors were simulated for photon beam-on and photon beam-off operation. In the latter case, the correlation signal is obtained via delayed neutrons from photofission, which induce further fission chains in the nuclear material. An analysis methodology was demonstrated based on features selected from the simulated correlation functions and on the use of artificial neural networks. We show that the methodology can reliably differentiate between highly enriched uranium and plutonium. Furthermore, the mass of the material can be determined with a relative error of about 12%. Keywords: MCNP, MCNP-PoliMi, Artificial neural network, Correlation measurement, Photofission

Pozzi, Sara A [ORNL; Downar, Thomas J [ORNL; Padovani, Enrico [Nuclear Engineering Department Politecnico di Milano, Milan, Italy; Clarke, Shaun D [ORNL

2006-01-01T23:59:59.000Z

288

Non-Born–Oppenheimer nuclear and electronic densities for a three-particle Hooke–Coulomb model  

Science Journals Connector (OSTI)

Abstract Non-Born–Oppenheimer, nBO, one-particle nuclear and electron densities for a Hooke–Coulomb model of a three-body system are presented. These densities are obtained using exact closed-form analytic solutions to this problem as well as variational solutions. Moreover, the densities are calculated using different reference points, such as the global center of mass [cm], the geometric centers between both identical [gc12] and non-identical particles [cm13], and the location of the non-identical particle [p3]. It is shown that the topology of these nBO densities depends upon the choice of the reference points. This result is in turn used to argue that in a nBO regime the topological properties of the one-particle density cannot be univocally correlated with molecular structure, in the way it is done for the Born–Oppenheimer approximation.

C.G. Rodríguez; A.S. Urbina; F.J. Torres; D. Cazar; E.V. Ludeña

2013-01-01T23:59:59.000Z

289

CFD Model Of A Planar Solid Oxide Electrolysis Cell For Hydrogen Production From Nuclear Energy  

SciTech Connect (OSTI)

A three-dimensional computational fluid dynamics (CFD) model has been created to model hightemperature steam electrolysis in a planar solid oxide electrolysis cell (SOEC). The model represents a single cell as it would exist in an electrolysis stack. Details of the model geometry are specific to a stack that was fabricated by Ceramatec2, Inc. and tested at the Idaho National Laboratory. Mass, momentum, energy, and species conservation and transport are provided via the core features of the commercial CFD code FLUENT2. A solid-oxide fuel cell (SOFC) model adds the electrochemical reactions and loss mechanisms and computation of the electric field throughout the cell. The FLUENT SOFC user-defined subroutine was modified for this work to allow for operation in the SOEC mode. Model results provide detailed profiles of temperature, Nernst potential, operating potential, anode-side gas composition, cathode-side gas composition, current density and hydrogen production over a range of stack operating conditions. Mean model results are shown to compare favorably with experimental results obtained from an actual ten-cell stack tested at INL.

Grant L. Hawkes; James E. O'Brien; Carl M. Stoots; J. Stephen Herring

2005-10-01T23:59:59.000Z

290

PC/FRAM, Version 3. 2 User Manual  

SciTech Connect (OSTI)

This manual describes the use of version 3.2 of the PC/FRAM plutonium isotopic analysis software developed in the Safeguards Science and Technology Group, NE-5, Nonproliferation and International Security Division Los Alamos National Laboratory. The software analyzes the gamma ray spectrum from plutonium-bearing items and determines the isotopic distribution of the plutonium 241Am content and concentration of other isotopes in the item. The software can also determine the isotopic distribution of uranium isotopes in items containing only uranium. The body of this manual descnies the generic version of the code. Special facility-specific enhancements, if they apply, will be described in the appendices. The information in this manual applies equally well to version 3.3, which has been licensed to ORTEC. The software can analyze data that is stored in a file on disk. It understands several storage formats including Canberra's S1OO format, ORTEC'S chn' and SPC' formats, and several ASCII text formats. The software can also control data acquisition using an MCA and then store the results in a file on disk for later analysis or analyze the spectrum directly after the acquisition. The software currently only supports the control of ORTEC MCB'S. Support for Canbema's Genie-2000 Spectroscopy Systems will be added in the future. Support for reading and writing CAM files will also be forthcoming. A versatile parameter fde database structure governs all facets of the data analysis. User editing of the parameter sets allows great flexibility in handling data with different isotopic distributions, interfering isotopes, and different acquisition parameters such as energy calibration, and detector type. This manual is intended for the system supervisor or the local user who is to be the resident expert. Excerpts from this manual may also be appropriate for the system operator who will routinely use the instrument.

Kelley, T.A.; Sampson, T.E.

1999-02-23T23:59:59.000Z

291

PC/FRAM, Version 3.2 User Manual  

SciTech Connect (OSTI)

This manual describes the use of version 3.2 of the PC/FRAM plutonium isotopic analysis software developed in the Safeguards Science and Technology Group, NE-5, Nonproliferation and International Security Division Los Alamos National Laboratory. The software analyzes the gamma ray spectrum from plutonium-bearing items and determines the isotopic distribution of the plutonium 241Am content and concentration of other isotopes in the item. The software can also determine the isotopic distribution of uranium isotopes in items containing only uranium. The body of this manual descnies the generic version of the code. Special facility-specific enhancements, if they apply, will be described in the appendices. The information in this manual applies equally well to version 3.3, which has been licensed to ORTEC. The software can analyze data that is stored in a file on disk. It understands several storage formats including Canberra's S1OO format, ORTEC'S `chn' and `SPC' formats, and several ASCII text formats. The software can also control data acquisition using an MCA and then store the results in a file on disk for later analysis or analyze the spectrum directly after the acquisition. The software currently only supports the control of ORTEC MCB'S. Support for Canbema's Genie-2000 Spectroscopy Systems will be added in the future. Support for reading and writing CAM files will also be forthcoming. A versatile parameter fde database structure governs all facets of the data analysis. User editing of the parameter sets allows great flexibility in handling data with different isotopic distributions, interfering isotopes, and different acquisition parameters such as energy calibration, and detector type. This manual is intended for the system supervisor or the local user who is to be the resident expert. Excerpts from this manual may also be appropriate for the system operator who will routinely use the instrument.

Kelley, T.A.; Sampson, T.E.

1999-02-23T23:59:59.000Z

292

METHANE DE-NOX FOR UTILITY PC BOILERS  

SciTech Connect (OSTI)

The primary focus for the project continues to be on developing a PC PREHEAT system design suitable for use with caking coals and readying the 100 MMBtu/h CBTF for testing with noncaking PRB coal. During the current quarter, twenty-two pilot tests were conducted with Central Appalachian (CA) caking coal. The objective for these tests was to achieve continuous operation of the pilot system at its design coal feed rate of 156 lb/h, without plugging or agglomeration in the combustor. One combustor air distribution method tested achieved continuous operation at 110 lb/hr, and inspection of the combustor afterward indicated that this method has potential to solve the caking problem. The NOx results from the pilot caking coal runs indicate that even greater NOx reduction is possible with CA coal than with the PRB coal tested, to levels near 100 ppmv or lower at 4-6% exit oxygen. It was therefore decided to conduct additional pilot tests of the air distribution method to determine how to incorporate this into a workable CA combustor design. Based on current weather and manpower restrictions at the site, this pilot testing is expected to be started in February. The design for the 100 MMBtu/h unit for PRB testing in the CBTF was completed and fabrication and installation started during the quarter. While significant progress has been made in the installation of the unit, weather and combustor fabrication delays are expected to move the start of large-scale testing with PRB coal into February, which will push the project completion date beyond the current 3/30/04 end date. GTI is in the process of developing a revised project schedule and estimated cost to complete.

Bruce Bryan; Joseph Rabovitser; Serguei Nester; Stan Wohadlo

2004-02-06T23:59:59.000Z

293

Nuclear Debate  

Science Journals Connector (OSTI)

Nuclear Debate ... This month, the Senate will consider the nominations of two women to serve on the Nuclear Regulatory Commission. ... Svinicki is a nuclear engineer with experience in the Department of Energy’s nuclear energy programs. ...

JEFF JOHNSON

2012-06-11T23:59:59.000Z

294

Conceptual Design of Oxygen-Based PC Boiler  

SciTech Connect (OSTI)

Coal is presently the world's primary fuel for generating electrical power and, being more abundant and less expensive than oil or natural gas, is expected to continue its dominance into the future. Coal, however, is more carbon intensive than natural gas and oil and consequently coal-fired power plants are large point source emitters of carbon dioxide (CO{sub 2}). Since CO{sub 2} is a greenhouse gas, which may have an adverse impact on the world's climate/weather patterns, studies have been conducted to determine the feasibility and economic impact of capturing power plant CO{sub 2} emissions for pipeline transport to a sequestration/storage site. The stack gas that exhausts from a modern coal-fired power plant typically contains about 15% CO{sub 2} on a dry volume basis. Although there are numerous processes available for removing CO{sub 2} from gas streams, gas scrubbing with amine solvent is best suited for this application because of the large gas volumes and low CO{sub 2} concentrations involved. Unfortunately the energy required to regenerate the solvent for continued use as a capturing agent is large and imposes a severe energy penalty on the plant. In addition this ''back end'' or post combustion cleanup requires the addition of large vessels, which, in retrofit applications, are difficult to accommodate. As an alternative to post combustion scrubbing, Foster Wheeler (FW) has proposed that the combustion process be accomplished with oxygen rather than air. With all air nitrogen eliminated, a CO{sub 2}-water vapor rich flue gas will be generated. After condensation of the water vapor, a portion of the flue gas will be recirculated back to the boiler to control the combustion temperature and the balance of the CO{sub 2} will be processed for pipeline transport. This proposed oxygen-carbon dioxide (O{sub 2}/CO{sub 2}) combustion process eliminates the need for CO{sub 2} removal/separation and reduces the cost of supplying a CO{sub 2} rich stream for sequestration. FW has developed a conceptual design of an O{sub 2} fired boiler to determine overall plant performance and economics. Five subtasks were conducted: (1) a literature review, (2) a system design and analysis, (3) a low NOx burner design and analysis, (4) a furnace and heat recovery area design analysis, and (5) an economic analysis. The objective of the literature search is to locate any data/information relevant to the Oxygen-Based PC Boiler conceptual design. The objective of the system design and analysis task is to optimize the PC boiler plant by maximizing system efficiency within practical considerations. Simulations of the oxygen-fired plant with CO{sub 2} sequestration were conducted using Aspen Plus and were compared to a reference air-fired 460 MW plant. Flue gas recycle is used in the O{sub 2}-fired PC to control the flame temperature. Parametric runs were made to determine the effect of flame temperature on system efficiency and required waterwall material and thickness. The degree of improvement on system efficiency of various modifications including hot gas recycle, purge gas recycle, flue gas feedwater recuperation, and recycle purge gas expansion were investigated. The selected O{sub 2}-fired design case has a system efficiency of 30.6% compared to the air-fired system efficiency of 36.7%. The design O{sub 2}-fired case requires T91 waterwall material and has a waterwall surface area of only 65% of the air-fired reference case. The objective of the low NOx burner design and analysis task is to optimize the burner design to ensure stable ignition, to provide safe operation, and to minimize pollutant formation. The burners were designed and analyzed using the Fluent CFD computer program. Four burner designs were developed: (1) with no OFG and 65% flue gas recycle, (2) with 20% OFG and 65% flue gas recycle, (3) with no OFG and 56% flue gas recycle and (4) with 20% OFG and 56% flue gas recycle. A 3-D Fluent simulation was made of a single wall-fired burner and horizontal portion of the furnace from the wall to the center. Without primary gas sw

Andrew Seltzer; Zhen Fan

2005-09-01T23:59:59.000Z

295

[Nuclear theory: Annual report  

SciTech Connect (OSTI)

This report discusses topics on : nuclear structure models; algebraic models of hadronic structure; nuclear reactions; hot rotating nuclei; chaos in nuclei; signatures of the quark-gluon plasma; hadronic spectroscopy; octupole collectivity in nuclei; finite-temperature methods for the many-body problem; and classical limit of algebraic hamiltonians. (LSP)

Iachello, F.; Alhassid, Y.; Kusnezov, D.

1991-12-31T23:59:59.000Z

296

(Nuclear theory: Annual report)  

SciTech Connect (OSTI)

This report discusses topics on : nuclear structure models; algebraic models of hadronic structure; nuclear reactions; hot rotating nuclei; chaos in nuclei; signatures of the quark-gluon plasma; hadronic spectroscopy; octupole collectivity in nuclei; finite-temperature methods for the many-body problem; and classical limit of algebraic hamiltonians. (LSP)

Iachello, F.; Alhassid, Y.; Kusnezov, D.

1991-01-01T23:59:59.000Z

297

Modeling Alloy 22 general corrosion in the Yucca Mountain nuclear waste repository  

Science Journals Connector (OSTI)

This paper presents the general corrosion model used by the Yucca Mountain Project to account for general corrosion degradation of the Alloy 22 waste package outer barrier. The general corrosion rates were det...

Kevin G. Mon; Brvan E. Bullard; Fred Hua; Gopal C. De

2008-01-01T23:59:59.000Z

298

Workforce Transition Model for DOE-AL non-nuclear reconfiguration  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory (PNL) was tasked by the US Department of Energy Albuquerque Field Office (DOE-AL) to develop a workforce assessment and transition planning tool to support integrated decision making at a single DOE installation. The planning tool permits coordinated, integrated workforce planning to manage growth, decline, or transition within a DOE installation. The tool enhances the links and provides commonality between strategic, programmatic, and operations planners and human resources. Successful development and subsequent complex-wide implementation of the model will also facilitate planning at the national level by enforcing a consistent format on data that are now collected by installations in corporate-specific formats that are not amenable to national-level analyses. The workforce assessment and transition planning tool consists of two components: the Workforce Transition Model and the Workforce Budget Constraint Model. The Workforce Transition Model, the preponderant of the two, assists decision makers to identify and evaluates alternatives for transitioning the current workforce to meet the skills required to support projected workforce requirements. The Workforce Budget Constraint Model helps estimate the number of personnel that will be affected given a workforce budget increase or decrease and assists in identifying how the corresponding hiring or layoffs should be distributed across the common occupational classification system (COCS) occupations. The conceptual models and the computer implementation are described.

Stahlman, E.J.; Lewis, R.E.

1993-10-01T23:59:59.000Z

299

Advanced Modeling and Evaluation of the Response of Base-Isolated Nuclear Facility Structures to Vertical Earthquake Excitation  

E-Print Network [OSTI]

isolated nuclear power plant designs in Japan and the UnitedJapan were also affected by these events, including the Onagawa nuclear powerNuclear Power Plant In 1980, construction began on the Kashiwazaki-Kariwa NPP in Niigata Prefecture, on the west coast of Honshu, Japan.

Keldrauk, Eric Scott

2012-01-01T23:59:59.000Z

300

pc107334 1..18 - tpc.112.107334.full.pdf  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

pc107334 1..18 - tpc.112.107334.full.pdf pc107334 1..18 - tpc.112.107334.full.pdf http://www.plantcell.org/content/early/2013/01/30/tpc.112.107334.full.p... 1 of 19 3/12/2013 10:14 AM pc107334 1..18 - tpc.112.107334.full.pdf http://www.plantcell.org/content/early/2013/01/30/tpc.112.107334.full.p... 2 of 19 3/12/2013 10:14 AM pc107334 1..18 - tpc.112.107334.full.pdf http://www.plantcell.org/content/early/2013/01/30/tpc.112.107334.full.p... 3 of 19 3/12/2013 10:14 AM pc107334 1..18 - tpc.112.107334.full.pdf http://www.plantcell.org/content/early/2013/01/30/tpc.112.107334.full.p... 4 of 19 3/12/2013 10:14 AM pc107334 1..18 - tpc.112.107334.full.pdf http://www.plantcell.org/content/early/2013/01/30/tpc.112.107334.full.p... 5 of 19 3/12/2013 10:14 AM pc107334 1..18 - tpc.112.107334.full.pdf http://www.plantcell.org/content/early/2013/01/30/tpc.112.107334.full.p...

