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1

Nuclear Models  

SciTech Connect

The atomic nucleus is a typical example of a many-body problem. On the one hand, the number of nucleons (protons and neutrons) that constitute the nucleus is too large to allow for exact calculations. On the other hand, the number of constituent particles is too small for the individual nuclear excitation states to be explained by statistical methods. Another problem, particular for the atomic nucleus, is that the nucleon-nucleon (n-n) interaction is not one of the fundamental forces of Nature, and is hard to put in a single closed equation. The nucleon-nucleon interaction also behaves differently between two free nucleons (bare interaction) and between two nucleons in the nuclear medium (dressed interaction).Because of the above reasons, specific nuclear many-body models have been devised of which each one sheds light on some selected aspects of nuclear structure. Only combining the viewpoints of different models, a global insight of the atomic nucleus can be gained. In this chapter, we revise the the Nuclear Shell Model as an example of the microscopic approach, and the Collective Model as an example of the geometric approach. Finally, we study the statistical properties of nuclear spectra, basing on symmetry principles, to find out whether there is quantum chaos in the atomic nucleus. All three major approaches have been rewarded with the Nobel Prize of Physics. In the text, we will stress how each approach introduces its own series of approximations to reduce the prohibitingly large number of degrees of freedom of the full many-body problem to a smaller manageable number of effective degrees of freedom.

Fossion, Ruben [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, Apartado Postal 70-543, Mexico D. F., C.P. 04510 (Mexico)

2010-09-10T23:59:59.000Z

2

Nuclear Fuels - Modeling  

Science Conference Proceedings (OSTI)

Mar 12, 2012... for the Current and Advanced Nuclear Reactors: Nuclear Fuels - Modeling .... Using density functional theory (DFT), we have predicted that ...

3

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

NLE Websites -- All DOE Office Websites (Extended Search)

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

4

DOBSON: a Pentium-based SMP Linux PC Beowulf for distributed-memory high resolution environment modelling  

Science Conference Proceedings (OSTI)

With the increasing computational speed of PC processors, lowering hardware prices, and the increasing accessibility of open source software, PC clusters have become an attractive option for exploring budgetary high performance computation on high resolution ... Keywords: 07.05.Bx, 92.60.Fm, 92.60.Jq, 92.60.Sz, Air pollution modelling, Beowulf, Cluster computing, Distributed-memory computing

K. -Y. Wang; D. E. Shallcross; S. M. Hall; Y. -H. Lo; C. Chou; D. Chen

2005-10-01T23:59:59.000Z

5

2002 EIA Models Directory - Energy Information Administration  

U.S. Energy Information Administration (EIA)

Levelized Nuclear Fuel Cycle Cost Model (LNFCC-PC) Propane Market Model (PPMM) Short-Term Hydroelectric Generation Model (STHGM)

6

Nuclear models on a lattice  

E-Print Network (OSTI)

We present the first results of a quantum field approach to nuclear models obtained by lattice techniques. Renormalization effects for fermion mass and coupling constant in case of scalar and pseudoscalar interaction lagrangian densities are discussed.

F. De Soto; J. Carbonell; C. Roiesnel; Ph. Boucaud; J. P. Leroy; O. Pene

2005-11-04T23:59:59.000Z

7

Waste Form Performance Modeling [Nuclear Waste Management using...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

8

Unit Process Modeling [Nuclear Waste Management using Electrometallurg...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

9

Nuclear Systems Modeling and Design Analysis - Nuclear Engineering Division  

NLE Websites -- All DOE Office Websites (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

10

"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

11

Application of nuclear models to neutron nuclear cross section calculations  

Science Conference Proceedings (OSTI)

Nuclear theory is used increasingly to supplement and extend the nuclear data base that is available for applied studies. Areas where theoretical calculations are most important include the determination of neutron cross sections for unstable fission products and transactinide nuclei in fission reactor or nuclear waste calculations and for meeting the extensive dosimetry, activation, and neutronic data needs associated with fusion reactor development, especially for neutron energies above 14 MeV. Considerable progress has been made in the use of nuclear models for data evaluation and, particularly, in the methods used to derive physically meaningful parameters for model calculations. Theoretical studies frequently involve use of spherical and deformed optical models, Hauser-Feshbach statistical theory, preequilibrium theory, direct-reaction theory, and often make use of gamma-ray strength function models and phenomenological (or microscopic) level density prescriptions. The development, application, and limitations of nuclear models for data evaluation are discussed, with emphasis on the 0.1 to 50 MeV energy range. (91 references).

Young, P.G.

1982-01-01T23:59:59.000Z

12

Modeling Nuclear Fuels with a Combined Potts-Phase Field Model  

Science Conference Proceedings (OSTI)

Symposium, Materials Science Challenges for Nuclear Applications. Presentation Title, Modeling Nuclear Fuels with a Combined Potts-Phase Field Model.

13

Teaching With Tablet Pc's  

E-Print Network (OSTI)

Tablet PC's are traditional notebook computers with the ability to process digital ink by writing with a stylus. They have recently attracted attention as a potential tool for educational use. This paper describes the author's experience using the Tablet PC to conduct a CS1 course and a software engineering (SWE) course. The SWE course consisted primarily of PowerPoint lectures while the CS1 course consisted primarily of hand-written material. For both courses the Tablet PC was used in the classroom as a digital whiteboard by connecting it to a data projector. The lecture material was archived and accessed electronically for future reference by the students. To capture real-time gesturing and audio commentary, the CS1 course was recorded using screen capture technology. Outside of the classroom, the Tablet PC is also a useful tool for grading, creating lecture material, and capturing meeting notes. Student feedback regarding use of the Tablet PC has been extremely positive.

Kenrick Mock University; Kenrick Mock

2004-01-01T23:59:59.000Z

14

NUCLEAR ENERGY SYSTEM COST MODELING  

Science Conference Proceedings (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

15

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

16

Long-term deformational simulation of PC bridges based on the thermo-hygro model of micro-pores in cementitious composites  

Science Conference Proceedings (OSTI)

Creep deflections that greatly exceed the predicted values by the linear creep law are being found in measurements on actual PC bridge viaducts. In this study, structural creep deformations were reproduced by using the multi-scale coupled thermo-hygro and mechanical modeling which enables to deal with an interaction of chemo-physical events of differing dimensions ranging from the kinematics of moisture in micro-pores to the macroscopic structural mechanics, and the effect of various factors was analytically investigated. The numerical analysis approximately reproduced the excessive deflection measured on an actual bridge viaduct. It was confirmed that the creep bending of the viaduct having the hollow cross-section varies significantly due to the ambient temperature, humidity and the structural specific surface area. The macroscopic structural responses in association with the thermodynamic state of moisture in the micro-pores are also discussed.

Maekawa, Koichi, E-mail: Maekawa@concrete.t.u-tokyo.ac.jp; Chijiwa, Nobuhiro; Ishida, Tetsuya

2011-12-15T23:59:59.000Z

17

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

E-Print Network (OSTI)

Nuclear winter revisited with a modern climate model and current nuclear arsenals: Still of climate model simulations of the response to smoke and dust from a massive nuclear exchange between the superpowers could be summarized as ``nuclear winter,'' with rapid temperature, precipitation, and insolation

Robock, Alan

18

A knowledge representation model for the nuclear power generation domain  

Science Conference Proceedings (OSTI)

A knowledge representation model for the nuclear power field is proposed. The model is a generalized production rule function inspired by a neural network approach that enables the representation of physical systems of nuclear power plants. The article ... Keywords: Knowledge representation, Nuclear power plant, Physical systems, Production rules

Thiago Tinoco Pires

2007-11-01T23:59:59.000Z

19

Integrated Computational Modeling of Materials for Nuclear Energy  

Science Conference Proceedings (OSTI)

Nuclear fuel and primary cooling system structural components are exposed to elevated ... models for safety and performance evaluation of nuclear reactors but also for the ... Continuum Theory of Defects and Materials Response to Irradiation

20

Nuclear Asset Management (NAM) Process Model  

Science Conference Proceedings (OSTI)

Nuclear asset management (NAM) is the process of making operational, resource allocation, and risk management decisions at all levels of a nuclear generation business to maximize nuclear power plant value to stakeholders, while maintaining safety to the public and the plant staff. To support nuclear utilities in achieving these goals, the Nuclear Energy Institute (NEI) issued NEI AP 940, Nuclear Asset Management Process Description and Guideline, in May 2005. This document provides high-level guidance. H...

2007-12-20T23:59:59.000Z

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.


21

Nuclear Power Plant Fire-Modeling Applications Guide  

Science Conference Proceedings (OSTI)

This report replaces EPRI 1002981, Fire Modeling Guide for Nuclear Power Plant Applications, August 2002, as guidance for fire-modeling practitioners in nuclear power plants (NPPs). The report has benefited from insights gained since 2002 on the predictive capability of selected fire models to improve confidence in the use of fire modeling in NPP decision-making.

2009-12-22T23:59:59.000Z

22

NEAMS: The Nuclear Energy Advanced Modeling and Simulation Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

23

Comparison of nuclear mass models at nuclearmasses.org  

Science Conference Proceedings (OSTI)

Nuclear masses are crucial in many astrophysics studies, as well as other areas of basic and applied nuclear science. There are now many different global theoretical models of nuclear masses - but choosing the best model for a given application can be challenging. The suite of codes online at nuclearmasses.org greatly facilitates the comparison of nuclear models with evaluated masses as well as the intercomparison of theoretical models. We demonstrate the utility of this suite by comparing the RMS deviations of 13 different theoretical mass models from the AME2003 evaluated masses over mass ranges appropriate for astrophysics.

Smith, Michael S.; Nesaraja, Caroline D.; Lingerfelt, Eric J.; Koura, Hiroyuki; Kondev, Filip G. [Physics Division, Oak Ridge National Lab, Oak Ridge, Tennessee, 37831-6354 (United States); Computer Science and Mathematics Division, Oak Ridge National Lab, Oak Ridge, Tennessee, 37831-6354 (United States) and Physics Division, Oak Ridge National Lab, Oak Ridge, Tennessee, 37831-6354 (United States); Japan Atomic Energy Agency, Tokai, Naka-gun, Ibaraki, 319-1195 (Japan); Nuclear Engineering Division, Argonne National Laboratory, Argonne, Illinois, 60439 (United States)

2012-11-12T23:59:59.000Z

24

LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS  

E-Print Network (OSTI)

of a nuclear reactor with feedback," in: Applied Problems in the Theory of Oscillations [in RussianLIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS M. V. Bazhenov and E. F. Sabaev UDC of Nuclear Reactors [in Russian], l~nergoatomizdat, Moscow (1990). F. R. Gantmakher and V. A. Yakubovich

Bazhenov, Maxim

25

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

26

Multi-Scale Modeling of Irradiation Effects on Nuclear Fuel ...  

Science Conference Proceedings (OSTI)

Ab Initio-Based Rate Theory Modeling of Radiation Induced Segregation in ... Benchmarking of Structural Materials Pre-Selected for Advanced Nuclear Reactors.

27

Validation of Models and Simulations of Nuclear Fuels  

Science Conference Proceedings (OSTI)

Symposium, Characterization of Nuclear Reactor Materials and Components with ... Multi-scale theoretical models and computer simulations are often used to ...