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Study of degenerate parabolic system modeling the hydrogen displacement in a nuclear waste repository  

E-Print Network [OSTI]

Our goal is the mathematical analysis of a two phase (liquid and gas) two components (water and hydrogen) system modeling the hydrogen displacement in a storage site for radioactive waste. We suppose that the water is only in the liquid phase and is incompressible. The hydrogen in the gas phase is supposed compressible and could be dissolved into the water with the Henry's law. The flow is described by the conservation of the mass of each components. The model is treated without simplified assumptions on the gas density. This model is degenerated due to vanishing terms. We establish an existence result for the nonlinear degenerate parabolic system based on new energy estimate on pressures.

Caro, Florian; Saad, Mazen

2012-01-01T23:59:59.000Z

302

CCS, Nuclear Power and Biomass An Assessment of Option Triangle under Global Warming Mitigation Policy by an Integrated Assessment Model MARIA-23  

Science Journals Connector (OSTI)

Abstract It is well understood that the global climate change caused by the increase of greenhouse gas (GHG) emission would be a serious barrier towards the sustainable development. Nuclear power, CCS and biomass have been regarded as the major options in the GHG mitigation policy. However, since the social acceptance of nuclear power expansion has seriously been changed after the gigantic earthquake on March 11, 2011 followed by the Fukushima Daiichi nuclear power station accident, the energy policy makers are forced to consider both the global warming and the decline of nuclear power simultaneously. This study attempts to address the following key questions: (1) how much additional costs or decline of production will be needed when nuclear power expansion is limited under the GHG emission control policies and (2) to what extent the potential of the biomass and CCS could compensate for the nuclear power reductions. We expand an integrated assessment model, MARIA-23 (Multiregional Approach for Resource and Industry Allocation) to deal with the CCS options and biomass options taking into account the additional carbon emission by cultivation. The simulation results show the interrelationships of the carbon mitigation contributions of the above three major options under various scenarios.

Shunsuke Mori; Keisuke Miyaji; Kazuhisa Kamegai

2013-01-01T23:59:59.000Z

303

Nuclear Data | More Science | ORNL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Computer Science Computer Science Theory, Modeling and Simulation Cyber Security Bioinformatics Climate & Environment Systems Biology Neutron Data Analysis and Visualization Nuclear Data Nuclear Systems Modeling and Simulation Supercomputing and Computation More Science Home | Science & Discovery | More Science | Computer Science | Nuclear Data SHARE Nuclear Data Nuclear Data ORNL is a recognized, international leader in nuclear data research and development (R&D) to support nuclear applications analyses. For more than 40 years, ORNL has provided neutron resonance region nuclear data evaluations to the US Evaluated Nuclear Data File (ENDF/B) database, and many of the key ORNL resonance evaluations have also been adopted by international nuclear databases in Europe, Japan, China, and Russia. ORNL

304

A Network Model and Computational Approach Mo Supply Chain for Nuclear Medicine  

E-Print Network [OSTI]

, a radioactive isotope is bound to a pharmaceutical that is injected into the patient and travels to the site or organ of interest. The gamma rays emitted by the radioactive decay of the isotope are then used isotopes is 3.7 billion US$ per year (Kahn (2008)). Ladimer S. Nagurney and Anna Nagurney A Network Model

Nagurney, Anna

305

Is there a need for hydrological modelling in decision support systems for nuclear emergencies  

Science Journals Connector (OSTI)

......related to the aquatic modelling in...Pripyat-Dnieper aquatic system after...radionuclides on a lake ecosystem and its integration...system for the restoration of radionuclides...PripyatDnieper aquatic system after...radionuclides on a lake ecosystem and its integration...system for the restoration of radionuclides......

W. Raskob; R. Heling; M. Zheleznyak

2004-06-01T23:59:59.000Z

306

Creating geometry and mesh models for nuclear reactor core geometries using a lattice hierarchy-based approach.  

SciTech Connect (OSTI)

Nuclear reactor cores are constructed as rectangular or hexagonal lattices of assemblies, where each assembly is itself a lattice of fuel, control, and instrumentation pins, surrounded by water or other material that moderates neutron energy and carries away fission heat. We describe a system for generating geometry and mesh for these systems. The method takes advantage of information about repeated structures in both assembly and core lattices to simplify the overall process. The system allows targeted user intervention midway through the process, enabling modification and manipulation of models for meshing or other purposes. Starting from text files describing assemblies and core, the tool can generate geometry and mesh for these models automatically as well. Simple and complex examples of tool operation are given, with the latter demonstrating generation of meshes with 12 million hexahedral elements in less than 30 minutes on a desktop workstation, using about 4 GB of memory. The tool is released as open source software as part of the MeshKit mesh generation library.

Tautges, T. J.; Jain, R.; Mathematics and Computer Science

2010-01-01T23:59:59.000Z

307

Nuclear shape coexistence: A study of the even-even Hg isotopes using the interacting boson model with configuration mixing  

E-Print Network [OSTI]

Background: The Po, Pb, Hg, and Pt region is known for the presence of coexisting structures that correspond to different particle-hole configurations in the Shell Model language or equivalently to nuclear shapes with different deformation. Purpose: We intend to study the configuration mixing phenomenon in the Hg isotopes and to understand how different observables are influenced by it. Method: We study in detail a long chain of mercury isotopes, $^{172-200}$Hg, using the interacting boson model with configuration mixing. The parameters of the Hamiltonians are fixed through a least square fit to the known energies and absolute B(E2) transition rates of states up to $3$ MeV. Results: We obtained the IBM-CM Hamiltonians and we calculate excitation energies, B(E2)'s, quadrupole shape invariants, wave functions, isotopic shifts, and mean field energy surfaces. Conclusions: We obtain a fairly good agreement with the experimental data for all the studied observables and we conclude that the Hamiltonian and the states we obtain constitute a good approximation to the Hg isotopes.

J. E. Garcia-Ramos; K. Heyde

2013-12-17T23:59:59.000Z

308

Directory of Energy Information Administration models, 1990  

SciTech Connect (OSTI)

This directory revises and updates the Directory of Energy Information Administration Models, DOE/EIA-0293(89), Energy Information Administration (EIA), US Department of Energy, May 1989. The major changes are the inclusion of the Building Energy End-Use Model (BEEM-PC), Residential Energy End-Use Model (REEM-PC), the Refinery Yield Model Spreadsheet System (RYMSS-PC), and the Capital Stock Model (CAPSTOCK-PC). Also, the following models have been inactivated: Energy Disaggregated Input-Output Model (EDIO), Household Model of Energy (HOME3-PC), Commercial Sector Energy Model (CSEM-PC), Outer Continental Shelf Oil and Gas Supply Model (OCSM), and the Stock Module of the Intermediate Future Forecasting System (STOCK). This directory contains descriptions about each basic and auxiliary model, including the title, acronym, purpose, and type, followed by more detailed information on characteristics, uses, and requirements. For developing models, limited information is provided. Sources for additional information are identified. Included in this directory are 38 EIA models active as of March 1, 1990, as well as the PC-AEO Forecasting Model Overview and the three Subsystems for the Short-Term Integrated Forecasting System (STIFS) Model. Models that run on personal computers are identified by PC'' as part of the acronym.

Not Available

1990-06-04T23:59:59.000Z

309

A transient flow model of compressible gas mixtures in a nuclear fuel processing plant  

SciTech Connect (OSTI)

A model was developed to predict mixture concentration profiles in a subatmospheric mixture of hydrogen, nitrogen, and oxygen during valve-switching between a process line and an atmospheric vent line. The switching event allows air in-leakage to the system during the period in which the routing valves are open. Hydrogen and oxygen concentrations must be predicted to assess the potential for developing combustible mixtures in the system. The model consists of a one-dimensional finite-difference representation of the transient momentum and mass conservation equations, associated constitutive relationships and an equation-of-state for compressible gas. The resulting equation set was solved with Advanced Continuous Simulation Language (ACSL).

Farman, R.F.; Brown, R.A.

1989-02-16T23:59:59.000Z

310

Model of sludge behavior in nuclear plant steam generators. Final report  

SciTech Connect (OSTI)

The accumulation of large amounts of sludge in pressurized water reactor steam generators is thought to be a cause of accelerated corrosion by trace impurities which concentrate in such deposits. Based on fundamental principles, this study develops a mathematical model for predicting the behavior (e.g., deposition and reentrainment) of sludge in steam generators. The calculated sludge behavior shows good agreement with the limited amount of experimental data available. The results suggest that the continued accumulation of sludge on the tubesheet might be preventable, and that if it could be, the incoming sludge would be removed by blowdown. An analysis of the uncertainties in the model led to suggested priorities for further analytical and experimental work to gain a better understanding of sludge behavior. 29 refs., 12 figs., 15 tabs.

Beal, S.K.; Chen, J.H.

1986-06-01T23:59:59.000Z

311

Derivation of models for nuclear weapon terrorist arming and detonation risk analysis  

SciTech Connect (OSTI)

This report investigates "use control" for the on-site arming and detonation, by terrorists, of stored weapon systems. We investigate both components of weapon "use control", which we define as: (1) weapon "use denial" * that we model as a probability, Pj (denial), that represents the chances that terrorists attempting to arm a type j weapon will commit a non-recoverable error, and (2) weapon "use delay" that we model as a random variable, Tj , that represents the arming delay imposed by the use control features of a type j weapon, before detonation can occur. Using information pertaining to the physical security system at a storage site, the postulated terrorist attack force size, and simulated combat engagement outcomes, we formulate the frequency, fj , and probability, P(dj ), of on-site detonation, for generic weapon types j. We derive a model that disjoins the performance of site physical security, from that for weapon use control, if the use control random variable Tj has a Uniform or histogram distribution. This is an especially significant result where most complex distributions can be adequately approximated with a histogram. Hence, we can conduct combat simulations to obtain the physical security performance of a specific storage site independent of the use control features associated with specific weapon types that are stored, or might be stored, at the site. In turn, we can obtain the use control performance for various weapon types, independent of where they are stored and the physical security systems surrounding them. Our models can then mathematically combine physical security performance and weapon use control performance for any combination of storage facility and weapon type.

Parziale, A A

1998-03-01T23:59:59.000Z

312

A long term radiological risk model for plutonium-fueled and fission reactor space nuclear system  

SciTech Connect (OSTI)

This report describes the optimization of the RISK III mathematical model, which provides risk assessment for the use of a plutonium-fueled, fission reactor in space systems. The report discusses possible scenarios leading to radiation releases on the ground; distinctions are made for an intact reactor and a dispersed reactor. Also included are projected dose equivalents for various accident situations. 54 refs., 31 figs., 11 tabs. (TEM)

Bartram, B.W.; Dougherty, D.K.

1987-01-01T23:59:59.000Z

313

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network [OSTI]

Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

314

Pentafluorophenoxy Boron Subphthalocyanine (F5BsubPc) as a Multifunctional Material for Organic Photovoltaics  

Science Journals Connector (OSTI)

We have demonstrated that pentafluoro phenoxy boron subphthalocyanine (F5BsubPc) can function as either an electron donor or an electron acceptor layer in a planar heterojunction organic photovolatic (PHJ OPV) cell. ...

Graham E. Morse; Jeremy L. Gantz; K. Xerxes Steirer; Neal R. Armstrong; Timothy P. Bender

2013-12-27T23:59:59.000Z

315

Improved color coordinates of green monochromatic pc-LED capped with a band-pass filter  

Science Journals Connector (OSTI)

This study introduces a “greener” green monochromatic phosphor-converted light-emitting diode (pc-LED) using a band-pass filter (BPF) combined with a long-pass dichroic...

Oh, Ji Hye; Yang, Su Ji; Sung, Yeon-Goog; Do, Young Rag

2013-01-01T23:59:59.000Z

316

Beta.-glucosidase coding sequences and protein from orpinomyces PC-2  

DOE Patents [OSTI]

Provided is a novel .beta.-glucosidase from Orpinomyces sp. PC2, nucleotide sequences encoding the mature protein and the precursor protein, and methods for recombinant production of this .beta.-glucosidase.

Li, Xin-Liang (Athens, GA); Ljungdahl, Lars G. (Athens, GA); Chen, Huizhong (Lawrenceville, GA); Ximenes, Eduardo A. (Athens, GA)

2001-02-06T23:59:59.000Z

317

Predicted Solar Neutrino Rates in the Q-Nuclear Solar Model  

Science Journals Connector (OSTI)

It is been shown previoulsy that the existence of a tiny abundance of nuclei which have an additional embedded hadronic particle, Q-nuclei, can solve the solar-neutrino problem. We present here detailed predictions of solar-neutrino detection rates for detectors of Cl37, Ga71, and In115. It is found that, while Q-nuclei could reduce the Cl37 detection rate from that of the standard model to the experimental value, they would also produce a dramatic increase in the rates for the Ga71 and In115 detectors.

B. Sur and R. N. Boyd

1985-02-04T23:59:59.000Z

318

Particle number fluctuations in nuclear collisions within excluded volume hadron gas model  

E-Print Network [OSTI]

The multiplicity fluctuations are studied in the van der Waals excluded volume hadron-resonance gas model. The calculations are done in the grand canonical ensemble within the Boltzmann statistics approximation. The scaled variances for positive, negative and all charged hadrons are calculated along the chemical freeze-out line of nucleus-nucleus collisions at different collision energies. The multiplicity fluctuations are found to be suppressed in the van der Waals gas. The numerical calculations are presented for two values of hard-core hadron radius, $r=0.3$ fm and 0.5 fm, as well as for the upper limit of the excluded volume suppression effects.

M. I. Gorenstein; M. Hauer; D. O. Nikolajenko

2007-02-26T23:59:59.000Z

319

Three-dimensional Computational Fluid Dynamics (CFD) modeling of dry spent nuclear fuel storage canisters  

SciTech Connect (OSTI)

One of the interim storage configurations being considered for aluminum-clad foreign research reactor fuel, such as the Material and Testing Reactor (MTR) design, is in a dry storage facility. To support design studies of storage options, a computational and experimental program was conducted at the Savannah River Site (SRS). The objective was to develop computational fluid dynamics (CFD) models which would be benchmarked using data obtained from a full scale heat transfer experiment conducted in the SRS Experimental Thermal Fluids Laboratory. The current work documents the CFD approach and presents comparison of results with experimental data. CFDS-FLOW3D (version 3.3) CFD code has been used to model the 3-dimensional convective velocity and temperature distributions within a single dry storage canister of MTR fuel elements. For the present analysis, the Boussinesq approximation was used for the consideration of buoyancy-driven natural convection. Comparison of the CFD code can be used to predict reasonably accurate flow and thermal behavior of a typical foreign research reactor fuel stored in a dry storage facility.

Lee, S.Y.