28

HOTSPOT Health Physics codes for the PC  

SciTech Connect

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

29

Modeling and Simulation for Nuclear Reactors Hub | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

30

A Dynamical Systems Model for Nuclear Power Plant Risk Management  

Science Conference Proceedings (OSTI)

This report provides a mathematical dynamical systems model of the effect of plant processes and programs on nuclear plant safety. That is, it models the safety risk management process. Responses of this model to postulated changes in performance and coupling parameters were verified to be in accordance with experience from years of commercial nuclear power plant operation. A preliminary analysis of the model was performed using the techniques of dynamical systems theory to determine regions of operation...

2003-10-31T23:59:59.000Z

31

Modeling and simulation in analyzing geological repositories for high level nuclear waste  

Science Conference Proceedings (OSTI)

Nuclear energy is very often used to generate electricity. But first the energy must be released from atoms which can be done in two ways: nuclear fusion and nuclear fission. Nuclear power plants use nuclear fission to produce electrical energy. Electrical ... Keywords: modeling, nuclear energy, nuclear waste, nuclear waste storage, simulation

Dietmar P. F. Möller

2007-07-01T23:59:59.000Z

32

Nuclear Systems Modeling, Simulation & Validation | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

from single processors to the world's largest supercomputers. The DOE Nuclear Energy Hub (CASL, the Consortium for Advanced Simulation of Light Water Reactors) is a prominent...

33

Nuclear Systems Modeling & Simulation | More Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

from single processors to the world's largest supercomputers. The DOE Nuclear Energy Hub (CASL, the Consortium for Advanced Simulation of Light Water Reactors) is a prominent...

34

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

35

White paper on VU for Modeling Nuclear Energy Systems  

SciTech Connect

The purpose of this whitepaper is to provide a framework for understanding the role that Verification and Validation (V&V), Uncertainty Quantification (UQ) and Risk Quantification, collectively referred to as VU, is expected to play in modeling nuclear energy systems. We first provide background for the modeling of nuclear energy based systems. We then provide a brief discussion that emphasizes the critical elements of V&V as applied to nuclear energy systems but is general enough to cover a broad spectrum of scientific and engineering disciplines that include but are not limited to astrophysics, chemistry, physics, geology, hydrology, chemical engineering, mechanical engineering, civil engineering, electrical engineering, nu nuclear engineering material clear science science, etc. Finally, we discuss the critical issues and challenges that must be faced in the development of a viable and sustainable VU program in support of modeling nuclear energy systems.

Klein, R; Turinsky, P

2009-05-07T23:59:59.000Z

36

Parity Dependent Shell Model Level Densities for Nuclear Astrophysics  

E-Print Network (OSTI)

Recently, we developed a methodology [1-4] of calculating the spin and parity dependent shell model nuclear level density, which is a very useful ingredient in the Huaser-Feshbach theory for calculating reaction rates for nuclear astrophysics[5]. We developed new techniques based on nuclear statistical spectroscopy [6] to calculate the spin and parity projected moments of the nuclear shell model Hamiltonian, that can be further used to obtain an accurate description of the nuclear level density up to about 15 MeV excitation energy. These techniques were fully tested for the sd-shell nuclei and some light f p-shell nuclei, by comparing with the level density obtained from exact shell model diagonalization. Here we present for the first time comparisons with the exact shell model diagonalization for nuclei heavier than 56 Ni, in a model space spanned by the f 5/2, p 3/2, p 1/2 and g 9/2 orbits. The ratio of nuclear level densities of opposite parities is also discussed. This analysis was possible due to a new and very efficient nuclear shell model code [7] that can provide a large number of states of given spin and parity. PoS(NIC X)132

Mike Scott; Mihai Horoi; Mike Scott

2008-01-01T23:59:59.000Z

37

Fire models for assessment of nuclear power plant fires  

SciTech Connect

This paper reviews the state-of-the-art in available fire models for the assessment of nuclear power plants fires. The advantages and disadvantages of three basic types of fire models (zone, field, and control volume) and Sandia's experience with these models will be discussed. It is shown that the type of fire model selected to solve a particular problem should be based on the information that is required. Areas of concern which relate to all nuclear power plant fire models are identified. 17 refs., 6 figs.

Nicolette, V.F.; Nowlen, S.P.

1989-01-01T23:59:59.000Z

38

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

39

Modeling and simulation of Ran-mediated nuclear import  

E-Print Network (OSTI)

We present here a detailed description of the model of ran-driven nuclear transduction in living cells to be published elswere. The mathematical model presented is the first to account for the active transport of molecules along the cytoplasmic microtubules. All parameters entering the models are thoroughly discussed. The simulations reproduce the behavior observed experimentally.

A. Cangiani

2009-07-06T23:59:59.000Z

40

First Gogny-Hartree-Fock-Bogoliubov Nuclear Mass Model  

Science Conference Proceedings (OSTI)

We present the first Gogny-Hartree-Fock-Bogoliubov (HFB) model which reproduces nuclear masses with an accuracy comparable with the best mass formulas. In contrast with the Skyrme-HFB nuclear-mass models, an explicit and self-consistent account of all the quadrupole correlation energies are included within the 5D collective Hamiltonian approach. The final rms deviation with respect to the 2149 measured masses is 798 keV. In addition, the new Gogny force is shown to predict nuclear and neutron matter properties in agreement with microscopic calculations based on realistic two- and three-body forces.

Goriely, S.; Hilaire, S.; Girod, M.; Peru, S. [Institut d'Astronomie et d'Astrophysique, CP-226, Universite Libre de Bruxelles, 1050 Brussels (Belgium); CEA, DAM, DIF, F-91297, Arpajon (France)

2009-06-19T23:59:59.000Z

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.


41

PC Intel AMT AMT VM AMT AMT vAMT  

E-Print Network (OSTI)

#12;PC VM AMT VM PC VM AMT AMT vAMT vAMT AMT VM AMT vAMT PC AMT 2 AMT 3 vAMT vAMT CIM 4 vAMT CIM 5 vAMT vAMT Common In- formation Model (CIM [3] AMT AMT vAMT 1 VM #12;1 3. 1 CIM CIM CIM CIM 2 CIM Managed Object Format MOF MOF BNF CIM CIM MOF 2 CIM Processor CIM Chip CIM Realizes 3 2 CIM Processor CIM CIM

Kourai, Kenichi

42

Materials Modeling and Simulation for Nuclear Fuels (MMSNF) Workshops  

NLE Websites -- All DOE Office Websites (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

43

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

44

Upgrade and Repair Your PC  

Science Conference Proceedings (OSTI)

From the Publisher:More PC for less $$$! Whether you have the latest,state-of-the-art computer equipment or a 286/386/486 workhorse,here's a book that will help you improve your machine and save a bundle. No,you don't need to be a computer genius. Its ...

Aubrey Pilgrim

1997-10-01T23:59:59.000Z

45

Upgrade and Repair Your PC  

Science Conference Proceedings (OSTI)

From the Publisher:More PC for less $$$! Whether you have the latest,state-of-the-art computer equipment or a 286/386/486 workhorse,here's a book that will help you improve your machine and save a bundle. No,you don't need to be a computer genius. Its ...

Aubrey Pilgrim

1997-11-01T23:59:59.000Z

46

Correlations Tests in Nuclear Mass Model Development  

E-Print Network (OSTI)

Correlation testing provides a quick method of discriminating amongst potential terms to include in a nuclear mass formula or functional; however a firm mathematical foundation of the method has not been previously set forth. Here, the necessary justification for correlation testing is developed and more detail of the motivation behind its use is given. We provide a quantitative demonstration of the method's performance and short-comings, highlighting also potential issues a user may encounter. In concluding we suggestion some possible future developments to improve the limitations of the method.

Bertolli, M G

2012-01-01T23:59:59.000Z

47

Nuclear Mass Datasets and Models at nuclearmasses.org  

DOE Data Explorer (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.

48

Relativistic models in nuclear and particle physics  

SciTech Connect

A comparative overview is presented of different approaches to the construction of phenomenological dynamical models that respect basic principles of quantum theory and relativity. Wave functions defined as matrix elements of products of field operators on one hand and wave functions that are defined as representatives of state vectors in model Hilbert spaces are related differently to observables and dynamical models for these wave functions have each distinct advantages and disadvantages 34 refs.

Coester, F.

1988-01-01T23:59:59.000Z

49

Nuclear Asset Management (NAM) Model - Update for Project Prioritization  

Science Conference Proceedings (OSTI)

This report provides an update of the Nuclear Asset Management (NAM) Process Model developed in 2007 and published in EPRI report 1015091. It incorporates results from modeling project prioritization guidance developed as part of EPRI's participation in the Equipment Reliability Working Group (ERWG). This update presents additional detail on the model described in report 1015091 and provides a reflection of current industry best practices for project prioritization.

2009-07-17T23:59:59.000Z

50

Mesoscale to plant-scale models of nuclear waste reprocessing.  

Science Conference Proceedings (OSTI)

Imported oil exacerabates our trade deficit and funds anti-American regimes. Nuclear Energy (NE) is a demonstrated technology with high efficiency. NE's two biggest political detriments are possible accidents and nuclear waste disposal. For NE policy, proliferation is the biggest obstacle. Nuclear waste can be reduced through reprocessing, where fuel rods are separated into various streams, some of which can be reused in reactors. Current process developed in the 1950s is dirty and expensive, U/Pu separation is the most critical. Fuel rods are sheared and dissolved in acid to extract fissile material in a centrifugal contactor. Plants have many contacts in series with other separations. We have taken a science and simulation-based approach to develop a modern reprocessing plant. Models of reprocessing plants are needed to support nuclear materials accountancy, nonproliferation, plant design, and plant scale-up.

Noble, David Frederick; O'Hern, Timothy John; Moffat, Harry K.; Nemer, Martin B.; Domino, Stefan Paul; Rao, Rekha Ranjana; Cipiti, Benjamin B.; Brotherton, Christopher M.; Jove-Colon, Carlos F.; Pawlowski, Roger Patrick

2010-09-01T23:59:59.000Z

51

Nuclear binding energies from a BPS Skyrme model  

E-Print Network (OSTI)

Recently, within the space of generalized Skyrme models, a BPS submodel was identified which reproduces some bulk properties of nuclear matter already on a classical level and, as such, constitutes a promising field theory candidate for the detailed and reliable description of nuclei and hadrons. Here we extend and further develop these investigations by applying the model to the calculation of nuclear binding energies. Concretely, we calculate these binding energies by including the classical soliton energies, the excitation energies from the collective coordinate quantization of spin and isospin, the electrostatic Coulomb energies and a small explicit isospin symmetry breaking, which accounts for the mass difference between proton and neutron. The integrability properties of the BPS Skyrme model allow, in fact, for an analytical calculation of all contributions, which may then be compared with the semi-empirical mass formula. We find that for heavier nuclei, where the model is expected to be more accurate o...