1997-06-01T23:59:59.000Z

320

Fast-neutron total and scattering cross sections of sup 58 Ni and nuclear models  

SciTech Connect (OSTI)

An extensive experimental and theoretical study of the fast-neutron interaction with {sup 58}Ni was undertaken. The neutron total cross sections of {sup 58}Ni were measured from {approx} 1 to > 10 MeV using white source techniques. Differential neutron elastic-scattering cross sections were measured from {approx} 4.5 to 10 MeV at {approx} 0.5 Mev intervals with {ge} 75 differential values per distribution. Differential neutron inelastic-scattering cross sections were measured, corresponding to fourteen levels with excitations up to {approx} 4.8 Mev. The measured results, combined with lower-energy values previously obtained at this laboratory and with relevant values available in the literature, were interpreted in terms of optical-statistical, dispersive-optical and coupled-channels models using both vibrational and rotational coupling schemes. The physical implications of the experimental results and their interpretation are discussed. The considerations are being extended to collective vibrational nuclei generally, exploring the potential for utilizing electro-magnetic matrix elements, deduced from experiment or predicted by the shell model, to determine the strengths of the neutron interaction. Detailed aspects of this work are given in the Laboratory Report, ANL/NDM-120 (in press). 9 refs., 10 figs.

Smith, A.B.; Guenther, P.T.; Whalen, J.F.; Lawson, R.D.; Chiba, S.

1991-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Absolute nuclear material assay  

DOE Patents [OSTI]

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-05-15T23:59:59.000Z

322

Nuclear Returns  

Science Journals Connector (OSTI)

Nuclear Returns ... For the first time since 1978, the Nuclear Regulatory Commission has given the green light for a new U.S. nuclear power plant. ... NRC granted a license to Southern Co. to build and operate twin 1,100-MW reactors adjacent to two operating nuclear power plants at its Vogtle nuclear facility, near Waynesboro, Ga. ...

JEFF JOHNSON

2012-02-19T23:59:59.000Z

323

Cold-cap reactions in vitrification of nuclear waste glass: experiments and modeling  

SciTech Connect (OSTI)

Cold-cap reactions are multiple overlapping reactions that occur in the waste-glass melter during the vitrification process when the melter feed is being converted to molten glass. In this study, we used differential scanning calorimetry (DSC) to investigate cold-cap reactions in a high-alumina high-level waste melter feed. To separate the reaction heat from both sensible heat and experimental instability, we employed the run/rerun method, which enabled us to define the degree of conversion based on the reaction heat and to estimate the heat capacity of the reacting feed. Assuming that the reactions are nearly independent and can be approximated by the nth order kinetics, we obtained the kinetic parameters using the Kissinger method combined with least squares analysis. The resulting mathematical simulation of the cold-cap reactions provides a key element for the development of an advanced cold-cap model.

Chun, Jaehun [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Pierce, David A. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Pokorny, Richard [Inst. of Chemical Technology, Prague (Czech Republic); Hrma, Pavel R. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Pohang Univ. of Science and Techology (Korea, Republic of)

2013-05-10T23:59:59.000Z

324

Sliding mode observer design for a PWR to estimate the xenon concentration & delayed neutrons precursor density based on the two point nuclear reactor model  

Science Journals Connector (OSTI)

Abstract One of the important operations in nuclear power plants is load-following in which imbalance of axial power distribution induces xenon oscillations. These oscillations must be maintained within acceptable limits otherwise the nuclear power plant could become unstable. Therefore, bounded xenon oscillation considered to be a constraint for the load-following operation. In other hands, precursors produce delayed neutrons which are most important in control of nuclear reactor, but xenon concentration & precursor density cannot be measured directly. In this paper, non-linear sliding mode observer which has the robust characteristics facing the parameters uncertainties and disturbances is proposed based on the two point nuclear reactor model to estimate the xenon concentration & delayed neutron precursor density of the Pressurized-Water Nuclear Reactor (PWR) using reactor power measurement. The stability analysis is given by means Lyapunov approach, thus the system is guaranteed to be stable within a large range. The employed method is easy to implement in practical applications. This estimation is done taking into account the effects of reactivity feedback due to temperature and xenon concentration. Simulation results clearly show that the sliding mode observer follows the actual system variables accurately and is satisfactory in the presence of the parameters uncertainties & disturbances.

G.R. Ansarifar; M.H. Esteki; M. Arghand

2015-01-01T23:59:59.000Z

325

Thermodynamic properties and shear viscosity over entropy density ratio of nuclear fireball in a quantum-molecular dynamics model  

E-Print Network [OSTI]

Thermodynamic and transport properties of nuclear fireball created in the central region of heavy-ion collisions below 400 MeV/nucleon are investigated within the isospin-dependent quantum molecular dynamic (IQMD) model. These properties including the density, temperature, chemical potential, entropy density ($s$) and shear viscosity ($\\eta$), are calculated by a generalized hot Thomas Fermi formulism and a parameterized function, which was developed by Danielewicz. As the collision goes on, a transient minimal $\\eta/s=5/4\\pi-10/4\\pi$ occurs in the largest compression stage. Besides, the relationship of $\\eta/s$ to temperature ($T$) in the freeze-out stage displays a local minimum which is about 9-20 times $1/4\\pi$ around $T$ = 8-12 MeV, which can be argued as indicative of a liquid gas phase transition. In addition, the influences of nucleon-nucleon (NN) cross section ($\\sigma_{NN}$) and symmetry energy coefficient ($C_{s}$) are also discussed, and it is found that the results are sensitive to $\\sigma_{NN}$ but not to $C_{s}$.

C. L. Zhou; Y. G. Ma; D. Q. Fang; G. Q. Zhang

2012-12-20T23:59:59.000Z

326

Utilization of a finite element model to verify spent nuclear fuel storage rack welds  

SciTech Connect (OSTI)

Elastic and plastic finite element analyses were performed for the inner tie block assembly of a 25 port fuel rack designed for installation at the Idaho National Engineering and Environmental Laboratory (INEEL) Idaho Chemical Processing Plant (ICPP). The model was specifically developed to verify the adequacy of certain welds joining components of the fuel storage rack assembly. The work scope for this task was limited to an investigation of the stress levels in the inner tie welds when the rack was subjected to seismic loads. Structural acceptance criteria used for the elastic calculations performed were as defined by the rack`s designer. Structural acceptance criteria used for the plastic calculations performed as part of this effort were as defined in Subsection NF and Appendix F of Section III of the ASME Boiler and Pressure Vessel Code. The results confirm that the welds joining the inner tie block to the surrounding rack structure meet the acceptance criteria. The analysis results verified that the inner tie block welds should be capable of transferring the expected seismic load without structural failure.

Nitzel, M.E.

1998-07-01T23:59:59.000Z

327

Nuclear Fusion  

Science Journals Connector (OSTI)

Although not yet developed at the commercial stage, nuclear fusion technology is still being considered as a ... used in nuclear warfare. Since research in nuclear fusion for the production of energy started abou...

Ricardo Guerrero-Lemus; José Manuel Martínez-Duart

2013-01-01T23:59:59.000Z

328

Nuclear Nonproliferation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Nonproliferation As more countries embrace nuclear power as a cost-effective and clean alternative to fossil fuels, the need exists to ensure that the nuclear fuel cycle is...

329

Nuclear Engineering Nuclear Criticality Safety  

E-Print Network [OSTI]

Nuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear, and neutron spectra. The NE nuclear criticality safety (NCS) capabilities are based on a staff with decades

Kemner, Ken

330

Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).  

SciTech Connect (OSTI)

This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

2010-09-01T23:59:59.000Z

331

NUCLEAR REACTORS.  

E-Print Network [OSTI]

??Nuclear reactors are devices containing fissionable material in sufficient quantity and so arranged as to be capable of maintaining a controlled, self-sustaining NUCLEAR FISSION chain… (more)

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

332

nuclear reactor  

Science Journals Connector (OSTI)

...a complex atomic apparatus used to obtain energy from nuclear fission chain reaction. Used to produce nuclear energy, radioactive isotopes, and artificial elements.... atomic pile ...

2009-01-01T23:59:59.000Z

333

Nuclear Energy  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Energy Idaho National Laboratory is the Department of Energy's lead nuclear energy research and development facility. Building upon its legacy responsibilities,...

334

Nuclear Hydrogen  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Error Error Nuclear Hydrogen - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Hydrogen - RCC * Increasing your portlet timeout setting. *...

335

Nuclear Physics  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

336

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Technology Technology Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Bookmark and Share The NE system engineering activities involve the conceptual design, through the manufacturing and qualification testing of the Mk-IV and Mk-V electrorefiner and the cathode processor. These first-of-a-kind large scale

337

METHANE de-NOX for Utility PC Boilers  

SciTech Connect (OSTI)

Large-scale PRB testing during the current quarter was cut short due to the inability of the coal mill to meet the 85 MMBtu/h design firing rate. The project was therefore redirected toward design, installation and testing of the 85-million Btu/h preheater for bituminous coal. Based on extensive pilot-scale testing completed earlier in the project, 2-D modeling and preliminary design activities were started based on the use of staged, annular protective air films to control temperature and prevent deposition on the preheater walls. A total of 14 2-D modeling cases were completed for the modified preheater for bituminous coal. The preheater concept modeled was based on an expanding preheater chamber where the diameter of the chamber is increased in steps along its length and annular cooling/protective air is introduced at each step. A process flow diagram for the bituminous coal preheating system and a preliminary preheater design drawing were developed based on the modeling results. A project schedule to complete design, installation and testing of the 85 MMBtu/h bituminous coal preheating system before the end of December was also developed.

Bruce Bryan; Joseph Rabovitser; Serguei Nester; Stan Wohadlo

2004-09-30T23:59:59.000Z

338

Temperature dependence of single-particle properties in nuclear and neutron matter in the Dirac-Brueckner-Hartree-Fock model  

E-Print Network [OSTI]

The understanding of the interaction of nucleons in nuclear and neutron-rich matter at non-zero temperature is important for a variety of applications ranging from heavy-ion collisions to nuclear astrophysics. In this paper we apply the Dirac-Brueckner-Hartree-Fock method along with the Bonn B nucleon-nucleon potential to predict single-particle properties in symmetric nuclear matter and pure neutron matter at finite temperature. It is found that temperature effects are generally small but can be significant at low density and momentum.

Sammarruca, Francesca

2009-01-01T23:59:59.000Z

339

Temperature dependence of single-particle properties in nuclear and neutron matter in the Dirac-Brueckner-Hartree-Fock model  

E-Print Network [OSTI]

The understanding of the interaction of nucleons in nuclear and neutron-rich matter at non-zero temperature is important for a variety of applications ranging from heavy-ion collisions to nuclear astrophysics. In this paper we apply the Dirac-Brueckner-Hartree-Fock method along with the Bonn B nucleon-nucleon potential to predict single-particle properties in symmetric nuclear matter and pure neutron matter at finite temperature. It is found that temperature effects are generally small but can be significant at low density and momentum.

Francesca Sammarruca

2009-08-13T23:59:59.000Z

340

Nuclear Matter and Nuclear Dynamics  

E-Print Network [OSTI]

Highlights on the recent research activity, carried out by the Italian Community involved in the "Nuclear Matter and Nuclear Dynamics" field, will be presented.

M Colonna

2009-02-26T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Relationship between the PC and AL indices during repetitive bay-like magnetic disturbances in the auroral zone  

Science Journals Connector (OSTI)

To study the relations of the polar cap (PC) magnetic activity (characterized by the PC index) to magnetic disturbances in the auroral zone (AL index) the behavior of 62 repetitive bay-like magnetic disturbances has been analyzed. It was found that the PC index, derived as a proxy of the geoeffective interplanetary electric field Em, starts to increase, on average, about 30 min ahead of the magnetic disturbance onset. Value of Em and PC?2 mV/m seems to be necessary for development of the repetitive bay-like disturbances with peak AL exceeding 400 nT. Growth phase duration (the time interval between the start of PC increase and AL sudden onset) and intensity of magnetic disturbances in the auroral zone (AL max) highly correlate with the PC growth rate. The growth phase reduces to a few minutes, if the PC index suddenly jumps above ?6–8 mV/m. The sharp development of Birkeland current wedge during expansion phase insignificantly influences the polar cap activity: the corresponding PC index increase does not exceed 10–20% of the PC value. It is concluded that the PC index may be considered as a convenient proxy of the solar wind energy input into the magnetosphere.

O. Troshichev; A. Janzhura

2009-01-01T23:59:59.000Z

342

Nuclear Forensics | More Science | ORNL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Materials Science and Engineering Materials Science and Engineering Advanced Materials Clean Energy Materials Theory and Simulation Neutron Science Nuclear Forensics Nuclear Science Supercomputing Theory, Modeling and Simulation More Science Home | Science & Discovery | More Science | Materials Science and Engineering | Nuclear Forensics SHARE Nuclear Forensics image Tools, techniques, and expertise in nuclear fuel cycle research gained over seven decades help ORNL scientists control and track nuclear bomb-grade materials to be sure they don't fall into the wrong hands. Among the leading-edge technologies used by researchers are high-resolution techniques that allow analysis of radiation detector data in stunning detail. Researchers are also developing aerosol sampling systems to collect

343

Nuclear effects in Neutrino Nuclear Cross-sections  

E-Print Network [OSTI]

Nuclear effects in the quasielastic and inelastic scattering of neutrinos(antineutrinos) from nuclear targets have been studied. The calculations are done in the local density approximation which take into account the effect of nucleon motion as well as renormalisation of weak transition strengths in the nuclear medium. The inelastic reaction leading to production of pions is calculated in a $\\Delta$ dominance model taking into account the renormalization of $\\Delta$ properties in the nuclear medium.

S. K. Singh; M. Sajjad Athar

2007-10-24T23:59:59.000Z

344

Unsaturated flow modeling in performance assessments for the Yucca Mountain disposal system for spent nuclear fuel and high-level radioactive waste  

Science Journals Connector (OSTI)

Abstract This paper summarizes the progression of modeling efforts of infiltration, percolation, and seepage conducted between 1984 and 2008 to evaluate feasibility, viability, and assess compliance of a repository in the unsaturated zone for spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nevada. Scientific understanding of infiltration in a desert environment, unsaturated percolation flux in fractures and matrix of the volcanic tuff, and seepage into an open drift in a thermally perturbed environment was initially lacking in 1984. As understanding of the Yucca Mountain disposal system increased through site characterization and in situ testing, modeling of infiltration, percolation, and seepage evolved from simple assumptions in a single model in 1984 to three modeling modules each based on several detailed process models in 2008. Uncertainty in percolation flux through Yucca Mountain was usually important in explaining the observed uncertainty in performance measures:cumulative release in assessments prior to 1995 and individual dose, thereafter.

Rob P. Rechard; Jens T. Birkholzer; Yu-Shu Wu; Joshua S. Stein; James E. Houseworth

2014-01-01T23:59:59.000Z

345

Nuclear choices  

SciTech Connect (OSTI)

This book contains part of the series New Liberal Arts, which is intended to make science and technology more accessible to students of the liberal arts. Volume in hand provides a comprehensive, multifaceted examination of nuclear energy, in nontechnical terms. Wolfson explains the basics of nuclear energy and radiation, nuclear power..., and nuclear weapons..., and he invites readers to make their own judgments on controversial nuclear issues. Illustrated with photos and diagrams. Each chapter contains suggestions for additional reading and a glossary. For policy, science, and general collections in all libraries. (ES) Topics contained include Atoms and nuclei. Effects and uses of radiation. Energy and People. Reactor safety. Nuclear strategy. Defense in the nuclear age. Nuclear power, nuclear weapons, and nuclear futures.

Wolfson, R.

1991-01-01T23:59:59.000Z

346

Economic Analysis for Conceptual Design of Oxygen-Based PC Boiler  

SciTech Connect (OSTI)

The objective of the economic analysis is to prepare a budgetary estimate of capital and operating costs of the O{sub 2}-fired PC power plant as well as for the equivalent conventional PC-fired power plant. Capital and operating costs of conventional steam generation, steam heating, and power generation equipment are estimated based on Foster Wheeler's extensive experience and database. Capital and operating costs of equipment, such as oxygen separation and CO{sub 2} liquefaction, are based on vendor supplied data and FW process plant experience. The levelized cost of electricity is determined for both the air-fired and O{sub 2}-fired power plants as well as the CO{sub 2} mitigation cost. An economic comparison between the O{sub 2}-fired PC and other alternate technologies is presented.

Andrew Seltzer

2005-02-01T23:59:59.000Z

347

Application of sPC-SAFT-JC and sPC-SAFT-GV to Phase Equilibria Predictions of Alkane/Alcohol, Alcohol/Alcohol, and Water/Alcohol Binary Systems  

Science Journals Connector (OSTI)

Application of sPC-SAFT-JC and sPC-SAFT-GV to Phase Equilibria Predictions of Alkane/Alcohol, Alcohol/Alcohol, and Water/Alcohol Binary Systems ... This paper reports on the ability of sPC-SAFT extended with the polar terms of Gross and Vrabec (GV) and Jog and Chapman (JC) to predict the phase equilibria of alkane/alcohol, alcohol/alcohol, and water/alcohol binary systems. ... For these selected binary systems, the GV and JC polar terms deliver similar results when incorporated into sPC-SAFT. ...

Adriaan J. de Villiers; Cara E. Schwarz; Krasimir G. Chobanov; Andries J. Burger

2014-03-12T23:59:59.000Z

348

Transactions of the fourth symposium on space nuclear power systems  

SciTech Connect (OSTI)

This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these papers include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, refractory alloys and high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

El-Genk, M.S.; Hoover, M.D. (eds.)

1987-01-01T23:59:59.000Z

349

Transactions of the fifth symposium on space nuclear power systems  

SciTech Connect (OSTI)

This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these paper include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

El-Genk, M.S.; Hoover, M.D. (eds.)

1988-01-01T23:59:59.000Z

350

defense nuclear security | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

nuclear security | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

351

Chernobyl Nuclear Accident | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Chernobyl Nuclear Accident | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

352

Countering Nuclear Terrorism and Trafficking | National Nuclear...  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism and Trafficking | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

353

Petri Net Modeling for Probabilistic Safety Assessment and its Application in the Air Lock System of a CANDU Nuclear Power Plant  

Science Journals Connector (OSTI)

Historically, fault trees are extensively used in Probabilistic Safety Assessment (PSA) to model and evaluate the probability and consequence of failures of complex engineering systems, such as nuclear power plants. Scenarios of hypothetical accidents resulting in severe core damage can be developed. Petri net is another modeling technique that offers many advantages when comparing with fault trees, such as is ability to represent the time sequence of the events along with their duration. In this research, Petri net theory is extended to model system failures. The transformations required to model logic gates by Petri nets are explored and examples provided. Methods for qualitative analysis for Petri nets are presented. The application of Petri net in the airlock system of a Canada Deuterium Uranium (CANDU) reactor is explored. It is further demonstrated that Petri net can be used in both coherent and non-coherent systems.

Andrew Lee; Lixuan Lu

2012-01-01T23:59:59.000Z

354

Dynamics of low-energy nuclear forces for electromagnetic and weak reactions with the deuteron in the Nambu-Jona-Lasinio model of light nuclei  

E-Print Network [OSTI]

A dynamics of low-energy nuclear forces is investigated for low-energy electromagnetic and weak nuclear reactions with the deuteron in the Nambu-Jona-Lasinio model of light nuclei by example of the neutron-proton radiative capture (M1-capture) n + p -> D + photon, the photomagnetic disintegration of the deuteron photon + D -> n + p and weak reactions of astrophysical interest. These are the solar proton burning p + p -> D + positron + nu_e, the pep-process p + electron + p -> D + nu_e and the neutrino and anti-neutrino disintegration of the deuteron caused by charged nu_e + D -> electron + p + p, anti-nu_e + D -> positron + n + n and neutral nu_e(anti-nu_e) + D -> nu_e(ant-nu_e) + n + p weak currents.

A. N. Ivanov; H. Oberhummer; N. I. Troitskaya; M. Faber

2000-06-22T23:59:59.000Z

355

Spin- and isospin-polarized states of nuclear matter in the Dirac-Brueckner-Hartree-Fock model  

E-Print Network [OSTI]

Spin-polarized isospin asymmetric nuclear matter is studied within the Dirac-Brueckner-Hartree-Fock approach. After a brief review of the formalism, we present and discuss the self-consistent single-particle potentials at various levels of spin and isospin asymmetry. We then move to predictions of the energy per particle, also under different conditions of isospin and spin polarization. Comparison with the energy per particle in isospin symmetric or asymmetric unpolarized nuclear matter shows no evidence for a phase transition to a spin ordered state, neither ferromagnetic nor antiferromagnetic.

Francesca Sammarruca

2011-04-03T23:59:59.000Z

356

Spin- and isospin-polarized states of nuclear matter in the Dirac-Brueckner-Hartree-Fock model  

E-Print Network [OSTI]

Spin-polarized isospin asymmetric nuclear matter is studied within the Dirac-Brueckner-Hartree-Fock approach. After a brief review of the formalism, we present and discuss the self-consistent single-particle potentials at various levels of spin and isospin asymmetry. We then move to predictions of the energy per particle, also under different conditions of isospin and spin polarization. Comparison with the energy per particle in isospin symmetric or asymmetric unpolarized nuclear matter shows no evidence for a phase transition to a spin ordered state, neither ferromagnetic nor antiferromagnetic.

Sammarruca, Francesca

2011-01-01T23:59:59.000Z

357

A&T Engineering, P.C. A4S Technologies, Inc.  

E-Print Network [OSTI]

Technology Inc. Civitas Learning Clark Construction Group, California LP Clean Water Action CodeForce 3603D Labs 3D Labs A&T Engineering, P.C. A4S Technologies, Inc. Abound Solar Inc. Accountemps ACIT. Advanced Micro Devices Inc. Advanced Technology Network, Inc Advanced Video Technology Corp. AECOM Aegis

Barnes, Elizabeth A.

358

Generation of magnetic and particle Pc5 pulsations during the recovery phase of strong magnetic storms  

Science Journals Connector (OSTI)

...meta-stable state under high solar wind velocities, and quasi-periodic fluctuations of the solar wind plasma density stimulate the...R. , A. N. Wright, K. Mills, and V. M. Nakariakov1999Excitation...I. R. Mann2001On the solar wind control of Pc5 ULF pulsation...

2010-01-01T23:59:59.000Z

359

SYSTEM DESIGN AND ANALYSIS FOR CONCEPTUAL DESIGN OF OXYGEN-BASED PC BOILER  

SciTech Connect (OSTI)

The objective of the system design and analysis task of the Conceptual Design of Oxygen-Based PC Boiler study is to optimize the PC boiler plant by maximizing system efficiency. Simulations of the oxygen-fired plant with CO{sub 2} sequestration were conducted using Aspen Plus and were compared to a reference air-fired 460 Mw plant. Flue gas recycle is used in the O{sub 2}-fired PC to control the flame temperature. Parametric runs were made to determine the effect of flame temperature on system efficiency and required waterwall material and thickness. The degree of improvement on system efficiency of various modifications including hot gas recycle, purge gas recycle, flue gas feedwater recuperation, and recycle purge gas expansion were investigated. The selected O{sub 2}-fired design case has a system efficiency of 30.1% compared to the air-fired system efficiency of 36.7%. The design O{sub 2}-fired case requires T91 waterwall material and has a waterwall surface area of only 44% of the air-fired reference case. Compared to other CO{sub 2} sequestration technologies, the O{sub 2}-fired PC is substantially better than both natural gas combined cycles and post CO{sub 2} removal PCs and is slightly better than integrated gasification combined cycles.

Zhen Fan; Andrew Seltzer

2003-11-01T23:59:59.000Z

360

SoPC based Smart Home Embedded Computer Capable of Caring for the Home Occupants  

E-Print Network [OSTI]

to safe and environmental friendly living spaces. One aspect of home automation is the direct controlSoPC based Smart Home Embedded Computer Capable of Caring for the Home Occupants G. N. Khan and J. Toronto, Ontario Canada M5B 2K3 Abstract--We present a Smart-Home Embedded Computer (SHEC) system

Khan, Gul N.

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

HOME ADVANTAGE AND TIED GAMES P.C. van der Kruit  

E-Print Network [OSTI]

HOME ADVANTAGE AND TIED GAMES IN SOCCER P.C. van der Kruit 0. Introduction. Home advantage about half the games end in a victory for the home team, one quarter end up tied, while only one quarter about 3) is rather low. The home advantage is supposedly evened out between the teams by playing a full

Kruit, Piet van der

362

Calibration constant of Alpha track detector-polycarbonate film, CAPFILM PC  

E-Print Network [OSTI]

parameters for LR-1 15 11 were found to be with 2.5 N NaOH for 145 minutes at 60 C (Vasudevan 1991). Both LR-1 15 and CAPFILM PC were simultaneously exposed in the radon exposure chamber which was connected to a barrel containing uranium ore. The exposed film...

Chung, Isaac Young

2012-06-07T23:59:59.000Z

363

Prediction of the PC-SAFT Associating Parameters by Molecular Simulation  

Science Journals Connector (OSTI)

Prediction of the PC-SAFT Associating Parameters by Molecular Simulation ... In this work, we propose a new methodology to determine association scheme and association parameters (energy and volume) of a SAFT-type EoS for hydrogen-bonding molecules. ... A new set of parameters for 1-alkanol for the PPC-SAFT equation of state has been proposed following this methodology. ...

Nicolas Ferrando; Jean-Charles de Hemptinne; Pascal Mougin; Jean-Philippe Passarello

2011-11-29T23:59:59.000Z

364

Nuclear Science  

Broader source: Energy.gov (indexed) [DOE]

Science Science and Engineering Education Sourcebook 2013 American Nuclear Society US Department of Energy Nuclear Science & Engineering Education Sourcebook 2013 North American Edition American Nuclear Society Education, Training, and Workforce Division US Department of Energy Office of Nuclear Energy Editor and Founder John Gilligan Professor of Nuclear Engineering North Carolina State University Version 5.13 Welcome to the 2013 Edition of the Nuclear Science and Engineering Education (NS&EE) Sourcebook. We have evolved and improved! The core mission of the Sourcebook has not changed, however. Our purpose is to facilitate interaction among faculty, students, industry, and government agencies to accomplish nuclear research, teaching and service activities. Since 1986 we have compiled critical information on nuclear

365

Nuclear reactions  

Science Journals Connector (OSTI)

Much reference has been made in the last chapter to nuclear energy levels and their various properties (e.g ... ways of doing this — the use of nuclear reactions, and studies of how excited nuclei...

R. J. Blin-Stoyle FRS

1991-01-01T23:59:59.000Z

366

nuclear security  

National Nuclear Security Administration (NNSA)

3%2A en Shaping the future of nuclear detection http:nnsa.energy.govblogshaping-future-nuclear-detection

367

Stellar Populations in the Central 0.5 pc of the Galaxy I: A New Method for Constructing Luminosity Functions and Surface-Density Profiles  

E-Print Network [OSTI]

We present new high angular resolution near-infrared spectroscopic observations of the nuclear star cluster surrounding the Milky Way's central supermassive black hole. Using the integral-field spectrograph OSIRIS on Keck II behind the laser-guide-star adaptive optics system, this spectroscopic survey enables us to separate early-type (young, 4-6 Myr) and late-type (old, >1 Gyr) stars with a completeness of 50% down to K' = 15.5 mag, which corresponds to ~10 \\msun for the early-type stars. This work increases the radial extent of reported OSIRIS/Keck measurements by more than a factor of 3 from 4" to 14" (0.16 pc to 0.56 pc), along the projected disk of young stars. For our analysis, we implement a new method of completeness correction using a combination of star-planting simulations and Bayesian inference. We assign probabilities for the spectral type of every source detected in deep imaging down to K' = 15.5 mag using information from spectra, simulations, number counts, and the distribution of stars. The i...

Do, Tuan; Ghez, Andrea M; Morris, Mark R; Yelda, Sylvana; Martinez, Gregory D; Wright, Shelley A; Matthews, Keith

2013-01-01T23:59:59.000Z

368

Nuclear Ukraine  

Science Journals Connector (OSTI)

... SIR - Your article (Nature 365, 599; 1993) on the US-Ukraine stalemate over nuclear weapons prompts the following remarks. The United States made a mistake ... nuclear weapons prompts the following remarks. The United States made a mistake in not recognizing Ukraine as a legitimate successor state to the Soviet nuclear arsenal and is still insisting that ...

Arno Arrak

1994-01-13T23:59:59.000Z

369

Source Term Estimation of Radioxenon Released from the Fukushima Dai-ichi Nuclear Reactors Using Measured Air Concentrations and Atmospheric Transport Modeling  

SciTech Connect (OSTI)

Systems designed to monitor airborne radionuclides released from underground nuclear explosions detected radioactive fallout from the Fukushima Daiichi nuclear accident in March 2011. Atmospheric transport modeling (ATM) of plumes of noble gases and particulates were performed soon after the accident to determine plausible detection locations of any radioactive releases to the atmosphere. We combine sampling data from multiple International Modeling System (IMS) locations in a new way to estimate the magnitude and time sequence of the releases. Dilution factors from the modeled plume at five different detection locations were combined with 57 atmospheric concentration measurements of 133-Xe taken from March 18 to March 23 to estimate the source term. This approach estimates that 59% of the 1.24×1019 Bq of 133-Xe present in the reactors at the time of the earthquake was released to the atmosphere over a three day period. Source term estimates from combinations of detection sites have lower spread than estimates based on measurements at single detection sites. Sensitivity cases based on data from four or more detection locations bound the source term between 35% and 255% of available xenon inventory.

Eslinger, Paul W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Biegalski, S. [Univ. of Texas at Austin, TX (United States); Bowyer, Ted W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Cooper, Matthew W. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Haas, Derek A. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Hayes, James C. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Hoffman, Ian [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); Korpach, E. [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); Yi, Jing [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); Miley, Harry S. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Rishel, Jeremy P. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ungar, R. Kurt [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); White, Brian [Radiation Protection Bureau, Health Canada, Ottawa, ON (Canada); Woods, Vincent T. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

2014-01-01T23:59:59.000Z

370

Nuclear Engineer (Nuclear Safety Specialist)  

Broader source: Energy.gov [DOE]

A successful candidate of this position will serve as a Nuclear Engineer (Nuclear Safety Specialist) responsible for day-to-day technical monitoring, and evaluation of aspects of authorization...

371

Nuclear excitation and precompound nuclear reactions  

Science Journals Connector (OSTI)

The angular distribution of nucleons emitted in nucleon-induced precompound nuclear reactions are calculated taking into account the effect of excitation on the kinematics of nucleon-nucleon scattering inside the target-plus-projectile system. The results are compared with quantum mechanical calculations and those of reaction models based on a pure nucleon-nucleon collision picture.