Adam, C; Sanchez-Guillen, J; Wereszczynski, A

2013-01-01T23:59:59.000Z

52

Thermohydraulic modeling of nuclear thermal rockets: The KLAXON code  

DOE Green Energy (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

53

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 of nuclear reactors: current practices in a nutshell Christophe Demazière Department of Applied Physics, Division of Nuclear Engineering, Chalmers University of Technology, SE-412 96 Gothenburg, Sweden Email

Demazière, Christophe

54

Relativistic mean-field models and nuclear matter constraints  

SciTech Connect

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

55

Integration of Facility Modeling Capabilities for Nuclear Nonproliferation Analysis  

Science Conference Proceedings (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.

Humberto E. Garcia

2012-01-01T23:59:59.000Z

56

INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS  

SciTech Connect

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

57

Integration of facility modeling capabilities for nuclear nonproliferation analysis  

SciTech Connect

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.

Garcia, Humberto [Idaho National Laboratory (INL); Burr, Tom [Los Alamos National Laboratory (LANL); Coles, Garill A [ORNL; Edmunds, Thomas A. [Lawrence Livermore National Laboratory (LLNL); Garrett, Alfred [Savannah River National Laboratory (SRNL); Gorensek, Maximilian [Savannah River National Laboratory (SRNL); Hamm, Luther [Savannah River National Laboratory (SRNL); Krebs, John [Argonne National Laboratory (ANL); Kress, Reid L [ORNL; Lamberti, Vincent [Y-12 National Security Complex; Schoenwald, David [ORNL; Tzanos, Constantine P [ORNL; Ward, Richard C [ORNL

2012-01-01T23:59:59.000Z

58

Modeling Deep Burn TRISO Particle Nuclear Fuel  

Science Conference Proceedings (OSTI)

Under the DOE Deep Burn program TRISO fuel is being investigated as a fuel form for consuming plutonium and minor actinides, and for greater efficiency in uranium utilization. The result will thus be to drive TRISO particulate fuel to very high burn-ups. In the current effort the various phenomena in the TRISO particle are being modeled using a variety of techniques. The chemical behavior is being treated utilizing thermochemical analysis to identify phase formation/transformation and chemical activities in the particle, including kernel migration. First principles calculations are being used to investigate the critical issue of fission product palladium attack on the SiC coating layer. Density functional theory is being used to understand fission product diffusion within the plutonia oxide kernel. Kinetic Monte Carlo techniques are shedding light on transport of fission products, most notably silver, through the carbon and SiC coating layers. The diffusion of fission products through an alternative coating layer, ZrC, is being assessed via DFT methods. Finally, a multiscale approach is being used to understand thermal transport, including the effect of radiation damage induced defects, in a model SiC material.

Besmann, Theodore M [ORNL; Stoller, Roger E [ORNL; Samolyuk, German D [ORNL; Schuck, Paul C [ORNL; Rudin, Sven [Los Alamos National Laboratory (LANL); Wills, John [Los Alamos National Laboratory (LANL); Wirth, Brian D. [University of California, Berkeley; Kim, Sungtae [University of Wisconsin, Madison; Morgan, Dane [University of Wisconsin, Madison; Szlufarska, Izabela [University of Wisconsin, Madison

2012-01-01T23:59:59.000Z

59

Phase structure in a chiral model of nuclear matter  

Science Conference Proceedings (OSTI)

The phase structure of symmetric nuclear matter in the extended Nambu-Jona-Lasinio (ENJL) model is studied by means of the effective potential in the one-loop approximation. It is found that chiral symmetry gets restored at high nuclear density and a typical first-order phase transition of the liquid-gas transition occurs at zero temperature, T=0, which weakens as T grows and eventually ends up with a second-order critical point at T=20 MeV. This phase transition scenario is confirmed by investigating the evolution of the effective potential versus the effective nucleon mass and the equation of state.

Phat, Tran Huu [Vietnam Atomic Energy Commission, 59 Ly Thuong Kiet, Hanoi (Viet Nam); Dong Do University, 8 Nguyen Cong Hoan, Hanoi (Viet Nam); Anh, Nguyen Tuan [Electric Power University, 235 Hoang Quoc Viet, Hanoi (Viet Nam); Tam, Dinh Thanh [University of Taybac, Sonla (Viet Nam); Vietnam Atomic Energy Commission, 59 Ly Thuong Kiet, Hanoi (Viet Nam)

2011-08-15T23:59:59.000Z

60

TAMCN: a tool for aggregate modeling of civil nuclear materials  

E-Print Network (OSTI)

There has been some concern in recent years about the buildup of separated civil plutonium in the world. In order to address issues related to these concerns, it is useful to have models that provide quantitative predictions of this buildup, under various scenarios. Our goal was to develop a publicly available model that would allow users to specify scenarios of their own, not simply the scenarios we envisioned. We believe this approach will provide a more complete understanding of the processes 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 present in these countries, we believe, represent the pressing issues in all nuclear countries and may fully address the current problems in the buildup of reactor grade plutonium in the world today. In addition, these countries have contributed a substantial quantity of material to the amount of civil separated plutonium present today, so we thought it wise to begin here. We have developed a model of the nuclear fuel cycle in Western Europe and Japan using STELLA®. Our model uses the simple "stock and flow" structure of STELLA® to describe the discharge, storage, and reprocessing of spent nuclear fuel from commercial power reactors, and the creation, storage, and utilization of reactor-grade civil separated plutonium in these regions. This provides an interface that is user-friendly and can be run on any computing platform that can operate the STELLA® software. In addition, detailed changes can be easily made to the model, if the user desires. We will describe features of the model from the perspective of a user, give the results of a few scenarios, and delineate plausibility tests of the model.

Watson, Aaron Michael

2002-01-01T23:59:59.000Z

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.


61

SI PC104 Performance Test Report  

SciTech Connect

The Spectral Instruments (SI) PC104 systems associated with the SI-1000 CCD camera exhibited intermittent power problems during setup, test and operations which called for further evaluation and testing. The SI PC104 System is the interface between the SI-1000 CCD camera and its associated Diagnostic Controller (DC). As such, the SI PC104 must be a reliable, robust system capable of providing consistent performance in various configurations and operating conditions. This SI PC104 system consists of a stackable set of modules designed to meet the PC104+ Industry Standard. The SI PC104 System consists of a CPU module, SI Camera card, Media converter card, Video card and a I/O module. The root cause of power problems was identified as failing solder joints at the LEMO power connector attached to the SI Camera Card. The recommended solution was to provide power to the PC104 system via a PC104+ power supply module configured into the PC104 stack instead of thru the LEMO power connector. Test plans (2) were developed to test SI PC104 performance and identify any outstanding issues noted during extended operations. Test Plan 1 included performance and image acquisition tests. Test Plan 2 verified performance after implementing recommendations. Test Plan 2 also included verifying integrity of system files and driver installation after bootup. Each test plan was implemented to fully test against each set of problems noted. Test Plan presentations and Test Plan results are attached as appendices. Anticipated test results will show successful operation and reliable performance of the SI PC104 system receiving its power via a PC104 power supply module. A SI PC104 Usage Recommendation Memo will be sent out to the SI PC104 User Community. Recommendation memo(s) are attached as appendices.

Montelongo, S

2005-12-16T23:59:59.000Z

62

Heat Transfer Modeling of Dry Spent Nuclear Fuel Storage Facilities  

Science Conference Proceedings (OSTI)

The present work was undertaken to provide heat transfer model that accurately predicts the thermal performance of dry spent nuclear fuel storage facilities. One of the storage configurations being considered for DOE Aluminum-clad Spent Nuclear Fuel (Al-SNF), such as the Material and Testing Reactor (MTR) fuel, is in a dry storage facility. To support design studies of storage options a computational and experimental program has been conducted at the Savannah River Site (SRS). The main objective is to develop heat transfer models including natural convection effects internal to an interim dry storage canister and to geological codisposal Waste Package (WP). Calculated temperatures will be used to demonstrate engineering viability of a dry storage option in enclosed interim storage and geological repository WP and to assess the chemical and physical behaviors of the Al-SNF in the dry storage facilities. The current paper describes the modeling approaches and presents the computational results along with the experimental data.

Lee, S.Y.

1999-01-13T23:59:59.000Z

63

Nuclear EMC effect in non-extensive statistical model  

SciTech Connect

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

64

Related Resources - Nuclear Data Program, Nuclear Engineering...  

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65

Publications: Other Resources - Nuclear Data Program - Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

66

Publications 2005 - Nuclear Data Program - Nuclear Engineering...  

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67

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68

Contacts - Nuclear Data Program, Nuclear Engineering Division...  

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69

Publications 2001 - Nuclear Data Program - Nuclear Engineering...  

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70

Publications 2004 - Nuclear Data Program - Nuclear Engineering...  

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71

Publications 2009 - Nuclear Data Program - Nuclear Engineering...  

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72

Nuclear Criticality Safety: Current Activities - Nuclear Engineering...  

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73

Nuclear Criticality Safety - Nuclear Engineering Division (Argonne...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

74

Nuclear Systems Analysis - Nuclear Engineering Division (Argonne...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

75

Publications 2011 - Nuclear Data Program - Nuclear Engineering...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

76

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

77

Role and use of nuclear theories and models in practical evaluation of neutron nuclear data needed for fission and fusion reactor design and other nuclear applications  

SciTech Connect

A review of the various nuclear models used in the evaluation of neutron nuclear data for fission and fusion reactors is presented. Computer codes embodying the principles of the relevant nuclear models are compared with each other and with experimental data. The regions of validity and limitations of the conceptual formalisms are also included, along with the effects of the numerical procedures used in the codes themselves. Conclusions and recommendations for future demands are outlined.15 tables, 15 figures, 90 references. (auth)

Prince, A.

1975-01-01T23:59:59.000Z

78

PC-1D installation manual and user's guide  

DOE Green Energy (OSTI)

PC-1D is a software package for personal computers that uses finite-element analysis to solve the fully-coupled two-carrier semiconductor transport equations in one dimension. This program is particularly useful for analyzing the performance of optoelectronic devices such as solar cells, but can be applied to any bipolar device whose carrier flows are primarily one-dimensional. This User's Guide provides the information necessary to install PC-1D, define a problem for solution, solve the problem, and examine the results. Example problems are presented which illustrate these steps. The physical models and numerical methods utilized are presented in detail. This document supports version 3.1 of PC-1D, which incorporates faster numerical algorithms with better convergence properties than previous versions of the program. 51 refs., 17 figs., 5 tabs.

Basore, P.A.

1991-05-01T23:59:59.000Z

79

Laboratory Equipment - Vacuubrand PC101 Vacuum Pump  

Science Conference Proceedings (OSTI)

Vacuubrand PC101 Vacuum Pump. ... pumping speed: 1.7/2.0 m 3 -h -1; Ultimate ... outlet: 2 bar; Permitted ambient temperature storage/operation: -10°C ...

2012-07-11T23:59:59.000Z

80

3-Dimensional, High-Resolution Modeling of Nuclear Fuel ...  

Science Conference Proceedings (OSTI)

Evaluation of Silicon Carbide Joining for Nuclear and Fusion Applications ... Light Water Reactor Materials for Commercial Nuclear Power Applications.

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

Nuclear Hybrid Energy System Modeling: RELAP5 Dynamic Coupling Capabilities  

SciTech Connect

The nuclear hybrid energy systems (NHES) research team is currently developing a dynamic simulation of an integrated hybrid energy system. A detailed simulation of proposed NHES architectures will allow initial computational demonstration of a tightly coupled NHES to identify key reactor subsystem requirements, identify candidate reactor technologies for a hybrid system, and identify key challenges to operation of the coupled system. This work will provide a baseline for later coupling of design-specific reactor models through industry collaboration. The modeling capability addressed in this report focuses on the reactor subsystem simulation.

Piyush Sabharwall; Nolan Anderson; Haihua Zhao; Shannon Bragg-Sitton; George Mesina

2012-09-01T23:59:59.000Z

82

Nuclear interactions of 160 MeV protons stopping in copper: A test of Monte Carlo nuclear models  

Science Conference Proceedings (OSTI)

To estimate the influence of nuclear interactions on dose or biological effect one uses Monte Carlo programs which include nuclear models. We introduce an experimental method to check these models at proton therapy energies. We have measured the distribution of charge deposited by 160 MeV protons stopping in a stack of insulated copper plates. A buildup region ahead of the main peak contains ?20% of the total charge and is entirely due to charged secondaries from inelastic nuclear interactions. The acceptance for charged secondaries is 100%. Therefore the data are a good benchmark for nuclear models. We have simulated the stack using GEANT with two nuclear models.FLUKA agrees fairly well with the measurement but GHEISHA

Bernard Gottschalk; Rachel Platais; Harald Paganetti

1999-01-01T23:59:59.000Z

83

Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling  

Science Conference Proceedings (OSTI)

This project addresses three important gaps in existing evaluated nuclear data libraries that represent a significant hindrance against highly advanced modeling and simulation capabilities for the Advanced Fuel Cycle Initiative (AFCI). This project will: Develop advanced theoretical tools to compute prompt fission neutrons and gamma-ray characteristics well beyond average spectra and multiplicity, and produce new evaluated files of U and Pu isotopes, along with some minor actinides; Perform state-of-the-art fission cross-section modeling and calculations using global and microscopic model input parameters, leading to truly predictive fission cross-sections capabilities. Consistent calculations for a suite of Pu isotopes will be performed; Implement innovative data assimilation tools, which will reflect the nuclear data evaluation process much more accurately, and lead to a new generation of uncertainty quantification files. New covariance matrices will be obtained for Pu isotopes and compared to existing ones. The deployment of a fleet of safe and efficient advanced reactors that minimize radiotoxic waste and are proliferation-resistant is a clear and ambitious goal of AFCI. While in the past the design, construction and operation of a reactor were supported through empirical trials, this new phase in nuclear energy production is expected to rely heavily on advanced modeling and simulation capabilities. To be truly successful, a program for advanced simulations of innovative reactors will have to develop advanced multi-physics capabilities, to be run on massively parallel super- computers, and to incorporate adequate and precise underlying physics. And all these areas have to be developed simultaneously to achieve those ambitious goals. Of particular interest are reliable fission cross-section uncertainty estimates (including important correlations) and evaluations of prompt fission neutrons and gamma-ray spectra and uncertainties.

Danon, Yaron; Nazarewicz, Witold; Talou, Patrick

2013-02-18T23:59:59.000Z

84

Nuclear mass systematics by complementing the Finite Range Droplet Model with neural networks  

E-Print Network (OSTI)

A neural-network model is developed to reproduce the differences between experimental nuclear mass-excess values and the theoretical values given by the Finite Range Droplet Model. The results point to the existence of subtle regularities of nuclear structure not yet contained in the best microscopic/phenomenological models of atomic masses. Combining the FRDM and the neural-network model, we create a hybrid model with improved predictive performance on nuclear-mass systematics and related quantities.

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

2005-11-30T23:59:59.000Z

85

EMPIRE: Nuclear Reaction Model Code System for Data Evaluation  

SciTech Connect

EMPIRE is a modular system of nuclear reaction codes, comprising various nuclear models, and designed for calculations over a broad range of energies and incident particles. A projectile can be a neutron, proton, any ion (including heavy-ions) or a photon. The energy range extends from the beginning of the unresolved resonance region for neutron-induced reactions ({approx} keV) and goes up to several hundred MeV for heavy-ion induced reactions. The code accounts for the major nuclear reaction mechanisms, including direct, pre-equilibrium and compound nucleus ones. Direct reactions are described by a generalized optical model (ECIS03) or by the simplified coupled-channels approach (CCFUS). The pre-equilibrium mechanism can be treated by a deformation dependent multi-step direct (ORION + TRISTAN) model, by a NVWY multi-step compound one or by either a pre-equilibrium exciton model with cluster emission (PCROSS) or by another with full angular momentum coupling (DEGAS). Finally, the compound nucleus decay is described by the full featured Hauser-Feshbach model with {gamma}-cascade and width-fluctuations. Advanced treatment of the fission channel takes into account transmission through a multiple-humped fission barrier with absorption in the wells. The fission probability is derived in the WKB approximation within the optical model of fission. Several options for nuclear level densities include the EMPIRE-specific approach, which accounts for the effects of the dynamic deformation of a fast rotating nucleus, the classical Gilbert-Cameron approach and pre-calculated tables obtained with a microscopic model based on HFB single-particle level schemes with collective enhancement. A comprehensive library of input parameters covers nuclear masses, optical model parameters, ground state deformations, discrete levels and decay schemes, level densities, fission barriers, moments of inertia and {gamma}-ray strength functions. The results can be converted into ENDF-6 formatted files using the accompanying code EMPEND and completed with neutron resonances extracted from the existing evaluations. The package contains the full EXFOR (CSISRS) library of experimental reaction data that are automatically retrieved during the calculations. Publication quality graphs can be obtained using the powerful and flexible plotting package ZVView. The graphic user interface, written in Tcl/Tk, provides for easy operation of the system. This paper describes the capabilities of the code, outlines physical models and indicates parameter libraries used by EMPIRE to predict reaction cross sections and spectra, mainly for nucleon-induced reactions. Selected applications of EMPIRE are discussed, the most important being an extensive use of the code in evaluations of neutron reactions for the new US library ENDF/B-VII.0. Future extensions of the system are outlined, including neutron resonance module as well as capabilities of generating covariances, using both KALMAN and Monte-Carlo methods, that are still being advanced and refined.

Herman, M. [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)], E-mail: mwherman@bnl.gov; Capote, R. [Nuclear Data Section, International Atomic Energy Agency, Wagramer Strasse, A-1400 Vienna (Austria); Carlson, B.V. [Departamento de Fisica, Instituto Tecnologico de Aeronautica, 12228-900, SP, Sao Jose dos Campos (Brazil); Oblozinsky, P. [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States); Sin, M. [Nuclear Physics Department, Bucharest University, P.O. Box MG-11, Bucharest-Magurele (Romania); Trkov, A. [Jozef Stefan Institute, Reactor Physics Division R-1, Jamova 39, 1000 Ljubljana (Slovenia); Wienke, H. [Belgonucleaire, Dessel, B2480 (Belgium); Zerkin, V. [Nuclear Data Section, International Atomic Energy Agency, Wagramer Strasse, A-1400 Vienna (Austria)

2007-12-15T23:59:59.000Z

86

Fusion Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research...

87

Risk analysis of nuclear safeguards regulations. [Aggregated Systems Model (ASM)  

Science Conference Proceedings (OSTI)

The Aggregated Systems Model (ASM), a probabilisitic risk analysis tool for nuclear safeguards, was applied to determine benefits and costs of proposed amendments to NRC regulations governing nuclear material control and accounting systems. The objective of the amendments was to improve the ability to detect insiders attempting to steal large quantities of special nuclear material (SNM). Insider threats range from likely events with minor consequences to unlikely events with catastrophic consequences. Moreover, establishing safeguards regulations is complicated by uncertainties in threats, safeguards performance, and consequences, and by the subjective judgments and difficult trade-offs between risks and safeguards costs. The ASM systematically incorporates these factors in a comprehensive, analytical framework. The ASM was used to evaluate the effectiveness of current safeguards and to quantify the risk of SNM theft. Various modifications designed to meet the objectives of the proposed amendments to reduce that risk were analyzed. Safeguards effectiveness was judged in terms of the probability of detecting and preventing theft, the expected time to detection, and the expected quantity of SNM diverted in a year. Data were gathered in tours and interviews at NRC-licensed facilities. The assessment at each facility was begun by carefully selecting scenarios representing the range of potential insider threats. A team of analysts and facility managers assigned probabilities for detection and prevention events in each scenario. Using the ASM we computed the measures of system effectiveness and identified cost-effective safeguards modifications that met the objectives of the proposed amendments.

Al-Ayat, R.A.; Altman, W.D.; Judd, B.R.

1982-06-01T23:59:59.000Z

88

Modeling Nuclear Pasta and the Transition to Uniform Nuclear Matter with the 3D-Skyrme-Hartree-Fock Method  

E-Print Network (OSTI)

The first results of a new three-dimensional, finite temperature Skyrme-Hartree-Fock+BCS study of the properties of inhomogeneous nuclear matter at densities and temperatures leading to the transition to uniform nuclear matter are presented. A constraint is placed on the two independent components of the quadrupole moment in order to self-consistently explore the shape phase space of nuclear configurations. The scheme employed naturally allows effects such as (i) neutron drip, which results in an external neutron gas, (ii) the variety of exotic nuclear shapes expected for extremely neutron heavy nuclei, and (iii) the subsequent dissolution of these nuclei into nuclear matter. In this way, the equation of state can be calculated across phase transitions from lower densities (where one dimensional Hartree-Fock suffices) through to uniform nuclear matter without recourse to interpolation techniques between density regimes described by different physical models.

W. G. Newton

2009-03-08T23:59:59.000Z

89

Modeling Nuclear Pasta and the Transition to Uniform Nuclear Matter with the 3D-Skyrme-Hartree-Fock Method  

E-Print Network (OSTI)

The first results of a new three-dimensional, finite temperature Skyrme-Hartree-Fock+BCS study of the properties of inhomogeneous nuclear matter at densities and temperatures leading to the transition to uniform nuclear matter are presented. A constraint is placed on the two independent components of the quadrupole moment in order to self-consistently explore the shape phase space of nuclear configurations. The scheme employed naturally allows effects such as (i) neutron drip, which results in an external neutron gas, (ii) the variety of exotic nuclear shapes expected for extremely neutron heavy nuclei, and (iii) the subsequent dissolution of these nuclei into nuclear matter. In this way, the equation of state can be calculated across phase transitions from lower densities (where one dimensional Hartree-Fock suffices) through to uniform nuclear matter without recourse to interpolation techniques between density regimes described by different physical models.