Anuradha De; Siddhartha Ray; Sudip Kumar Ghosh

1988-06-01T23:59:59.000Z

372

The single-strand DNA binding activity of human PC4 preventsmutagenesis and killing by oxidative DNA damage  

SciTech Connect (OSTI)

Human positive cofactor 4 (PC4) is a transcriptional coactivator with a highly conserved single-strand DNA (ssDNA) binding domain of unknown function. We identified PC4 as a suppressor of the oxidative mutator phenotype of the Escherichia coli fpg mutY mutant and demonstrate that this suppression requires its ssDNA binding activity. Yeast mutants lacking their PC4 ortholog Sub1 are sensitive to hydrogen peroxide and exhibit spontaneous and peroxide induced hypermutability. PC4 expression suppresses the peroxide sensitivity of the yeast sub l{Delta} mutant, suggesting that the human protein has a similar function. A role for yeast and human proteins in DNA repair is suggested by the demonstration that Sub1 acts in a peroxide-resistance pathway involving Rad2 and by the physical interaction of PC4 with the human Rad2 homolog XPG. We show XPG recruits PC4 to a bubble-containing DNA substrate with resulting displacement of XPG and formation of a PC4-DNA complex. We discuss the possible requirement for PC4 in either global or transcription-coupled repair of oxidative DNA damage to mediate the release of XPG bound to its substrate.

Wang, Jen-Yeu; Sarker, Altaf Hossain; Cooper, Priscilla K.; Volkert, Michael R.

2004-02-01T23:59:59.000Z

373

Data Sheet Fujitsu ESPRIMO P910 E90+ Desktop PC Page 1 / 8 www.fujitsu.com/fts/ESPRIMO  

E-Print Network [OSTI]

recommends Windows® 7. Data Sheet Fujitsu ESPRIMO P910 E90+ Desktop PC The Expandable Business Workhorse Fujitsu ESPRIMO P910 PCs give you the absolute highest PC manageability, performance and expandability *with Intel® Turbo Boost Technology (clock speed and will vary depending on workload and other variables

Fiebig, Peter

374

Uncertainties in nuclear transition matrix elements for ?+?+ and ??+ modes of neutrinoless positron double-? decay within the projected Hartree-Fock-Bogoliubov model  

Science Journals Connector (OSTI)

Uncertainties in the nuclear transition matrix elements M(0?) and M(0N) of the double-positron emission (?+?+)0? and electron-positron conversion (??+)0? modes owing to the exchange of light and heavy Majorana neutrinos, respectively, are calculated for 96Ru, 102Pd, 106Cd, 124Xe, 130Ba, and 156Dy isotopes by employing the PHFB model with four different parametrizations of the pairing plus multipolar two-body interactions and three different parametrizations of the Jastrow short-range correlations. In all cases but for 130Ba the uncertainties are smaller than 14% for light Majorana neutrino exchange and 35% for the exchange of a heavy Majorana neutrino.

P. K. Rath, R. Chandra, K. Chaturvedi, P. Lohani, P. K. Raina, and J. G. Hirsch

2013-01-03T23:59:59.000Z

375

Used Nuclear Fuel Loading and Structural Performance Under Normal...  

Office of Environmental Management (EM)

Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan Used Nuclear Fuel Loading...

376

Nuclear Deterrence  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Deterrence Nuclear Deterrence Nuclear Deterrence LANL's mission is to develop and apply science and technology to ensure the safety, security, and effectiveness of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. April 12, 2012 A B-2 Spirit bomber refuels from a KC-135 Stratotanker A B-2 Spirit bomber refuels from a KC-135 Stratotanker. Contact Operator Los Alamos National Laboratory (505) 667-5061 Charlie McMillan, Director: "For the last 70 years there has not been a world war, and I have to think that our strong deterrent has something to do with that fact." Mission nuclear weapons Charlie McMillan, Director of Los Alamos National Laboratory 1:06 Director McMillan on nuclear deterrence While the role and prominence of nuclear weapons in U.S. security policy

377

Morphology and properties of a hybrid organic-inorganic system: Al nanoparticles embedded into CuPc thin film  

SciTech Connect (OSTI)

The evolution of the morphology and the electronic structure of the hybrid organic-inorganic system composed of aluminum nanoparticles (NPs) distributed in an organic semiconductor matrix—copper phthalocyanine (CuPc)—as a function of nominal aluminum content was studied by transmission electron microscopy and by photoemission spectroscopy methods. The aluminum atoms deposited onto the CuPc surface diffuse into the organic matrix and self-assemble to NPs in a well-defined manner with a narrow diameter distribution, which depends on the amount of aluminum that is evaporated onto the CuPc film. We find clear evidence of a charge transfer from Al to CuPc and we have been able to determine the lattice sites where Al ions sit. The finally at high coverage about 64?Å the formation of metallic aluminum overlayer on CuPc thin film takes place.

Molodtsova, O. V.; Babenkov, S. V. [Deutsches Elektronen-Synchrotron DESY, Notkestraße 85, 22607 Hamburg (Germany); Aristova, I. M. [Institute of Solid State Physics of Russian Academy of Sciences, Chernogolovka 142432 (Russian Federation); Vilkov, O. V. [Helmholtz-Zentrum Berlin (HZB) für Materialien und Energie, Albert-Einstein-Straße 15, 12489 Berlin (Germany); Aristov, V. Yu., E-mail: aristov@issp.ac.ru [Deutsches Elektronen-Synchrotron DESY, Notkestraße 85, 22607 Hamburg (Germany); Institute of Solid State Physics of Russian Academy of Sciences, Chernogolovka 142432 (Russian Federation); Institut für Theoretische Physik, Universität Hamburg, Jungiusstraße 9, D-20355 Hamburg (Germany)

2014-04-28T23:59:59.000Z

378

A virtual control room with an embedded, interactive nuclear reactor simulator  

SciTech Connect (OSTI)

The use of virtual nuclear control room can be an effective and powerful tool for training personnel working in the nuclear power plants. Operators could experience and simulate the functioning of the plant, even in critical situations, without being in a real power plant or running any risk. 3D models can be exported to Virtual Reality formats and then displayed in the Virtual Reality environment providing an immersive 3D experience. However, two major limitations of this approach are that 3D models exhibit static textures, and they are not fully interactive and therefore cannot be used effectively in training personnel. In this paper we first describe a possible solution for embedding the output of a computer application in a 3D virtual scene, coupling real-world applications and VR systems. The VR system reported here grabs the output of an application running on an X server; creates a texture with the output and then displays it on a screen or a wall in the virtual reality environment. We then propose a simple model for providing interaction between the user in the VR system and the running simulator. This approach is based on the use of internet-based application that can be commanded by a laptop or tablet-pc added to the virtual environment. (authors)

Markidis, S.; Rizwan, U. [Dept. of Nuclear, Plasma, and Radiological Engineering, Univ. of Illinois, Urbana, IL 61801 (United States)

2006-07-01T23:59:59.000Z

379

Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project  

SciTech Connect (OSTI)

ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

Sullivan T.

2014-06-09T23:59:59.000Z

380

General Heat Transfer Characterization and Empirical Models of Material Storage Temperatures for the Los Alamos Nuclear Materials Storage Facility  

SciTech Connect (OSTI)

The Los Alamos National Laboratory's Nuclear Materials Storage Facility (NMSF) is being renovated for long-term storage of canisters designed to hold heat-generating nuclear materials. A fully passive cooling scheme, relying on the transfer of heat by conduction, free convection, and radiation has been proposed as a reliable means of maintaining material at acceptable storage temperatures. The storage concept involves placing radioactive materials, with a net heat-generation rate of 10 W to 20 W, inside a set of nested steel canisters. The canisters are, in placed in holding fixtures and positioned vertically within a steel storage pipe. Several hundred drywells are arranged in a linear array within a large bay and dissipate the waste heat to the surrounding air, thus creating a buoyancy driven airflow pattern that draws cool air into the storage facility and exhausts heated air through an outlet stack. In this study, an experimental apparatus was designed to investigate the thermal characteristics of simulated nuclear materials placed inside two nested steel canisters positioned vertically on an aluminum fixture plate and placed inside a section of steel pipe. The heat-generating nuclear materials were simulated with a solid aluminum cylinder containing .an embedded electrical resistance heater. Calibrated type T thermocouples (accurate to ~ O.1 C) were used to monitor temperatures at 20 different locations within the apparatus. The purposes of this study were to observe the heat dissipation characteristics of the proposed `canister/fixture plate storage configuration, to investigate how the storage system responds to changes in various parameters, and to develop and validate empirical correlations to predict material temperatures under various operating conditions

J. D. Bernardin; W. S. Gregory

1998-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Nuclear moment of inertia and spin distribution of nuclear levels  

Science Journals Connector (OSTI)

We introduce a simple model to calculate the nuclear moment of inertia at finite temperature. This moment of inertia describes the spin distribution of nuclear levels in the framework of the spin-cutoff model. Our model is based on a deformed single-particle Hamiltonian with pairing interaction and takes into account fluctuations in the pairing gap. We derive a formula for the moment of inertia at finite temperature that generalizes the Belyaev formula for zero temperature. We show that a number-parity projection explains the strong odd-even effects observed in shell model Monte Carlo studies of the nuclear moment of inertia in the iron region.

Y. Alhassid; G. F. Bertsch; L. Fang; S. Liu

2005-12-29T23:59:59.000Z

382

Progression of performance assessment modeling for the Yucca Mountain disposal system for spent nuclear fuel and high-level radioactive waste  

Science Journals Connector (OSTI)

Abstract This paper summarizes the evolution of consequence modeling for a repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain in southern Nevada. The discussion includes four early performance assessments (PAs) conducted between 1982 and 1995 to support selection and to evaluate feasibility and three major \\{PAs\\} conducted between 1998 and 2008 to evaluate viability, recommend the site, and assess compliance. Modeling efforts in 1982 estimated dose to individuals 18 km from the site caused by volcanic eruption through the repository. Modeling in 1984 estimated releases via the groundwater pathway because of container corrosion. In combination, this early analysis supported the first environmental assessment. Analysts in 1991 evaluated cumulative release, as specified in the 1985 US radiation protection standards, via the groundwater pathway over 104 yr at a 5-km boundary by modeling waste degradation and flow/transport in the saturated and unsaturated zones. By 1992, however, the US Congress mandated a change to a dose measure. Thus, the 1993 and 1995 performance assessments improved modeling of waste container degradation to provide better estimates of radionuclide release rates out to 106 yr. The 1998 viability assessment was a major step in modeling complexity. Dose at a 20-km boundary from the repository was evaluated through 106 yr for undisturbed conditions using more elaborate modeling of flow and the addition of modules for modeling infiltration, drift seepage, the chemical environment, and biosphere transport. The 2000 assessment for the site recommendation refined the analysis. Seepage modeling was greatly improved and waste form degradation modeling included more chemical dependence. The 2008 compliance assessment for the license application incorporated the influence of the seismicity on waste package performance to evaluate dose at an ~18-km boundary.

Rob P. Rechard; Michael L. Wilson; S. David Sevougian

2014-01-01T23:59:59.000Z

383

Recovery and Resilience After a Nuclear Power Plant Disaster: A Medical Decision model for Managing an Effective, Timely, and Balanced Response  

SciTech Connect (OSTI)

Based on experiences in Tokyo responding to the Fukushima Daiichi nuclear power plant crisis, a real-time, medical decision model is presented by which to make key health-related decisions given the central role of health and medical issues in such disasters. Focus is on response and recovery activities that are safe, timely, effective, and well-organized. This approach empowers on-site decision makers to make interim decisions without undue delay using readily available and high-level scientific, medical, communication, and policy expertise. Key features of this approach include ongoing assessment, consultation, information, and adaption to the changing conditions. This medical decision model presented is compatible with the existing US National Response Framework structure.

Coleman, C. Norman [National Cancer Institute, NIH; Blumenthal, Daniel J. [National Nuclear Security Administration (NNSA), Department of Energy

2013-05-01T23:59:59.000Z

384

HANSF 1.3 Users Manual FAI/98-40-R2 Hanford Spent Nuclear Fuel (SNF) Safety Analysis Model [SEC 1 and 2  

SciTech Connect (OSTI)

The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. This manual reflects the HANSF version 1.3.2, a revised version of 1.3.1. HANSF 1.3.2 was written to correct minor errors and to allow modeling of condensate flow on the MCO inner surface. HANSF 1.3.2 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under Lahey TI or digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments.

DUNCAN, D.R.

1999-10-07T23:59:59.000Z

385

How to Submit Forms: Exclusionary List: For the PC Electronic Data  

U.S. Energy Information Administration (EIA) Indexed Site

For the PC Electronic Data For the PC Electronic Data - DATE OF THIS REPORT: 1 3 Reseller/Retailer 2 4 Retailer 1 3 Sold or leased to another firm. See PART 3 of the instructions. 2 4 Permanently ceased operation. See PART 3 of the instructions. https://signon.eia.doe.gov/upload/noticeoog.jsp Reporting Option (PEDRO) software, call (202) 586- 9659. Mailing Address: City: OOG.SURVEYS@eia.doe.gov Email: Electronic Transmission: Physical Address: Fax No.: (e.g., Street Address, Bldg, Floor, Suite) (e.g., PO Box, RR) Original Mo Day Call: Year Questions? Type of Report (Check One ): Number of States for which you are reporting: Year Company Name: http://www.eia.gov/survey/form/eia_782a/list782a.pdf Instructions: http://www.eia.gov/survey/form/eia_782a/instructions.pdf FORM EIA-782A REFINERS'/GAS PLANT OPERATORS' MONTHLY PETROLEUM PRODUCT SALES REPORT

386

Selective adsorption and electronic interaction of F16CuPc on epitaxial graphene  

Science Journals Connector (OSTI)

We investigate the electronic coupling between copper hexadecafluoro-phthalocyanine (F16CuPc) and epitaxial graphene (EG) on 6H-SiC(0001) using a combined approach of low-temperature scanning tunneling spectroscopy and electronic structure calculations. The molecules are preferentially adsorbed on monolayer EG than bilayer EG. Competing molecule-surface and intermolecular van der Waals interactions result in two well-ordered incommensurate phases. We show that the amount of charge transfer from EG to F16CuPc can be tuned by applied voltage or the thickness of graphene layers. A characteristic feature at ?0.4?eV above the Dirac point is identified in bilayer EG, which indicates its electronic structure is modified via introducing extra unoccupied states upon adsorption.

Yi-Lin Wang; Jun Ren; Can-Li Song; Ye-Ping Jiang; Li-Li Wang; Ke He; Xi Chen; Jin-Feng Jia; Sheng Meng; Efthimios Kaxiras; Qi-Kun Xue; Xu-Cun Ma

2010-12-14T23:59:59.000Z

387

WebNow login Instructions for PC Users Accounts Payable & Travel Page 1 of 15  

E-Print Network [OSTI]

WebNow login Instructions for PC Users Accounts Payable & Travel Version 3 2/12/14 Page 1 of 15 1 into MyAccess, the system will prompt you to log in. 2) If this is the first time you're logging into WebNow, you will be asked to RUN an application to do an initial setup of the WebNow applet on your computer

Yamamoto, Keith

388

Dipole rescattering and the nuclear structure function  

SciTech Connect (OSTI)

In the framework of the dipole model, we study the effects of the dipole multiple scatterings in a nuclear target and compute the nuclear structure function. We compare different unitarization schemes and confront our results with the E665 data.

Carvalho, F. [Depto de Ciencias Exatas e da Terra, Universidade Federal de Sao Paulo, SP (Brazil); Goncalves, V. P. [Instituto de Fisica e Matematica, Universidade Federal de Pelotas, Caixa Postal 354, CEP 96010-900, Pelotas, RS (Brazil); Navarra, F. S.; Oliveira, E. G. [Instituto de Fisica, Universidade de Sao Paulo Rua do Matao, Travessa R, 187, 05508-090 Sao Paulo, SP (Brazil)

2013-03-25T23:59:59.000Z

389

A Safer Nuclear Enterprise  

Science Journals Connector (OSTI)

...2012 at the Nuclear Security...leadership in nuclear enterprise...multinational assessment of emerging risks and consequences...to assess nuclear risks in...or nuclear terrorism. States...and nuclear power. Since 1945...nuclear power plant can mean...