Newton, W G

2009-01-01T23:59:59.000Z

90

Modeled Salt Density for Nuclear Material Estimation in the Treatment of Spent Nuclear Fuel  

SciTech Connect

Spent metallic nuclear fuel is being treated in a pyrometallurgical process that includes electrorefining the uranium metal in molten eutectic LiCl-KCl as the supporting electrolyte. We report a model for determining the density of the molten salt. Inventory operations account for the net mass of salt and for the mass of actinides present. It was necessary to know the molten salt density but difficult to measure, and it was decided to model the salt density for the initial treatment operations. The model assumes that volumes are additive for the ideal molten salt solution as a starting point; subsequently a correction factor for the lanthanides and actinides was developed. After applying the correction factor, the percent difference between the net salt mass in the electrorefiner and the resulting modeled salt mass decreased from more than 4.0% to approximately 0.1%. As a result, there is no need to measure the salt density at 500 C for inventory operations; the model for the salt density is found to be accurate.

DeeEarl Vaden; Robert. D. Mariani

2010-09-01T23:59:59.000Z

91

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

92

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

93

MODELING ATMOSPHERIC RELEASES OF TRITIUM FROM NUCLEAR INSTALLATIONS  

DOE Green Energy (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

94

DOE/PC/88921--5  

NLE Websites -- All DOE Office Websites (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

95

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":""}]}

96

PC Electronic Data Reporting Option (PEDRO) System  

U.S. Energy Information Administration (EIA)

Windows-based personal computer (PC) Windows NT, 2000, XP, or Vista; Approximately 30 Mb of free disk space for the PEDRO system files, plus up to 10 Mb for each survey;

97

Integration of facility modeling capabilities for nuclear nonproliferation analysis  

Science Conference Proceedings (OSTI)

Developing automated methods for data collection and analysis that can facilitate nuclearnonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facilitymodeling 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 facilitymodeling 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 facilitymodelingcapabilities and illustrates how they could be integrated and utilized for nonproliferationanalysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facilitymodeling tools. After considering a representative sampling of key facilitymodelingcapabilities, the proposed integration framework is illustrated with several examples.

Burr, Tom [Los Alamos National Laboratory (LANL); Gorensek, M. B. [Savannah River National Laboratory (SRNL); Krebs, John [Argonne National Laboratory (ANL); Kress, Reid L [ORNL; Lamberti, Vincent [Y-12 National Security Complex; Schoenwald, David [ORNL; Ward, Richard C [ORNL

2012-01-01T23:59:59.000Z

98

Modeling and analysis of a heat transport transient test facility for space nuclear systems.  

E-Print Network (OSTI)

??The purpose of this thesis is to design a robust test facility for a small space nuclear power system and model its physical behavior under… (more)

[No author

2013-01-01T23:59:59.000Z

99

Summary of "Materials Modeling and Simulations for Nuclear Fuels"  

NLE Websites -- All DOE Office Websites (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

100

Multiscale Modeling of Defect Mechanics in Nuclear Materials  

Science Conference Proceedings (OSTI)

Abstract Scope, The key to developing advanced materials for nuclear applications is ... Physics-Based Homogenization of Random Continuum Microstructures.

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

Physics and Engineering Models | National Nuclear Security Administrat...  

National Nuclear Security Administration (NNSA)

Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering...

102

Fire Events Database and Generic Ignition Frequency Model for U.S. Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report contains a revision of the EPRI Fire Events Database for U.S. Nuclear Power Plants last published in EPRI Report 1000894 in October 2000. This report also contains a revision of the generic fire ignition frequency models that were published in NSAC-178L, "Fire Events Database of U.S. Nuclear Power Plants" (January 1993) and EPRI TR-105929, "Fire Ignition Frequency Model at Shutdown for U.S. Nuclear Power Plants" (December 1995).

2001-11-09T23:59:59.000Z

103

Mathematical model of steam generator feed system at power unit of nuclear plant  

Science Conference Proceedings (OSTI)

A mathematical model of a steam generator feed system at a power unit of a nuclear plant with variable values of transfer function coefficients is presented. The model is realized in the MATLAB/Simulink/Stateflow event-driven simulation.

E. M. Raskin; L. A. Denisova; V. P. Sinitsyn; Yu. V. Nesterov

2011-05-01T23:59:59.000Z

104

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

105

An improved structural mechanics model for the FRAPCON nuclear fuel performance code  

E-Print Network (OSTI)

In order to provide improved predictions of Pellet Cladding Mechanical Interaction (PCMI) for the FRAPCON nuclear fuel performance code, a new model, the FRAPCON Radial-Axial Soft Pellet (FRASP) model, was developed. This ...

Mieloszyk, Alexander James

2012-01-01T23:59:59.000Z

106

Stochastic simulation of pulverized coal (PC) processes  

SciTech Connect

An increasing population and electricity demand in the U.S. require capacity expansion of power systems. The National Energy Technology Laboratory (NETL), U.S. Department of Energy (DOE), has invested considerable efforts on research and development to improve the design and simulation of these power plants. Incorporation of novel process synthesis techniques and realistic simulation methodologies yield optimal flowsheet configurations and accurate estimation of their performance parameters. To provide a better estimation of such performance indicators, simulation models should predict the process behavior based on not only deterministic values of well-known input parameters but also uncertain variables associated with simulation assumptions. In this work, the stochastic simulation of a load-following pulverized coal (PC) power plant takes into account the variation of three input variables, namely, atmospheric air temperature, atmospheric air humidity, and generation load. These uncertain variables are characterized with probability density functions (pdfs) obtained from available atmospheric and electrical energy generation data. The stochastic simulation is carried out by obtaining a sample of values from the pdfs that generates a set of scenarios under which the model is run. An efficient sampling technique [Hammersley sequence sampling (HSS)] guarantees a set of scenarios uniformly distributed throughout the uncertain variable range. Then, each model run generates results on performance parameters as cycle efficiency, carbon emissions, sulfur emissions, and water consumption that are statistically analyzed after all runs are completed. Among these parameters, water consumption is of importance because an increasing demand has been observed mostly in arid regions of the country and, therefore, constrains the operability of the processes. This water consumption is significantly affected by atmospheric uncertainties. The original deterministic process model simulation was designed in Aspen Plus, and a CAPE-OPEN compliant stochastic simulation capability is employed to run the uncertainty analysis. Initially, the influences of atmospheric conditions and load change on the performance parameters are analyzed separately to understand their individual influences on the process, and then their simultaneous variation is analyzed to generate more realistic estimations of the process performance.

Salazar, J.; Diwekar, U.; Zitney, S.

2010-01-01T23:59:59.000Z

107

International Cooperation on Safety of Nuclear Plants - Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

108

Current R&D Activities in Nuclear Criticality Safety - Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

109

NUCLEAR DATA AND MEASUREMENTS REPORTS 161-180 - Nuclear Data...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

110

Analysis Tools for Nuclear Criticality Safety - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

111

Modeling, analysis and experiments for fusion nuclear technology: FNT progress report: Modeling and FINESSE  

Science Conference Proceedings (OSTI)

This document is a progress report on two technical studies carried out during 1986, both of which relate to the implementation phase of FNT. The first, which is a follow-up to FINESSE, focuses on specific key questions for: (1) very near-term (0 to 3 years) non-fusion experiments and facilities, and (2) FNT testing in a fusion facility. The second is the initial stage of a detailed effort to develop theory, models and computer codes for predicting the performance of nuclear components. Chapters are presented on (1) introduction and chapter summaries, (2) non-fusion experiments and facilities, (3) fusion testing issues, and (4) theory and modeling. Chapter 2 is an assessment of the relative advantages of many solid breeders, neutron multipliers and configurations. Various issues affecting design and cost of the blanket are examined in Chapter 3. Chapter 4 reports on the progress of the initial stage of an effort to develop theory and analytical and numerical models for nuclear components. A major part of the effort has focused on modeling of MHD effects for liquid metal blankets. Progress has also been made on modeling tritium transport and inventory in solid breeder blankets and the thermomechanical behavior of liquid-metal-cooled limiters. (MOW)

Abdou, M.A.; Tillack, M.S.; Raffray, A.R.; Hadid, A.H.; Bartlit, J.R.; Bell, C.E.C.; Gierszewski, P.J.; Gordon, J.D.; Iizuka, T.; Kim, C.N.

1987-01-01T23:59:59.000Z

112

Organization - Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

113

Achievements: Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

114

Helium Behavior in Oxide Nuclear Fuels: First Principles Modeling  

Science Conference Proceedings (OSTI)

UO2 and (U, Pu)O2 solid solutions (the so-called MOX) nowadays are used as commercial nuclear fuels in many countries. One of the safety issues during the storage of these fuels is related to their self-irradiation that produces and accumulates point defects and helium therein. We present density functional theory (DFT) calculations for UO2, PuO2 and MOX containing He atoms in octahedral interstitial positions. In particular, we calculated basic MOX properties and He incorporation energies as functions of Pu concentration within the spin-polarized, generalized gradient approximation (GGA) DFT calculations. We also included the on-site electron correlation corrections using the Hubbard model (in the framework of the so-called DFT + U approach). We found that PuO2 remains semiconducting with He in the octahedral position while UO2 requires a specific lattice distortion. Both materials reveal a positive energy for He incorporation, which, therefore, is an exothermic process. The He incorporation energy increases with the Pu concentration in the MOX fuel.

Gryaznov, D.; Rashkeev, Sergey N.; Kotomin, E. A.; Heifets, Eugene; Zhukovskii, Yuri F.

2010-10-01T23:59:59.000Z

115

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

Science Conference Proceedings (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

116

Remote PC Security: Securing the home worker  

Science Conference Proceedings (OSTI)

A recent study of 1000 teleworkers in 10 countries, commissioned by Cisco, showed that one in five allows friends, family and others to use their work PC to access the Internet. Now is the time to pull stray remote workers back into the security fold. ...

Steven Furnell

2006-11-01T23:59:59.000Z

117

On nuclear scars, renewables, and an acid rain model  

SciTech Connect

The author argues that the extreme precautions observed at a nuclear power plant and throughout the nuclear industry create an interesting conflict in imagery. First, the safety measures far exceed the normal acceptable lengths taken to protect workers and the public at large in any other circumstance. Second, those very extremes in precaution contribute to public fear. Naturally, anti-nuclear radicals use this to great advantage by constantly trying to force more extreme measures on the industry. According to the author it happens even though some of these groups seem to realize that fighting the most environmentally benign source of power makes no sense.

Rittenhouse, R.C

1989-11-01T23:59:59.000Z

118

Caloric curve for nuclear liquid-gas phase transition in relativistic mean-field hadronic model  

E-Print Network (OSTI)

The main thermodynamical properties of the nuclear liquid-gas phase transition were explored in the framework of the relativistic mean-field hadronic model in three statistical ensembles: canonical, grand canonical and isobaric. We have found that the liquid-gas phase transition, i.e., the first order phase transition which is defined by the plateau in the isotherms, cannot contain the plateau in the caloric curves in the canonical and microcanonical ensembles. The plateau in the isotherms is incompatible with the plateau in the caloric curves at fixed baryon density. Moreover, for the nuclear liquid-gas phase transition the caloric curve has a plateau only at fixed pressure or chemical potential. The results of the statistical multifragmentation models for the nuclear liquid-gas phase transition were reanalyzed. It was revealed that one class of statistical multifragmentation models do indeed predict the nuclear liquid-gas phase transition for the nuclear multifragmentation. However, there is another class o...

Parvan, A S

2011-01-01T23:59:59.000Z

119

Isospin Lattice-Gas Model and Liquid-Gas Phase Transition in Asymmetric Nuclear Matter  

E-Print Network (OSTI)

An isospin lattice-gas model, which is a spin-1 Ising model, is employed to investigate the liquid-gas phase transition in asymmetric nuclear matter. We consider nuclear matter as a lattice where each lattice site can be either empty or occupied by a proton or a neutron, with a nearest-neighbor interaction among the nucleons. With the Bragg-Williams mean field approximation, we calculate various thermodynamic properties of nuclear matter for different densities and different proton-neutron asymmetry parameter s. Our model exhibits liquidgas phase transition below a critical temperature Tc, and predicts a monotonic decreasing of Tc as the magnitude of s is increased. The dependence of the nuclear matter isotherms on the asymmetry parameter s is discussed. Ray, Shamanna and Kuo / Liquid-gas phase transition in Nuclear matter 2 1.

S. Ray; J. Shamanna; T. T. S. Kuo

2008-01-01T23:59:59.000Z

120

Characterization and Modeling of Disolcation Structures in Nuclear ...  

Science Conference Proceedings (OSTI)

Mar 13, 2012... Greg Oberson, United States Nuclear Regulatory Commission; Matthew ... Session Chair: Elaine West, Knolls Atomic Power Laboratory; Osman ... Sung Soo Kim1; Dae Whan Kim1; 1Korea Atomic Energy Research Institute

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

Spatial multi-taper spectrum estimation for nuclear reactor modelling  

Science Conference Proceedings (OSTI)

Multi-taper univariate and cross-spectral analysis is used to investigate the structure of spatial variation in the temperatures measured across the surface of a nuclear reactor. The construction of the spatial tapers over the approximate circular reactor ...

C. J. Scarrott; G. Tunnicliffe Wilson

2009-10-01T23:59:59.000Z

122

Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG)  

Science Conference Proceedings (OSTI)

There is a movement to introduce risk-informed and performance-based (RI/PB) analyses into fire protection engineering practice, both domestically and worldwide.  This movement exists in both the general fire protection and the nuclear power plant (NPP) fire protection communities.  The U.S. Nuclear Regulatory Commission (NRC) has used risk-informed insights as a part of its regulatory decision making since the 1990s.In 2001, the National Fire Protection Association (NFPA) ...

2012-11-30T23:59:59.000Z

123

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

124

Robust nuclear signal reconstruction by a novel ensemble model aggregation procedure P. Baraldi1  

E-Print Network (OSTI)

of a nuclear boiling water reactor and 215 signals measured at a pressurized water reactor. The advantagesRobust nuclear signal reconstruction by a novel ensemble model aggregation procedure P. Baraldi1 Reactor Project, 1751, Halden, Norway Abstract Monitoring of sensor operation is important for detecting

125

Modelling of the Uncertainty of Nuclear Fuel Thermal Behaviour Using the URANIE Framework  

Science Conference Proceedings (OSTI)

In the global framework of nuclear fuel behaviour simulation, the response of the models describing the physical phenomena occurring during the irradiation in reactor is mainly conditioned by the confidence in the calculated temperature of the fuel. ... Keywords: uncertainty, thermal behaviour, nuclear fuel, URANIE

Antoine Boulore; Christine Struzik; Fabrice Gaudier

2009-09-01T23:59:59.000Z

126

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

SciTech Connect

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

A Model of Nuclear Recoil Scintillation Efficiency in Noble Liquids  

E-Print Network (OSTI)

Scintillation efficiency of low-energy nuclear recoils in noble liquids plays a crucial role in interpreting results from some direct searches for Weakly Interacting Massive Particle (WIMP) dark matter. However, the cause of a reduced scintillation efficiency relative to electronic recoils in noble liquids remains unclear at the moment. We attribute such a reduction of scintillation efficiency to two major mechanisms: 1) energy loss and 2) scintillation quenching. The former is commonly described by Lindhard's theory and the latter by Birk's saturation law. We propose to combine these two to explain the observed reduction of scintillation yield for nuclear recoils in noble liquids. Birk's constants $kB$ for argon, neon and xenon determined from existing data are used to predict noble liquid scintillator's response to low-energy nuclear recoils and low-energy electrons. We find that energy loss due to nuclear stopping power that contributes little to ionization and excitation is the dominant reduction mechanism in scintillation efficiency for nuclear recoils, but that significant additional quenching results from the nonlinear response of scintillation to the ionization density.

D. -M. Mei; Z. -B. Yin; L. C. Stonehill; A. Hime

2007-12-14T23:59:59.000Z

128

Modeling of Sulfate Double-salts in Nuclear Wastes  

Science Conference Proceedings (OSTI)

Due to limited tank space at Hanford and Savannah River, the liquid nuclear wastes or supernatants have been concentrated in evaporators to remove excess water prior to the hot solutions being transferred to underground storage tanks. As the waste solutions cooled, the salts in the waste exceeded the associated solubility limits and precipitated in the form of saltcakes. The initial step in the remediation of these saltcakes is a rehydration process called saltcake dissolution. At Hanford, dissolution experiments have been conducted on small saltcake samples from five tanks. Modeling of these experimental results, using the Environmental Simulation Program (ESP), are being performed at the Diagnostic Instrumentation and Analysis Laboratory (DIAL) at Mississippi State University. The River Protection Project (RPP) at Hanford will use these experimental and theoretical results to determine the amount of water that will be needed for its dissolution and retrieval operations. A comprehensive effort by the RPP and the Tank Focus Area continues to validate and improve the ESP and its databases for this application. The initial effort focused on the sodium, fluoride, and phosphate system due to its role in the formation of pipeline plugs. In FY 1999, an evaluation of the ESP predictions for sodium fluoride, trisodium phosphate dodecahydrate, and natrophosphate clearly indicated that improvements to the Public database of the ESP were needed. One of the improvements identified was double salts. The inability of any equilibrium thermodynamic model to properly account for double salts in the system can result in errors in the predicted solid-liquid equilibria (SLE) of species in the system. The ESP code is evaluated by comparison with experimental data where possible. However, data does not cover the range of component concentrations and temperatures found in many tank wastes. Therefore, comparison of ESP with another code is desirable, and may illuminate problems with both. For this purpose, the SOLGASMIX code was used in conjunction with a small private database developed at ORNL. This code calculates thermodynamic equilibria through minimization of Gibbs Energy, and utilizes the Pitzer model for activity coefficients. The sodium nitrate-sulfate double salt and the sodium fluoride-sulfate double salt were selected for the FY 2000 validation study of ESP. Even though ESP does not include the sulfate-nitrate double salt, this study found that this omission does not appear to be a major consequence. In this case, the solubility predictions with and without the sulfate-nitrate double salt are comparable. In contrast, even though the sulfate-fluoride double salt is included within the ESP databank, comparison to previous experimental results indicates that ESP underestimates solubility. Thus, the prediction for the sulfate-fluoride system needs to be improved. A main consequence of the inability to accurately predict the SLE of double salts is its impact on the predicted ionic strength of the solution. The ionic strength has been observed to be an important factor in the formation of pipeline plugs. To improve the ESP prediction, solubility tests on the sulfate-fluoride system are underway at DIAL, and these experimental results will be incorporated into the Public database by OLI System, Inc. Preliminary ESP simulations also indicated difficulties with the SLE prediction for anhydrous sodium sulfate. The Public database for the ESP does not include fundamental parameters for this solid in mixed solutions below 32.4 C. The limitation, in the range of anhydrous sodium sulfate, leads to convergence problems in ESP and to inaccurate predictions of solubility near the invariant point when sodium sulfate decahydrate and other salts, such as sodium nitrate, were present. These difficulties were partially corrected through the use of an additional database. In conclusion, these results indicate the need for experimental data at temperatures above 25 C and in solutions containing both nitrate and hydroxide. Furthermore, the validation and do

Toghiani, B.

2000-10-30T23:59:59.000Z

129

Role of criticality models in ANSI standards for nuclear criticality safety  

SciTech Connect

Two methods used in nuclear criticality safety evaluations in the area of neutron interaction among subcritical components of fissile materials are the solid angle and surface density techniques. The accuracy and use of these models are briefly discussed. (TFD)

Thomas, J.T.

1976-01-01T23:59:59.000Z

130

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 ...

131

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications  

Science Conference Proceedings (OSTI)

This report documents the verification and validation (VV) of five selected fire models commonly used in support of risk-informed and performance-based (RI/PB) fire protection at nuclear power plants (NPPs).

2007-05-30T23:59:59.000Z

132

Virtual enterprise model for the electronic components business in the Nuclear Weapons Complex  

Science Conference Proceedings (OSTI)

The electronic components business within the Nuclear Weapons Complex spans organizational and Department of Energy contractor boundaries. An assessment of the current processes indicates a need for fundamentally changing the way electronic components are developed, procured, and manufactured. A model is provided based on a virtual enterprise that recognizes distinctive competencies within the Nuclear Weapons Complex and at the vendors. The model incorporates changes that reduce component delivery cycle time and improve cost effectiveness while delivering components of the appropriate quality.

Ferguson, T.J.; Long, K.S.; Sayre, J.A. [Sandia National Labs., Albuquerque, NM (United States); Hull, A.L. [Sandia National Labs., Livermore, CA (United States); Carey, D.A.; Sim, J.R.; Smith, M.G. [Allied-Signal Aerospace Co., Kansas City, MO (United States). Kansas City Div.

1994-08-01T23:59:59.000Z

133

A Model-Based Signal Processing Approach to Nuclear Explosion Monitoring  

Science Conference Proceedings (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

134

Development of hydrogeological modelling approaches for assessment of consequences of hazardous accidents at nuclear power plants  

SciTech Connect

This paper introduces some modeling approaches for predicting the influence of hazardous accidents at nuclear reactors on groundwater quality. Possible pathways for radioactive releases from nuclear power plants were considered to conceptualize boundary conditions for solving the subsurface radionuclides transport problems. Some approaches to incorporate physical-and-chemical interactions into transport simulators have been developed. The hydrogeological forecasts were based on numerical and semi-analytical scale-dependent models. They have been applied to assess the possible impact of the nuclear power plants designed in Russia on groundwater reservoirs.

Rumynin, V.G.; Mironenko, V.A.; Konosavsky, P.K.; Pereverzeva, S.A. [St. Petersburg Mining Inst. (Russian Federation)

1994-07-01T23:59:59.000Z

135

The Lifecycle of Bayesian Network Models Developed for Multi-Source Signature Assessment of Nuclear Programs  

Science Conference Proceedings (OSTI)

The Multi-Source Signatures for Nuclear Programs project, part of Pacific Northwest National Laboratory’s (PNNL) Signature Discovery Initiative, seeks to computationally capture expert assessment of multi-type information such as text, sensor output, imagery, or audio/video files, to assess nuclear activities through a series of Bayesian network (BN) models. These models incorporate knowledge from a diverse range of information sources in order to help assess a country’s nuclear activities. The models span engineering topic areas, state-level indicators, and facility-specific characteristics. To illustrate the development, calibration, and use of BN models for multi-source assessment, we present a model that predicts a country’s likelihood to participate in the international nuclear nonproliferation regime. We validate this model by examining the extent to which the model assists non-experts arrive at conclusions similar to those provided by nuclear proliferation experts. We also describe the PNNL-developed software used throughout the lifecycle of the Bayesian network model development.