Sidney D. Drell; George P. Shultz; Steven P. Andreasen

2012-06-08T23:59:59.000Z

390

Nuclear astrophysics  

SciTech Connect (OSTI)

The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized.

Haxton, W.C.

1992-12-31T23:59:59.000Z

391

Nuclear astrophysics  

SciTech Connect (OSTI)

The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized.

Haxton, W.C.

1992-01-01T23:59:59.000Z

392

Nuclear Counterterrorism  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information.) Appendices A and B are Official Use Only. Point of contact is Adam Boyd (NA-82), 202-586-0010. Cancels DOE O 457.1 and DOE M 457.1-1.

2013-08-26T23:59:59.000Z

393

Application of SAFER-PC program to determine turbine rotor boresonic inspection intervals  

SciTech Connect (OSTI)

Public Service Company of Colorado (PSCC) used EPRI`s SAFER-PC Program to evaluate their HP/IP, LP, and generator rotors from Cherokee Station Unit 3, to determine appropriate boresonic re-inspection intervals. The program uses fracture mechanics to calculate critical crack sizes, which could lead to catastrophic failure of the rotors. Conservative stress and fracture mechanics analyses showed negligible fatigue crack growth of assumed bore surface cracks would occur over the proposed inspection interval of eighteen years. The evaluation assumed consistent operational start-up procedures for the inspection interval. If the unit experiences more severe operational procedures, the analysis may not be applicable, with smaller critical crack sizes and accelerated crack growth rates expected. The SAFER-PC analysis resulted in an extension of the previously recommended reinspection interval by eight years. By eliminating just this one inspection, PSCC achieved savings in the range of $100,000. Further savings are anticipated by utilizing the SAFER-PC Program to evaluate these and other PSCC rotors in the future.

Sachse, D.G.; Hellner, R.L.; Dupont, E.J. [Public Service Co., Denver, CO (United States)

1996-12-31T23:59:59.000Z

394

Modeling of asphaltene precipitation and deposition tendency using the PC-SAFT equation of state.  

E-Print Network [OSTI]

??Asphaltene precipitation and deposition can occur at different stages during petroleum production causing reservoir formation damage and plugging of pipeline and production equipment. Even though… (more)

Gonzalez Rodriguez, Doris Lucia

2008-01-01T23:59:59.000Z

395

Radioactive target needs for nuclear reactor physics and nuclear astrophysics , G. Barreau1  

E-Print Network [OSTI]

Radioactive target needs for nuclear reactor physics and nuclear astrophysics B.Jurado1* , G Gradignan, France 2 IPN, CNRS/IN2P3, Univ. Paris-Sud, 91405 Orsay, France Abstract: Nuclear reaction cross sections of short-lived nuclei are key inputs for new generation nuclear reactor simulations and for models

Boyer, Edmond

396

Nuclear Power  

Science Journals Connector (OSTI)

Nuclear Power ... THIS WEEK’S issue contains six letters on nuclear power, a representative sample of the letters C&EN received in response to the editorial, “Resist Hysteria,” I wrote shortly after the earthquake and tsunami in Japan devastated the Fukushima Daiichi Nuclear Power Station (C&EN, March 21, page 5). ... Four of the six letters take sharp issue with the primary point I made in the editorial, which was that, despite the severity of the situation in Japan, nuclear power remains an essential component of our overall energy mix for the near to mid-term because it will help us avert the worst impacts of global climate disruption. ...

RUDY M. BAUM

2011-05-09T23:59:59.000Z

397

NUCLEAR STUDIES  

Science Journals Connector (OSTI)

Japanese nuclear power plant crisis sparks examination of U.S. REACTORS ... Calls are particularly zeroing in on reactors similar in location and design to those in Japan. ...

JEFF JOHNSON

2011-04-04T23:59:59.000Z

398

Modeling of strongly heat-driven flow processes at a potential high-level nuclear waste repository at Yucca Mountain, Nevada  

SciTech Connect (OSTI)

Two complementary numerical models for analyzing high-level nuclear waste emplacement at Yucca Mountain have been developed. A vertical cross-sectional (X-Z) model permits a realistic representation of hydrogeologic features, such as alternating tilting layers of welded and non-welded tuffs. fault zones, and surface topography. An alternative radially symmetric (R-Z) model is more limited in its ability to describe the hydrogeology of the site, but is better suited to model heat transfer in the host rock. Our models include a comprehensive description of multiphase fluid and heat flow processes, including strong enhancements of vapor diffusion from pore-level phase change effects. The neighborhood of the repository is found to partially dry out from the waste heat. A condensation halo of large liquid saturation forms around the drying zone, from which liquid flows downward at large rates. System response to infiltration from the surface and to ventilation of mined openings is evaluated. The impact of the various flow processes on the waste isolation capabilities of the site is discussed.

Pruess, K.; Tsang, Y.

1993-01-01T23:59:59.000Z

399

Large scale nuclear sensor monitoring and diagnostics by means of an ensemble of regression models based on Evolving Clustering Methods  

E-Print Network [OSTI]

, Enrico Ziob a Institute for Energy Technology, Halden, Norway b Polytechnic of Milan, Milan, Italy is very large and cannot be handled effectively by a single reconstruction model. This paper tackles this issue by resorting to an ensemble of reconstruction models in which each model handles a small group

Boyer, Edmond

400

United States Nuclear Regulatory Commission  

Broader source: Energy.gov (indexed) [DOE]

qU oSoLTJRC qU oSoLTJRC United States Nuclear Regulatory Commission Protecting People and the Environment NUREG-1872, Vol. 2 HudcD [jE©wftamfsýýpc Wafm(M oran EA Office of New Reactors AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material As of November 1999, you may electronically access NUREG-series publications and other NRC records at NRC's Public Electronic Reading Room at http:t/www.nrc..ov/reading-rm.html. Publicly released records include, to name a few, NUREG-series publications; Federal Register notices; applicant, licensee, and vendor documents and correspondence; NRC correspondence and internal memoranda; bulletins and information notices; inspection and investigative reports; licensee event reports; and Commission papers and their attachments.

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Nuclear radiation electronic gear  

Science Journals Connector (OSTI)

Nuclear radiation electronic gear ... Examines the line of nuclear radiation instrumentation offered by Nuclear-Chicago Corporation and Victoreen Instrument Company. ... Nuclear / Radiochemistry ...

S. Z. Lewin

1961-01-01T23:59:59.000Z

402

Nuclear Weapons Journal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Weapons Journal Nuclear Weapons Journal x The Nuclear Weapons Journal ceased publication after Issue 2, 2009. Below are Nuclear Weapons Journal archived issues. Issue 2,...

403

Nuclear Materials Management & Safeguards System | National Nuclear...  

National Nuclear Security Administration (NNSA)

System Nuclear Materials Management & Safeguards System NMMSS U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards...

404

Nuclear options  

Science Journals Connector (OSTI)

... sad if transient commercial expediency led the country to take risks now by adopting nuclear reactor designs from abroad which are in some respects technically less sound than those produced at ... much lower priority. It can be anticipated, however; that although the types of nuclear reactor selected as the best that Britain could build next may be suitable for unit designs ...

G. R. Bainbridge

1974-06-21T23:59:59.000Z

405

Overview of mercury radionuclides and nuclear model calculations of 195Hgm,g and 197Hgm,g to evaluate experimental cross section data  

Science Journals Connector (OSTI)

Theoretical studies of isomers through nuclear reaction model calculations significantly assist the estimation of the different experimental data reported from different databases. In this paper, the production methods and the applications of mercury radionuclides are reviewed with special attention to the feasibility of the cyclotron production of mercury radionuclides, including 195Hgm,g and 197Hgm,g. First, talys and empire codes were employed to illustrate the formation of both the isomeric and the ground states of the mercury radionuclides. Then the excitation function was calculated via a variety of nuclear processes using the codes and the data taken from the TENDL database. Then we compared the data with the reported experimental measurement. The mercury radionuclide production yield was evaluated with concentration on the excitation function calculations and the stopping powers of the projectiles in the targets. Last, the 197Au(d,2n) and 197Au(p,3n) reactions were selected as the best reactions to produce 197Hgm,g and 195Hgm,g, respectively.

M. Sadeghi; M. Bakhtiari; M. K. Bakht; M. Anjomrouz; L. Mokhtari

2012-03-13T23:59:59.000Z

406

Nuclear incompressibility determined by nuclear mass and monopole resonance energy  

Science Journals Connector (OSTI)

The standard nuclear matter incompressibility K0 is determined by a data fit based on a model of nuclear energy functional and the scaling assumption of the nuclear breathing mode. The selected nuclear data used in this fit are taken from a limited set of nuclei which have both the measured mass M and the isoscalar giant monopole resonance energy EM. The obtained value of K0, based on 26 experimental points corresponding to 18 spherical nuclei with 89<~A<~209, is 220±20 MeV.

K. C. Chung; C. S. Wang; A. J. Santiago

1999-02-01T23:59:59.000Z

407

Nuclear Reactor Materials and Fuels  

Science Journals Connector (OSTI)

Nuclear reactor materials and fuels can be classified into six categories: Nuclear fuel materials Nuclear clad materials Nuclear coolant materials Nuclear poison materials Nuclear moderator materials

Dr. James S. Tulenko

2012-01-01T23:59:59.000Z

408

Radiochemical Investigations of Gastrin-releasing Peptide Receptor-specific [99mTc(X)(CO)3-Dpr-Ser-Ser-Ser-Gln-Trp-Ala-Val-Gly-His-Leu-Met-(NH2)] in PC-3, Tumor-bearing, Rodent Models: Syntheses, Radiolabeling, and in Vitro/in Vivo Studies where Dpr = 2,3-Diaminopropionic acid and X = H2O or P(CH2OH)3  

Science Journals Connector (OSTI)

...availability (99Mo/99mTc generator system), ideal nuclear...of borohydride under atmospheric carbon monoxide pressure...lability of the three water molecules coordinated...from a 99Mo/99mTc generator provided by Mallinckrodt...were performed on a Waters 600E system equipped...

C. Jeffrey Smith; Gary L. Sieckman; Nellie K. Owen; Donald L. Hayes; Dana G. Mazuru; Raghuraman Kannan; Wynn A. Volkert; and Timothy J. Hoffman

2003-07-15T23:59:59.000Z

409

7.0 References Davidson, J. R. 1995. ELIPGRID-PC: Upgraded Version. ORNL/TM-13103, Oak Ridge National  

E-Print Network [OSTI]

7.0 References Davidson, J. R. 1995. ELIPGRID-PC: Upgraded Version. ORNL/TM-13103, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Gilbert, R.O., J. E. Wilson, B. A. Pulsipher, N. L. Hassig

410

First-principles study for the adsorption of segments of BPA-PC on ?-Al2O3(0001)  

Science Journals Connector (OSTI)

We have studied the adsorption of bisphenol-A-polycarbonate (BPA-PC) on the ?-Al2O3(0001) surface using density functional theory (DFT) with van der Waals (vdW) corrections. The BPA-PC polymer can be divided into its chemical fragments, which are phenylene, carbonate, and isopropylidene groups. We have calculated the adsorption energy and geometry of the BPA-PC segments that consist of two to three adjacent groups of the polymer. Our DFT results show that the adsorption is dominated by the vdW interaction. It is also important to include the interaction of nearest-neighbor groups in order to provide a realistic environment for the adsorption of the polymer onto the surface. Our results also show that the BPA-PC molecule attaches to the alumina surface via the carbonate group located in the middle of the molecule chain.

Janne Blomqvist and Petri Salo

2011-10-25T23:59:59.000Z

411

NextPC computation for a banked instruction cache for a VLIW architecture with a compressed encoding  

E-Print Network [OSTI]

to the execution pipeline. The com- plexity of the hardware support required for i-fetch is related to the type cache Miss-repair logic ``Block Fetch'' Tag compare, Valid select & NextPC computation Expander Execution pipeline

Conte, Thomas M.

412

(Nuclear theory). [Research in nuclear physics  

SciTech Connect (OSTI)

This report discusses research in nuclear physics. Topics covered in this paper are: symmetry principles; nuclear astrophysics; nuclear structure; quark-gluon plasma; quantum chromodynamics; symmetry breaking; nuclear deformation; and cold fusion. (LSP)

Haxton, W.

1990-01-01T23:59:59.000Z

413

Development of multicomponent hybrid density functional theory with polarizable continuum model for the analysis of nuclear quantum effect and solvent effect on NMR chemical shift  

SciTech Connect (OSTI)

We have developed the multicomponent hybrid density functional theory [MC-(HF+DFT)] method with polarizable continuum model (PCM) for the analysis of molecular properties including both nuclear quantum effect and solvent effect. The chemical shifts and H/D isotope shifts of the picolinic acid N-oxide (PANO) molecule in chloroform and acetonitrile solvents are applied by B3LYP electron exchange-correlation functional for our MC-(HF+DFT) method with PCM (MC-B3LYP/PCM). Our MC-B3LYP/PCM results for PANO are in reasonable agreement with the corresponding experimental chemical shifts and isotope shifts. We further investigated the applicability of our method for acetylacetone in several solvents.

Kanematsu, Yusuke; Tachikawa, Masanori [Quantum Chemistry Division, Yokohama City University, Seto 22-2, Kanazawa-ku, Yokohama 236-0027 (Japan)] [Quantum Chemistry Division, Yokohama City University, Seto 22-2, Kanazawa-ku, Yokohama 236-0027 (Japan)

2014-04-28T23:59:59.000Z

414

Nuclear Astrophysics  

E-Print Network [OSTI]

Nuclear physics has a long and productive history of application to astrophysics which continues today. Advances in the accuracy and breadth of astrophysical data and theory drive the need for better experimental and theoretical understanding of the underlying nuclear physics. This paper will review some of the scenarios where nuclear physics plays an important role, including Big Bang Nucleosynthesis, neutrino production by our sun, nucleosynthesis in novae, the creation of elements heavier than iron, and neutron stars. Big-bang nucleosynthesis is concerned with the formation of elements with A nuclear physics inputs required are few-nucleon reaction cross sections. The nucleosynthesis of heavier elements involves a variety of proton-, alpha-, neutron-, and photon-induced reactions, coupled with radioactive decay. The advent of radioactive ion beam facilities has opened an important new avenue for studying these processes, as many involve radioactive species. Nuclear physics also plays an important role in neutron stars: both the nuclear equation of state and cooling processes involving neutrino emission play a very important role. Recent developments and also the interplay between nuclear physics and astrophysics will be highlighted.

Carl R. Brune

2005-02-28T23:59:59.000Z

415

nuclear security | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

security | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our...

416

Nuclear Incident Team | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Incident Team | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing...

417

nuclear navy | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

navy | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our...

418

nuclear threat science | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

threat science | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing...

419

Nuclear Operations | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

420

Two phase partially miscible flow and transport modeling in porous media: application to gas migration in a nuclear waste repository  

E-Print Network [OSTI]

We derive a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological repository for radioactive waste. This model includes capillary effects and the gas high diffusivity. Moreover, it is written in variables (total hydrogen mass density and liquid pressure) chosen in order to be consistent with gas appearance or disappearance. We discuss the well possedness of this model and give some computational evidences of its adequacy to simulate gas generation in a water saturated repository.