Gastelum, Zoe N.; White, Amanda M.; Whitney, Paul D.; Gosink, Luke J.; Sego, Landon H.

2013-06-04T23:59:59.000Z

136

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

Science Conference Proceedings (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

137

Isospin Lattice-Gas Model and Liquid-Gas Phase Transition in Asymmetric Nuclear Matter  

E-Print Network (OSTI)

An isospin lattice-gas model, which is a spin-1 Ising model, is employed to investigate the liquid-gas phase transition in asymmetric nuclear matter. We consider nuclear matter as a lattice where each lattice site can be either empty or occupied by a proton or a neutron, with a nearest-neighbor interaction among the nucleons. With the Bragg-Williams mean field approximation, we calculate various thermodynamic properties of nuclear matter for different densities and different proton-neutron asymmetry parameter $s$. Our model exhibits liquid-gas phase transition below a critical temperature $T_c$, and predicts a monotonic decreasing of $T_c$ as the magnitude of $s$ is increased. The dependence of the nuclear matter isotherms on the asymmetry parameter $s$ is discussed.

S. Ray; J. Shamanna; T. T. S. Kuo

1996-08-13T23:59:59.000Z

138

Nuclear Bar, Star Formation and Gas Fueling in the Active Galaxy NGC 4303  

E-Print Network (OSTI)

A combination of Hubble Space Telescope (HST) WFPC2 and NICMOS images are used to investigate the gas/dust and stellar structure inside the central 300 pc of the nearby active galaxy NGC 4303. The NICMOS H-band (F160W) image reveals a bright core and a nuclear elongated bar-like structure of 250 pc in diameter. The bar is centered on the bright core, and its major axis is oriented in proyection along the spin axis of the nuclear gaseous rotating disk recently detected (Colina & Arribas 1999). The V-H (F606W - F160W) image reveals a complex gas/dust distribution with a two-arm spiral structure of about 225 pc in radius. The southwestern arm is traced by young star-forming knots while the northeastern arm is detected by the presence of dust lanes. These spirals do not have a smooth structure but rather they are made of smaller flocculent spirals or filament-like structures. The magnitudes and colors of the star-forming knots are typical of clusters of young stars with masses of 0.5 to 1 x $10^5 M_{solar}, and ages of 5 to 25 million years. The overall structure of the nuclear spirals as well as the size, number and masses of the star-forming knots are explained in the context of a massive gaseous nuclear disk subject to self-gravitational instabilities and to the gravitational field created by the nuclear bar. According to the model, the gaseous disk has a mass of about 5 x 10^7 M_{solar} inside a radius of 400 pc, the bar has a radius of 150 pc and a pattern speed of about 0.5 Myr^{-1}, and the average mass accretion rate into the core (R < 8 pc) is about 0.01 M_{solar}$ yr^{-1} for about 80 Myr.

L. Colina; K. Wada

1999-10-19T23:59:59.000Z

139

Revised rail-stop exposure model for incident-free transport of nuclear waste  

SciTech Connect

This report documents a model for estimating railstop doses that occur during incident-free transport of nuclear waste by rail. The model, which has been incorporated into the RADTRAN III risk assessment code, can be applied to general freight and dedicated train shipments of waste.

Ostmeyer, R.M.

1986-02-01T23:59:59.000Z

140

Characterization and Dose Modeling of Soil, Sediment and Bedrock During Nuclear Power Plant Decommissioning  

Science Conference Proceedings (OSTI)

A decommissioning nuclear power plant must confirm that the radionuclides present in the soils, sediments, and bedrock left on site at the time of license termination will meet the appropriate dose limits for site release. This process involves the characterization, dose modeling, and if required, remediation, of these media. At some decommissioning nuclear power plants, the management of contaminated soil, sediments, and bedrocks was a major project that led to generation of remediation projects and rad...

2009-11-20T23:59:59.000Z

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

Progress toward bridging from atomistic to continuum modeling to predict nuclear waste glass dissolution.  

SciTech Connect

This report summarizes research performed for the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Subcontinuum and Upscaling Task. The work conducted focused on developing a roadmap to include molecular scale, mechanistic information in continuum-scale models of nuclear waste glass dissolution. This information is derived from molecular-scale modeling efforts that are validated through comparison with experimental data. In addition to developing a master plan to incorporate a subcontinuum mechanistic understanding of glass dissolution into continuum models, methods were developed to generate constitutive dissolution rate expressions from quantum calculations, force field models were selected to generate multicomponent glass structures and gel layers, classical molecular modeling was used to study diffusion through nanopores analogous to those in the interfacial gel layer, and a micro-continuum model (K{mu}C) was developed to study coupled diffusion and reaction at the glass-gel-solution interface.

Zapol, Peter (Argonne National Laboratory, Argonne, IL); Bourg, Ian (Lawrence Berkeley National Laboratories, Berkeley, CA); Criscenti, Louise Jacqueline; Steefel, Carl I. (Lawrence Berkeley National Laboratories, Berkeley, CA); Schultz, Peter Andrew

2011-10-01T23:59:59.000Z

142

Use of the nuclear model code GNASH to calculate cross section data at energies up to 100 MeV  

Science Conference Proceedings (OSTI)

The nuclear theory code GNASH has been used to calculate nuclear data for incident neutrons, protons, and deuterons at energies up to 100 MeV. Several nuclear models and theories are important in the 10--100 MeV energy range, including Hauser-Feshbach statistical theory, spherical and deformed optical model, preequilibrium theory, nuclear level densities, fission theory, and direct reaction theory. In this paper we summarize general features of the models in GNASH and describe the methodology utilized to determine relevant model parameters. We illustrate the significance of several of the models and include comparisons with experimental data for certain target materials that are important in applications.

Young, P.G.; Chadwick, M.B.; Bosoian, M.

1992-12-01T23:59:59.000Z

143

Use of the nuclear model code GNASH to calculate cross section data at energies up to 100 MeV  

Science Conference Proceedings (OSTI)

The nuclear theory code GNASH has been used to calculate nuclear data for incident neutrons, protons, and deuterons at energies up to 100 MeV. Several nuclear models and theories are important in the 10--100 MeV energy range, including Hauser-Feshbach statistical theory, spherical and deformed optical model, preequilibrium theory, nuclear level densities, fission theory, and direct reaction theory. In this paper we summarize general features of the models in GNASH and describe the methodology utilized to determine relevant model parameters. We illustrate the significance of several of the models and include comparisons with experimental data for certain target materials that are important in applications.

Young, P.G.; Chadwick, M.B.; Bosoian, M.

1992-01-01T23:59:59.000Z

144

Executive Bios: Christopher Grandy - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

145

Nuclear Engineering Division of Argonne National Laboratory:...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

146

Fuel Cycle Technologies Program - Nuclear Engineering Division...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

147

International Safety Projects - Nuclear Engineering Division...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

148

The Dawn of the Nuclear Age  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

149

Facility Safety Assessment - Nuclear Engineering Division (Argonne...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

150

Computer Facilities - Nuclear Engineering Division (Argonne)  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

151

Advanced Computation & Visualization - Nuclear Engineering Division...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

152

Steam Generator Tube Integrity Facilities - Nuclear Engineering...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

153

Safety - Vulnerability Assessment Team - Nuclear Engineering...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

154

Physics and Engineering Models | National Nuclear Security Administrat...  

National Nuclear Security Administration (NNSA)

initiatives such as academic alliances and Russian programs are included here. Thermal & Fluid Response This area develops and delivers predictive science-based models that...

155

The statistical multifragmentation model for liquid-gas phase transition with a compressible nuclear liquid  

E-Print Network (OSTI)

We propose a new formulation of the statistical multifragmentation model based on the analysis of the virial expansion for a system of the nuclear fragments of all sizes. The developed model not only enables us to account for short-range repulsion, but also to calculate the surface free energy which is induced by the interaction between the fragments. We propose a new parameterization for the liquid phase pressure which allows us to introduce a compressible nuclear liquid into the statistical multifragmentation model. The resulting model is exactly solvable and has no irregular behavior of the isotherms in the mixed phase region that is typical for mean-field models. The general conditions for the 1-st and 2-nd (or higher) order phase transitions are formulated. It is shown that all endpoints of the present model phase diagram are the tricritical points, if the Fisher exponent $\\tau$ is in the range $\\{3}{2} \\le \\tau \\le 2$. The treatment of nuclear liquid compressibility allows us to reduce the tricritical endpoint density of the statistical multifragmentation model to one third of the normal nuclear density. A specific attention is paid to of the fragment size distributions in the region of a negative surface tension at supercritical temperatures.

V. V. Sagun; A. I. Ivanytskyi; K. A. Bugaev; I. N. Mishustin

2013-06-10T23:59:59.000Z

156

New Olodels COnfirOl nuclear winter Everything from purely mathematical models to forest fire studies shows that  

E-Print Network (OSTI)

-scale nuclear war. Smoke- es- pecially black, sooty smoke from cities and industrial plants The basic theoryNew Olodels COnfirOl nuclear winter Everything from purely mathematical models to forest fire studies shows that even a small nuclear war would devastate the earth. But the Pentagon's only policy

Robock, Alan

157

Power system simulation and optimization models for planning nuclear refueling cycles  

SciTech Connect

From Operation Research Society of America; San Diego, California, USA (12 Nov 1973). The mid-range system being modeled may include a mix of fossil, nuclear, hydro, pumped-storage, and peaking units. For any predetermined nuclear refueling schedule, the program (ORSIM) determines an approximately optical plan of operation for the system. This includes the determination of a maintenance schedule for the non-nuclear units and a schedule of energy delivery for each plant in the system. The criterion of optimality is the minimization of the total discounted operating cost of the system over the specified study period. Over this period, the model computes the expected station load factors, the loss of load probability and unserved energy for the system, and the production costs of operating so as to meet the forecasted loads on the system. The code takes account of variations and growth in demand over the planning horizon, occurrence of unit forced outages, planned shutdowns for nuclear refuelings, maintenance scheduling, allocations of fixed hydro and nuclear energies, and interactions between nuclear unit reloadings and fuel costs. 13 references. (auth)

Turnage, J.C.; Bennett, L.L.; Joy, D.S.; Prince, B.E.