Alain Bourgeat; Mladen Jurak; Farid Smaï

2008-02-29T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Two phase partially miscible flow and transport modeling in porous media: application to gas migration in a nuclear waste repository  

E-Print Network [OSTI]

We derive a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological repository for radioactive waste. This model includes capillary effects and the gas high diffusivity. Moreover, it is written in variables (total hydrogen mass density and liquid pressure) chosen in order to be consistent with gas appearance or disappearance. We discuss the well possedness of this model and give some computational evidences of its adequacy to simulate gas generation in a water saturated repository.

Bourgeat, Alain; Smaï, Farid

2008-01-01T23:59:59.000Z

422

Nuclear Radius and Nuclear Forces  

Science Journals Connector (OSTI)

The difference between the radius of the nuclear matter distribution and the nuclear force radius, RN?1.4A13×10-13 cm, for heavy nuclei (A>100) is interpreted as a consequence of the finite range of nuclear forces. Assuming that the nuclear matter distribution coincides with the charge distribution as determined at Stanford (RC=1.12A13×10-13 cm is the distance at which the charge density falls to one half value) we sum up the nuclear interactions of an incident nucleon for various proposed internucleon potentials, V(r). We also evaluate contributions from the spin, charge, and matter polarizations induced in the nuclear distributions by the incident nucleon as a test of the convergence of these calculations. The aim here is to infer some features of nuclear forces which satisfy saturation requirements and at the same time give rise to an appreciable nuclear attraction for an incident nucleon at RN. Analyses of the scattering of neutrons and protons by heavy nuclei suggest a nuclear attraction ?14 Mev at a distance RN.These considerations are primarily sensitive to the long range behavior of the direct, central part of V(r). The key point which emerges from them is that the nuclear forces must contain long range (~ meson Compton wavelength) direct, central attractions which will be felt by an incident nucleon at RN before the shorter range repulsions (hard cores, many-body forces, or exchange interactions), which are responsible for saturation, become effective. Such interactions can be constructed phenomenologically, but are not found in recent meson-theoretically deduced potentials.

S. D. Drell

1955-10-01T23:59:59.000Z

423

Nuclear condensation  

Science Journals Connector (OSTI)

This work draws an analogy between a heated nucleus breaking up into clusters and a liquid undergoing a phase transition to a gas in which droplets appear. The critical temperature and density in the nucleus are investigated using a Skyrme effective interaction and finite temperature Hartree-Fock theory. The energy and pressure as a function of density are calculated. The effects of compressibility, effective mass, and binding energy per particle on the critical temperature and critical density of nuclear systems is developed. In some cases, analytic expressions for these quantities can be obtained.NUCLEAR REACTIONS Phase transitions in hot nuclear matter.

H. Jaqaman; A. Z. Mekjian; L. Zamick

1983-06-01T23:59:59.000Z

424

Nuclear War  

SciTech Connect (OSTI)

Several chapters in Last Aid warrant the attention of the medical profession. What is known and not known about acute biologic effects following a nuclear explosion is described. The social, physical, and environmental impact of nuclear war on urban population centers is described. How nuclear weapons could affect the composition of the ozone layer and the effects this could have on human survival, including possible interruption of the aquatic ecosystem to produce single-cell organisms for the food cycle, especially seafood is noted.

MacLeod, G.K.

1983-01-01T23:59:59.000Z

425

Fuel Cycle Science & Technology | Nuclear Science | ORNL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Advanced Fuel Cycle Systems Radiochemical Separation & Processing Recycle & Waste Management Uranium Enrichment Used Nuclear Fuel Storage, Transportation, and Disposal Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research Areas | Fuel Cycle Science & Technology SHARE Fuel Cycle Science and Technology The ORNL expertise and experience across the entire nuclear fuel cycle is underpinned by extensive facilities and a comprehensive modeling and simulation capability ORNL supports the understanding, development, evaluation and deployment of

426

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 54, NO. 6, DECEMBER 2007 2363 Soft Error Trends and New Physical Model for  

E-Print Network [OSTI]

. D. Yoder, Senior Member, IEEE, and Muhammad Ashraful Alam, Fellow, IEEE Abstract--We model the soft of today's processors and this trend is expected to reach to 90% by year 2011 [1], [2]. Although SRAM

Alam, Muhammad A.

427

Experiments to investigate direct containment heating phenomena with scaled models of the Zion Nuclear Power Plant in the Surtsey Test Facility  

SciTech Connect (OSTI)

The Surtsey Facility at Sandia National Laboratories (SNL) is used to perform scaled experiments that simulate hypothetical high-pressure melt ejection (HPME) accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effect of specific phenomena associated with direct containment heating (DCH) on the containment load, such as the effect of physical scale, prototypic subcompartment structures, water in the cavity, and hydrogen generation and combustion. In the Integral Effects Test (IET) series, 1:10 linear scale models of the Zion NPP structures were constructed in the Surtsey vessel. The RPV was modeled with a steel pressure vessel that had a hemispherical bottom head, which had a 4-cm hole in the bottom head that simulated the final ablated hole that would be formed by ejection of an instrument guide tube in a severe NPP accident. Iron/alumina/chromium thermite was used to simulate molten corium that would accumulate on the bottom head of an actual RPV. The chemically reactive melt simulant was ejected by high-pressure steam from the RPV model into the scaled reactor cavity. Debris was then entrained through the instrument tunnel into the subcompartment structures and the upper dome of the simulated reactor containment building. The results of the IET experiments are given in this report.

Allen, M.D.; Pilch, M.M.; Blanchat, T.K.; Griffith, R.O. [Sandia National Labs., Albuquerque, NM (United States); Nichols, R.T. [Ktech Corp., Albuquerque, NM (United States)

1994-05-01T23:59:59.000Z

428

Climate Change, Nuclear Power and Nuclear  

E-Print Network [OSTI]

Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters Rob Goldston MIT IAP biomass wind hydro coal CCS coal nat gas CCS nat gas nuclear Gen IV nuclear Gen III nuclear Gen II 5-1 Electricity Generation: CCS and Nuclear Power Technology Options Available Global Electricity Generation WRE

429

Isospin-dependent properties of asymmetric nuclear matter in relativistic mean field models RID A-2398-2009  

E-Print Network [OSTI]

values at other densities are poorly known [6,7]. Various microscopic and phenomenological models, such as the relativistic Dirac-Brueckner-Hartree-Fock (DBHF) [16?22] and nonrelativistic Brueckner-Hartree-Fock (BHF) [23,24] approaches... values at other densities are poorly known [6,7]. Various microscopic and phenomenological models, such as the relativistic Dirac-Brueckner-Hartree-Fock (DBHF) [16?22] and nonrelativistic Brueckner-Hartree-Fock (BHF) [23,24] approaches...

Chen, Lie-Wen; Ko, Che Ming; Li, Bao-An.

2007-01-01T23:59:59.000Z

430

Development and Testing of a Groundwater Management Model for the Faultless Underground Nuclear Test, Central Nevada Test Area  

SciTech Connect (OSTI)

This document describes the development and application of a user-friendly and efficient groundwater management model of the Central Nevada Test Area (CNTA) and surrounding areas that will allow the U.S. Department of Energy and state personnel to evaluate the impact of future proposed scenarios. The management model consists of a simple hydrologic model within an interactive groundwater management framework. This framework is based on an object user interface that was developed by the U.S. Geological Survey and has been used by the Desert Research Institute researchers and others to couple disparate environmental resource models, manage the necessary temporal and spatial data, and evaluate model results for management decision making. This framework was modified and applied to the CNTA and surrounding Hot Creek Valley. The utility of the management model was demonstrated through the application of hypothetical future scenarios including mineral mining, regional expansion of agriculture, geothermal energy production, and export of water to large urban areas outside the region. While the results from some of the scenarios indicated potential impacts to the region near CNTA and others did not, together they demonstrate the usefulness of the management tool for managers who need to evaluate the impact proposed changes in groundwater use in or near CNTA may have on radionuclide migration.

Douglas P. Boyle; Gregg Lamorey; Scott Bassett; Greg Pohll; Jenny Chapman

2006-01-25T23:59:59.000Z

431

An ex Vivo Model for the Study of Tumor Metabolism by Nuclear Magnetic Resonance: Characterization of the Phosphorus-31 Spectrum of the Isolated Perfused Morris Hepatoma 7777  

Science Journals Connector (OSTI)

...el al. In vivo "P nuclear magnetic resonance spectroscopy...M. J. Phosphorus nuclear magnetic resonance of...Nunnally, R. L. High-energy phosphates and function...monilored by in vivo 31P nuclear magnelic resonance speclroscopy...adminislralion on Ihe energy slale of in vivo liver...

Robert A. Graham; Truman R. Brown; and Ronald A. Meyer

1991-02-01T23:59:59.000Z

432

Microsoft Word - PC-000566_0_White Paper_rel.doc  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Plant (NGNP). Other countries, including Russia, Japan, South Korea, China, South Africa, and France are also developing this technology, and large-scale deployment of VHTR...

433

Nuclear Medicine  

Science Journals Connector (OSTI)

Nuclear medicine is the branch of medicine that is concerned with the use of in the diagnosis, management, and treatment of disease. It usually uses small amounts of radioactive materials or , substances th...

2008-01-01T23:59:59.000Z

434

Nuclear viscosity  

Science Journals Connector (OSTI)

The decay rate of momentum in a nuclear reaction is given by an exact formula expressed in terms of the T matrix. A special case, where a viscosity coefficient can be estimated, is considered.

B. Giraud; J. Le Tourneux; E. Osnes

1975-01-01T23:59:59.000Z

435

Nuclear Waste  

Science Journals Connector (OSTI)

Nuclear waste is radioactive material no longer considered valuable...238U, 235U, and 226Ra (where the latter decays to 222Rn gas by emitting an alpha particle) or formed through fission of fissile radioisotopes ...

Rob P. Rechard

2014-01-01T23:59:59.000Z

436

Nuclear Golf  

E-Print Network [OSTI]

Broadcast Transcript: Pay no attention to that nuclear warhead behind the 18th hole; just shout "Fore!" and drive your Titleist down the fairway. In a development that is bizarre even by North Korean standards, the country ...

Hacker, Randi; Tsutsui, William

2006-12-06T23:59:59.000Z

437

Nuclear Fuels  

Science Journals Connector (OSTI)

The core of a nuclear reactor is composed of a controlled critical configuration of a fissile material, which in strict a sense is the fuel. This fissile material is contained in a matrix, normally a ceramic c...

Rudy J. M. Konings; Thierry Wiss…

2011-01-01T23:59:59.000Z

438

Nuclear Energy!  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

driver, see the Nuclear Clean Air Energy race car and receive a special clean energy patch on October 21 from 6:30 - 7:30 p.m. Space is limited RSVP by October 4 Hands-on...

439

Nuclear forces  

SciTech Connect (OSTI)

These lectures present an introduction into the theory of nuclear forces. We focus mainly on the modern approach, in which the forces between nucleons emerge from low-energy QCD via chiral effective field theory.

Machleidt, R. [Department of Physics, University of Idaho, Moscow, Idaho 83844 (United States)

2013-06-10T23:59:59.000Z

440

Large low-energy $M1$ strength for $^{56,57}$Fe within the nuclear shell model  

E-Print Network [OSTI]

A strong enhancement at low $\\gamma$-ray energies has recently been discovered in the $\\gamma$-ray strength function of $^{56,57}$Fe. In this work, we have for the first time obtained theoretical $\\gamma$ decay spectra for states up to $\\approx 8$ MeV in excitation for $^{56,57}$Fe. We find large $B(M1)$ values for low $\\gamma$-ray energies that provide an explanation for the experimental observations. The role of mixed $E2$ transitions for the low-energy enhancement is addressed theoretically for the first time, and it is found that they contribute a rather small fraction. Our calculations clearly show that the high-$\\ell$ ($=f$) diagonal terms are most important for the strong low-energy $M1$ transitions. As such types of $0\\hbar\\omega$ transitions are expected for all nuclei, our results indicate that a low-energy $M1$ enhancement should be present throughout the nuclear chart. This could have far-reaching consequences for our understanding of the $M1$ strength function at high excitation energies, with profound implications for astrophysical reaction rates.

B. Alex Brown; A. C. Larsen

2014-09-11T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Nuclear shadowing and ? photoproduction  

Science Journals Connector (OSTI)

? photoproduction on complex nuclei is reexamined using a generalized vector dominance model which succesfully predicts the oberved nuclear shadowing in real photoabsorption and deep inelastic scattering. This model is shown to give a good fit to ? photoproduction data on both nucleons and complex nuclei, in which the disagreement between the measured ?-? coupling and the ?-? coupling required by the simple vector dominance model is eliminated. The ?N total cross sections required are similar to those predicted by the additive quark model, and the magnitude of the correction to simple vector dominance is consistent with that inferred from the analysis of real photoabsorption and deep inelastic scattering.

A. Pautz and G. Shaw

1998-05-01T23:59:59.000Z

442

Nuclear power expansion: thinking about uncertainty  

SciTech Connect (OSTI)

Nuclear power is one of many options available to achieve reduced carbon dioxide emissions. The real-option value model can help explain the uncertainties facing prospective nuclear plant developers in developing mitigation strategies for the development, construction, and operation of new nuclear plants. (author)

Holt, Lynne; Sotkiewicz, Paul; Berg, Sanford

2010-06-15T23:59:59.000Z

443

Monte carlo Techniques for the Comprehensive Modeling of Isotopic Inventories in Future Nuclear Systems and Fuel Cycles  

SciTech Connect (OSTI)

The development of Monte Carlo techniques for isotopic inventory analysis has been explored in order to facilitate the modeling of systems with flowing streams of material through varying neutron irradiation environments. This represents a novel application of Monte Carlo methods to a field that has traditionally relied on deterministic solutions to systems of first-order differential equations. The Monte Carlo techniques were based largely on the known modeling techniques of Monte Carlo radiation transport, but with important differences, particularly in the area of variance reduction and efficiency measurement. The software that was developed to implement and test these methods now provides a basis for validating approximate modeling techniques that are available to deterministic methodologies. The Monte Carlo methods have been shown to be effective in reproducing the solutions of simple problems that are possible using both stochastic and deterministic methods. The Monte Carlo methods are also effective for tracking flows of materials through complex systems including the ability to model removal of individual elements or isotopes in the system. Computational performance is best for flows that have characteristic times that are large fractions of the system lifetime. As the characteristic times become short, leading to thousands or millions of passes through the system, the computational performance drops significantly. Further research is underway to determine modeling techniques to improve performance within this range of problems. This report describes the technical development of Monte Carlo techniques for isotopic inventory analysis. The primary motivation for this solution methodology is the ability to model systems of flowing material being exposed to varying and stochastically varying radiation environments. The methodology was developed in three stages: analog methods which model each atom with true reaction probabilities (Section 2), non-analog methods which bias the probability distributions while adjusting atom weights to preserve a fair game (Section 3), and efficiency measures to provide local and global measures of the effectiveness of the non-analog methods (Section 4). Following this development, the MCise (Monte Carlo isotope simulation engine) software was used to explore the efficiency of different modeling techniques (Section 5).

Paul P.H. Wilson

2005-07-30T23:59:59.000Z

444

Countering Nuclear Terrorism | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism | National Nuclear Security Administration Countering Nuclear Terrorism | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Countering Nuclear Terrorism Home > Our Mission > Countering Nuclear Terrorism Countering Nuclear Terrorism NNSA provides expertise, practical tools, and technically informed policy

445

Nuclear reactor multiphysics via bond graph formalism  

E-Print Network [OSTI]

This work proposes a simple and effective approach to modeling nuclear reactor multiphysics problems using bond graphs. Conventional multiphysics simulation paradigms normally use operator splitting, which treats the ...

Sosnovsky, Eugeny

2014-01-01T23:59:59.000Z

446

Boyle temperature from SAFT, PC-SAFT and SAFT-VR equations of state  

Science Journals Connector (OSTI)

Abstract Second virial coefficient, Boyle temperature and Zeno (unit compressibility) line of some polar, non-polar and associating substances are calculated from SAFT, PC-SAFT and SAFT-VR equations of state (EOS). The results are compared with the corresponding values obtained from published correlations and available data. Our investigation shows that among the three \\{EOSs\\} considered the results obtained from the SAFT EOS are more accurate in predicting the Boyle temperature and the Zeno line. For second virial coefficient prediction, PC-SAFT is superior to SAFT for many substances and, for some alkanols and water; the results of SAFT-VR are more accurate. A modification on Tsonopoulos correlation for the second virial coefficient is presented for branched-alcohols and amines which has reduced the average absolute percent relative deviation (AAD%) from 13.22 to 3.52 and from 14.55 to 6.00 for four branched-alcohol and two amines, respectively. The proposed modification uses the Boyle temperature obtained from the SAFT EOS as a property of substance.

Samane Zarei; Farzaneh Feyzi

2013-01-01T23:59:59.000Z

447

Solubility of benzyl methacrylate/methacrylic acid copolymers in carbon dioxide-expanded acetone and correlation with the PC-SAFT equation of state  

Science Journals Connector (OSTI)

Abstract The high-pressure solid–liquid–vapor phase behavior of ternary systems comprising CO2, acetone, and benzyl methacrylate (BzMA)/methacrylic acid (MAA) copolymers has been probed experimentally and modeled with the PC-SAFT equation of state. Precipitation of BzMA/MAA copolymers required a larger overall CO2 mole fraction – and a correspondingly higher system pressure – in dilute solutions; however, a minimum in the precipitation pressure was observed for all copolymer compositions and temperatures near a CO2-free copolymer mass fraction of 0.05. These systems were characterized by a rapid reduction in copolymer solubility over a relatively narrow range of pressure (between 1.48 MPa and 2.86 MPa). The precipitation pressure increased with increasing temperature and BzMA mass fraction (per copolymer mass unit). The PC-SAFT EOS was successfully used to correlate the phase behavior data using binary interaction parameters with linear temperature dependence. The average relative error associated with the calculated precipitation pressure for each copolymer was 4.1% over the range of temperature and composition examined. Liquid phase carbon dioxide mole fraction was calculated to monotonically increase with increasing solid precipitation pressure, implying that carbon dioxide does not act as an antisolvent at higher (>5 wt%) copolymer fractions.

Scott M. Paap; Kurt Frey; Gregory R. Johnson; Jefferson W. Tester

2014-01-01T23:59:59.000Z

448

Reactor and Nuclear Systems Division (RNSD)  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

RNSD Home RNSD Home Research Groups Advanced Reactor Systems & Safety Nuclear Data & Criticality Safety Nuclear Security Modeling Radiation Safety Information Computational Center Radiation Transport Reactor Physics Thermal Hydraulics & Irradiation Engineering Used Fuel Systems Staff Details (CV/Bios) Publications Org Chart Contact Us ORNL Staff Only Research Groups Advanced Reactor Systems & Safety Nuclear Data & Criticality Safety Nuclear Security Modeling Radiation Safety Information Computational Center Radiation Transport Reactor Physics Thermal Hydraulics & Irradiation Engineering Used Fuel Systems Reactor and Nuclear Systems Division News Highlights U.S. Rep. Fleischmann touts ORNL as national energy treasure Martin Peng wins Fusion Power Associates Leadership Award

449

Nuclear Fuel Cycle and Waste Management Technologies - Nuclear Engineering  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Fuel Cycle and Nuclear Fuel Cycle and Waste Management Technologies Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Fuel Cycle and Waste Management Technologies Overview Bookmark and Share Much of the NE Division's research is directed toward developing software and performing analyses, system engineering design, and experiments to support the demonstration and optimization of the electrometallurgical

450

Distribution of oceanic 137Cs from the Fukushima Dai-ichi Nuclear Power Plant simulated numerically by a regional ocean model  

Science Journals Connector (OSTI)

Radioactive materials were released to the environment from the Fukushima Dai-ichi Nuclear Power Plant as a result of the reactor accident after the Tohoku earthquake and tsunami of 11 March 2011. The measured 137Cs concentration in a seawater sample near the Fukushima Dai-ichi Nuclear Power Plant site reached 68 kBq L?1 (6.8 × 104 Bq L?1) on 6 April. The two major likely pathways from the accident site to the ocean existed: direct release of high radioactive liquid wastes to the ocean and the deposition of airborne radioactivity to the ocean surface. By analysis of the 131I/137Cs activity ratio, we determined that direct release from the site contributed more to the measured 137Cs concentration than atmospheric deposition did. We then used a regional ocean model to simulate the 137Cs concentrations resulting from the direct release to the ocean off Fukushima and found that from March 26 to the end of May the total amount of 137Cs directly released was 3.5 ± 0.7 PBq ((3.5 ± 0.7) × 1015 Bq). The simulated temporal change in 137Cs concentrations near the Fukushima Daini Nuclear Power Plant site agreed well with observations. Our simulation results showed that (1) the released 137Cs advected southward along the coast during the simulation period; (2) the eastward-flowing Kuroshio and its extension transported 137C during May 2011; and (3) 137Cs concentrations decreased to less than 10 Bq L?1 by the end of May 2011 in the whole simulation domain as a result of oceanic advection and diffusion. We compared the total amount and concentration of 137Cs released from the Fukushima Dai-ichi reactors to the ocean with the 137Cs released to the ocean by global fallout. Even though the measured 137Cs concentration from the Fukushima accident was the highest recorded, the total released amount of 137Cs was not very large. Therefore, the effect of 137Cs released from the Fukushima Dai-ichi reactors on concentration in the whole North Pacific was smaller than that of past release events such as global fallout, and the amount of 137Cs expected to reach other oceanic basins is negligible comparing with the past radioactive input.

Daisuke Tsumune; Takaki Tsubono; Michio Aoyama; Katsumi Hirose

2012-01-01T23:59:59.000Z

451

Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program Issues and Strategy for Fusion Nuclear Science Facility (FNSF)  

E-Print Network [OSTI]

Need for Fusion Nuclear Science and Technology ProgramFusion Nuclear Science and Technology Program ­Issues and Strategy for Fusion Nuclear Science Facility (FNSF) ­Key R&D Areas to begin NOW (modeling 12, 2010 #12;Fusion Nuclear Science and Technology (FNST) FNST is the science engineering technology

Abdou, Mohamed

452

Dynamic Modeling and Control of Nuclear Reactors Coupled to Closed-Loop Brayton Cycle Systems using SIMULINK{sup TM}  

SciTech Connect (OSTI)

The operation of space reactors for both in-space and planetary operations will require unprecedented levels of autonomy and control. Development of these autonomous control systems will require dynamic system models, effective control methodologies, and autonomous control logic. This paper briefly describes the results of reactor, power-conversion, and control models that are implemented in SIMULINK{sup TM} (Simulink, 2004). SIMULINK{sup TM} is a development environment packaged with MatLab{sup TM} (MatLab, 2004) that allows the creation of dynamic state flow models. Simulation modules for liquid metal, gas cooled reactors, and electrically heated systems have been developed, as have modules for dynamic power-conversion components such as, ducting, heat exchangers, turbines, compressors, permanent magnet alternators, and load resistors. Various control modules for the reactor and the power-conversion shaft speed have also been developed and simulated. The modules are compiled into libraries and can be easily connected in different ways to explore the operational space of a number of potential reactor, power-conversion system configurations, and control approaches. The modularity and variability of these SIMULINK{sup TM} models provides a way to simulate a variety of complete power generation systems. To date, both Liquid Metal Reactors (LMR), Gas Cooled Reactors (GCR), and electric heaters that are coupled to gas-dynamics systems and thermoelectric systems have been simulated and are used to understand the behavior of these systems. Current efforts are focused on improving the fidelity of the existing SIMULINK{sup TM} modules, extending them to include isotopic heaters, heat pipes, Stirling engines, and on developing state flow logic to provide intelligent autonomy. The simulation code is called RPC-SIM (Reactor Power and Control-Simulator)

Wright, Steven A.; Sanchez, Travis [Sandia National Laboratories, Org 6872 MS-1146, PO Box 5800 Albuquerque, New Mexico 87185 (United States)

2005-02-06T23:59:59.000Z

453

Economic and environmental analysis of power generation expansion in Japan considering Fukushima nuclear accident using a multi-objective optimization model  

Science Journals Connector (OSTI)

Nuclear power has long been a cornerstone of energy policy in Japan, a country with few natural resources of its own. However, following on from the Fukushima Daiichi accident, the Japanese government is now in the throes of reviewing its nuclear power policy. On the other hand, under continuing policies of greenhouse gas reduction, it is crucial to consider scenarios for the country to realize an economic, safe and low-carbon power generation system in the future. Therefore, in the present study, economic and environmental analysis was conducted on the power generation system in Japan up to 2030 using a multi-objective optimization methodology. Four nuclear power scenarios were proposed in light of the nuclear accident: (1) actively anti-nuclear; (2) passively negative towards nuclear; (3) conservative towards nuclear; and (4) active expansion of nuclear power. The obtained capacity mix, generation mix, generation cost, CO2 emissions and fuel consumption of the scenarios were compared and analysed. The obtained results show that the large scale penetration of PV (photovoltaic), wind and LNG (Liquefied Natural Gas) power can partly replace nuclear power, however, removing nuclear power entirely was not suggested from economic, environmental and energy security perspectives.

Qi Zhang; Benjamin C. Mclellan; Tetsuo Tezuka; Keiichi N. Ishihara

2012-01-01T23:59:59.000Z

454

Defense and nuclear technologies  

SciTech Connect (OSTI)

Fulfilling our national security and stockpile stewardship responsibilities requires tremendous scientific and technical breadth: from esoteric theoretical physics and computational modeling to materials science and precision engineering. Because there exists no broad industrial or university base from which to draw expertise in nuclear weapon science and technology, we rely heavily on formal peer reviews and informal exchanges with our sister laboratory at Los Alamos. LLNL has an important, long-term role in the nation`s nuclear weapons program. We are responsible for four of the ten weapon systems in the enduring US stockpile (three of nine after 2002), including the only systems that incorporate all modern safety features. For years to come, we will be responsible for these weapons and for the problems that will inevitably arise. Our nuclear expertise will also play a crucial role as the US attempts to deal effectively with the threat of nuclear proliferation. This past year brought the culmination of our response to profound changes in the nation`s defense needs as we restructured and refocused our activities to address the Administration`s goal of reducing global nuclear danger. We made major contributions to important national security issues in spite of severe fiscal constraints.

NONE

1995-01-01T23:59:59.000Z

455

Modeling regional seismic waves from underground nuclear explosion. Report for 17 March 1987-30 March 88  

SciTech Connect (OSTI)

Two main topics are presented: the effects of ocean continent transition zones on L - g waves; and modeling regional Love waves with 2-D velocity structures. Hybrid regional and teleseismic SH mode sum seismograms are produced after propagation through a regional transition zone or other heterogeneity that exists as part of a longer, mostly plane-layered, path. In particular the effects of ocean continent transition regions of geometry for propagation along a partially oceanic path is at most a factor of four. Extending the oceanic path length changes this factor to at most 6. This is inadequate to explain the observed attenuation of Lg. Thus, additional effects, must be considered to provide a complete explanation of the attenuation of Lg. Long period seismograms recorded at Pasadena of earthquakes occurring along a profile to Imperial Valley are studied in terms of source phenomena versus path effects. Some of the events have known source parameters, determined by teleseismic or near-field studies, and are used as master events in a forward modeling exercise to derive the Green's functions that describe the propagation effects along the profile. Both timing and waveforms of records are matched by synthetics calculated from 2-dimensional velocity models. The best 2-dimensional section begins at Imperial Valley with a thin crust containing the basin structure and thickens towards Pasadena.

Clayton, R.W.; Harkrider, D.G.; Helmberger, D.V.

1988-05-09T23:59:59.000Z

456

Nuclear Induction  

Science Journals Connector (OSTI)

The magnetic moments of nuclei in normal matter will result in a nuclear paramagnetic polarization upon establishment of equilibrium in a constant magnetic field. It is shown that a radiofrequency field at right angles to the constant field causes a forced precession of the total polarization around the constant field with decreasing latitude as the Larmor frequency approaches adiabatically the frequency of the r-f field. Thus there results a component of the nuclear polarization at right angles to both the constant and the r-f field and it is shown that under normal laboratory conditions this component can induce observable voltages. In Section 3 we discuss this nuclear induction, considering the effect of external fields only, while in Section 4 those modifications are described which originate from internal fields and finite relaxation times.

F. Bloch

1946-10-01T23:59:59.000Z

457

Collaborating Organizations - Nuclear Data Program, Nuclear Engineering  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Collaborating Organizations Collaborating Organizations Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program Collaborating Organizations Bookmark and Share National Nuclear Data Center, Brookhaven National Laboratory, Upton, New York. International Nuclear Structure and Decay Data Network, coordinated by IAEA, Vienna, Austria Heavy-Ion Nuclear Physics Group, Physics Division, Argonne National Laboratory, Argonne, Illinois. Nuclear Spectroscopy Group, Department of Nuclear Physics,

458

Extended sum-rule model view of light and intermediate mass fragment emission in nuclear reactions at intermediate energies  

Science Journals Connector (OSTI)

The original sum-rule model worked out by Wilczy?ski et al. and successfully used for a global description of complete and incomplete fusion reactions has been extended by a term accounting for dissipative processes of the dinuclear system on its way to fusion. When applying to light- and heavy-ion collisions with various targets at energies in the transitional region, the new term proves to be rather essential for reproducing the element distributions of the fragments emitted from rather asymmetric systems.

I. M. Brncu?; H. Rebel; J. Wentz; V. Corcalciuc

1990-11-01T23:59:59.000Z

459

Nuclear Science & Technology  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Science & Technology Nuclear Science & Technology Nuclear Science & Technology1354608000000Nuclear Science & TechnologySome of these resources are LANL-only and will require Remote Access. /No/ Nuclear Science & Technology Some of these resources are LANL-only and will require Remote Access. Key Resources Databases Organizations Journals Key Resources International Atomic Energy Agency IAEA scientific and technical publications cover areas of nuclear power, radiation therapy, nuclear security, nuclear law, and emergency repose. Search under Publications/Books and Reports for scientific books, standards, technical guides and reports National Nuclear Data Center Nuclear physics data for basic nuclear research and for applied nuclear technologies, operated by Brookhaven.

460

NUCLEAR PROXIMITY FORCES  

E-Print Network [OSTI]

One might summarize of nuclear potential energy has beendegree of freedom) for the nuclear interaction between anyUniversity of California. Nuclear Proximity Forces 'I< at

Randrup, J.

2011-01-01T23:59:59.000Z

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461

Nuclear Nonproliferation Programs | ORNL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Nonproliferation Programs SHARE Nuclear Nonproliferation Programs image Oak Ridge National Laboratory covers the entire spectrum of nuclear nonproliferation work, from...

462

Nuclear Data | More Science | ORNL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Data SHARE Nuclear Data Nuclear Data ORNL is a recognized, international leader in nuclear data research and development (R&D) to support nuclear applications analyses. For...

463

Nuclear Facilities | Department of Energy  

Energy Savers [EERE]

Nuclear Facilities Nuclear Facilities Nuclear Facilities Locator Map Numerical map data points indicate two or more nuclear facilities in the same geographic location. Nuclear...