1973-10-01T23:59:59.000Z

158

Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)  

SciTech Connect

The Nuclear Energy Computational Fluid Dynamics Advanced Modeling and Simulation (NE-CAMS) system is being developed at the Idaho National Laboratory (INL) in collaboration with Bettis Laboratory, Sandia National Laboratory (SNL), Argonne National Laboratory (ANL), Utah State University (USU), and other interested parties with the objective of developing and implementing a comprehensive and readily accessible data and information management system for computational fluid dynamics (CFD) verification and validation (V&V) in support of nuclear energy systems design and safety analysis. The two key objectives of the NE-CAMS effort are to identify, collect, assess, store and maintain high resolution and high quality experimental data and related expert knowledge (metadata) for use in CFD V&V assessments specific to the nuclear energy field and to establish a working relationship with the U.S. Nuclear Regulatory Commission (NRC) to develop a CFD V&V database, including benchmark cases, that addresses and supports the associated NRC regulations and policies on the use of CFD analysis. In particular, the NE-CAMS system will support the Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program, which aims to develop and deploy advanced modeling and simulation methods and computational tools for reliable numerical simulation of nuclear reactor systems for design and safety analysis. Primary NE-CAMS Elements There are four primary elements of the NE-CAMS knowledge base designed to support computer modeling and simulation in the nuclear energy arena as listed below. Element 1. The database will contain experimental data that can be used for CFD validation that is relevant to nuclear reactor and plant processes, particularly those important to the nuclear industry and the NRC. Element 2. Qualification standards for data evaluation and classification will be incorporated and applied such that validation data sets will result in well-defined, well-characterized data. Element 3. Standards will be established for the design and operation of experiments for the generation of new validation data sets that are to be submitted to NE-CAMS that addresses the completeness and characterization of the dataset. Element 4. Standards will be developed for performing verification and validation (V&V) to establish confidence levels in CFD analyses of nuclear reactor processes; such processes will be acceptable and recognized by both CFD experts and the NRC.

Kimberlyn C. Mousseau

2011-10-01T23:59:59.000Z

159

Capabilities - Nuclear Engineering Division (Argonne)  

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Nuclear Waste Form and Repository Performance Modeling Nuclear Systems Technologies Nuclear Criticality Safety Research Reactor Analysis System Process Monitoring,...

160

Proxying: Reducing PC Energy Use With Network Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

vendors, component manufacturers, and PC companies. Proxying applies directly to other devices and will be an important strategy to reduce electricity consumption in the...

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

Nuclear criticality safety modeling of an LEU deposit  

DOE Green Energy (OSTI)

The construction of the Oak Ridge Gaseous Diffusion Plant (now known as the K-25 Site) began during World War H and eventually consisted of five major process buildings: K-25, K-27, K-29, K-31, and K-33. The plant took natural (0.711% {sup 231}U) uranium as feed and processed it into both low-enriched uranium (LEU) and high-enriched uranium (HEU) with concentrations up to {approximately}93% {sup 231}U. The K-25 and K-27 buildings were shut down in 1964, but the rest of the plant produced LEU until 1985. During operation, inleakage of humid air into process piping and equipment caused reactions with gaseous uranium hexafluoride (UF{sub 6}) that produced nonvolatile uranyl fluoride (UO{sub 2}F{sub 2}) deposits. As part of shutdown, most of the uranium was evacuated as volatile UF{sub 6}. The UO{sub 2}F{sub 2} deposits remained. The U.S. Department of Energy has mitiated a program to unprove nuclear criticality safety by removing the larger enriched uranium deposits.

Haire, M.J.; Elam, K.R.; Jordan, W.C.; Dahl, T.L.

1996-11-01T23:59:59.000Z

162

NUCLEAR DATA AND MEASUREMENTS REPORTS 61-80 - Nuclear Data Program...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

163

NUCLEAR DATA AND MEASUREMENTS REPORTS 81-100 - Nuclear Data Program...  

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Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

164

Color symmetrical superconductivity in a schematic nuclear quark model  

E-Print Network (OSTI)

In this note, a novel BCS-type formalism is constructed in the framework of a schematic QCD inspired quark model, having in mind the description of color symmetrical superconducting states. The physical properties of the BCS vacuum (average numbers of quarks of different colors) remain unchanged under an arbitrary color rotation. In the usual approach to color superconductivity, the pairing correlations affect only the quasi-particle states of two colors, the single particle states of the third color remaining unaffected by the pairing correlations. In the theory of color symmetrical superconductivity here proposed, the pairing correlations affect symmetrically the quasi-particle states of the three colors and vanishing net color-charge is automatically insured. It is found that the groundstate energy of the color symmetrical sector of the Bonn model is well approximated by the average energy of the color symmetrical superconducting state proposed here.

Henrik Bohr; João da Providência

2009-09-14T23:59:59.000Z

165

Quantum chaos in the nuclear collective model: II. Peres lattices  

E-Print Network (OSTI)

This is a continuation of our preceding paper devoted to signatures of quantum chaos in the geometric collective model of atomic nuclei. We apply the method by Peres to study ordered and disordered patterns in quantum spectra drawn as lattices in the plane of energy vs. average of a chosen observable. A good qualitative agreement with standard measures of chaos is manifested. The method provides an efficient tool for studying structural changes of eigenstates across quantum spectra of general systems.

Pavel Stransky; Petr Hruska; Pavel Cejnar

2009-02-23T23:59:59.000Z

166

Augmented l1 and Nuclear-Norm Models with a Globally Linearly ...  

E-Print Network (OSTI)

and X? and XF are the nuclear and Frobenius norms of X, respectively. We show that they let .... the total energy x0. 2 is roughly ..... Some expert readers may know that in theory, given matrix A, whether or not model (1) can exactly recover x0 ...

167

Modeling Human Behavior in the Aftermath of a Hypothetical Improvised Nuclear Detonation  

E-Print Network (OSTI)

Modeling Human Behavior in the Aftermath of a Hypothetical Improvised Nuclear Detonation Nidhi, human-initiated crisis in the center of Washington D.C. Prior studies of this scenario have focused on the agent design and multiagent interaction, and present initial results on how rapid restoration

Swarup, Samarth

168

Evolution of a Visual Impact Model to Evaluate Nuclear Plant Siting and Design Option1  

E-Print Network (OSTI)

for Analysis and Management of the Visual Resource, Incline Village, Nevada, April 23-25, 1979. 2 / AssociatesEvolution of a Visual Impact Model to Evaluate Nuclear Plant Siting and Design Option1 2/ Brian A/ The method can be used to train evaluators to use explicit criteria (vividness, intactness and unity

Standiford, Richard B.

169

Designing a component-based architecture for the modeling and simulation of nuclear fuels and reactors  

Science Conference Proceedings (OSTI)

Concerns over the environment and energy security have recently prompted renewed interest in the U. S. in nuclear energy. Recognizing this, the U. S. Dept. of Energy has launched an initiative to revamp and modernize the role that modeling and simulation ...

Jay J. Billings; Wael R. Elwasif; Lee M. Hively; David E. Bernholdt; John M. Hetrick, III; Tim Bohn

2009-11-01T23:59:59.000Z

170

Nuclear Reactor/Hydrogen Process Interface Including the HyPEP Model  

DOE Green Energy (OSTI)

The Nuclear Reactor/Hydrogen Plant interface is the intermediate heat transport loop that will connect a very high temperature gas-cooled nuclear reactor (VHTR) to a thermochemical, high-temperature electrolysis, or hybrid hydrogen production plant. A prototype plant called the Next Generation Nuclear Plant (NGNP) is planned for construction and operation at the Idaho National Laboratory in the 2018-2021 timeframe, and will involve a VHTR, a high-temperature interface, and a hydrogen production plant. The interface is responsible for transporting high-temperature thermal energy from the nuclear reactor to the hydrogen production plant while protecting the nuclear plant from operational disturbances at the hydrogen plant. Development of the interface is occurring under the DOE Nuclear Hydrogen Initiative (NHI) and involves the study, design, and development of high-temperature heat exchangers, heat transport systems, materials, safety, and integrated system models. Research and development work on the system interface began in 2004 and is expected to continue at least until the start of construction of an engineering-scale demonstration plant.

Steven R. Sherman

2007-05-01T23:59:59.000Z

171

Strategic Plan for Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)  

SciTech Connect

NE-KAMS knowledge base will assist computational analysts, physics model developers, experimentalists, nuclear reactor designers, and federal regulators by: (1) Establishing accepted standards, requirements and best practices for V&V and UQ of computational models and simulations, (2) Establishing accepted standards and procedures for qualifying and classifying experimental and numerical benchmark data, (3) Providing readily accessible databases for nuclear energy related experimental and numerical benchmark data that can be used in V&V assessments and computational methods development, (4) Providing a searchable knowledge base of information, documents and data on V&V and UQ, and (5) Providing web-enabled applications, tools and utilities for V&V and UQ activities, data assessment and processing, and information and data searches. From its inception, NE-KAMS will directly support nuclear energy research, development and demonstration programs within the U.S. Department of Energy (DOE), including the Consortium for Advanced Simulation of Light Water Reactors (CASL), the Nuclear Energy Advanced Modeling and Simulation (NEAMS), the Light Water Reactor Sustainability (LWRS), the Small Modular Reactors (SMR), and the Next Generation Nuclear Power Plant (NGNP) programs. These programs all involve computational modeling and simulation (M&S) of nuclear reactor systems, components and processes, and it is envisioned that NE-KAMS will help to coordinate and facilitate collaboration and sharing of resources and expertise for V&V and UQ across these programs. In addition, from the outset, NE-KAMS will support the use of computational M&S in the nuclear industry by developing guidelines and recommended practices aimed at quantifying the uncertainty and assessing the applicability of existing analysis models and methods. The NE-KAMS effort will initially focus on supporting the use of computational fluid dynamics (CFD) and thermal hydraulics (T/H) analysis for M&S of nuclear reactor systems, components and processes, and will later expand to include materials, fuel system performance and other areas of M&S as time and funding allow.

Rich Johnson; Kimberlyn C. Mousseau; Hyung Lee

2011-09-01T23:59:59.000Z

172

A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats  

Science Conference Proceedings (OSTI)

This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the range of possibilities. Once an object is generated, its radiation signature is calculated using a 1-dimensional deterministic transport code. Objects that do not make sense based on physics principles or other constraints are rejected. Thus, the model can be used to generate a population of spectral signatures that spans a large space, including smuggled nuclear material and nuclear weapons.

Nelson, K; Sokkappa, P

2008-10-29T23:59:59.000Z

173

Multi-Dimensional Modeling of Nova with Realistic Nuclear Physics  

DOE Green Energy (OSTI)

This contract covered the period from 03/09/2010 to 09/30/2010. Over this period, we adapted the low Mach number hydrodynamics code MAESTRO to perform simulations of novae. A nova is the thermonuclear runaway of an accreted hydrogen layer on the surface of a white dwarf. As the accreted layer grows in mass, the temperature and density at the base increase to the point where hydrogen fusion can begin by the CNO cycle - a burning process that uses carbon, nitrogen, and oxygen to complete the fusion of four hydrogen nuclei into one helium-4 nucleus. At this point, we are running initial models of nova, exploring the details of the convection. In the follow-on contract to this one, we will continue this investigation.

Zingale, M; Hoffman, R D

2011-01-27T23:59:59.000Z

174

Nuclear spirals in galaxies: gas response to asymmetric potential. II. Hydrodynamical models  

E-Print Network (OSTI)

Nuclear spirals naturally form as a gas response to non-axisymmetry in the galactic potential, even if the degree of this asymmetry is very small. Linear wave theory well describes weak nuclear spirals, but spirals induced by stronger asymmetries in the potential are clearly beyond the linear regime. Hydrodynamical models indicate spiral shocks in this latter case that, depending on how the spiral intersects the x2 orbits, either get damped, leading to the formation of the nuclear ring, or get strengthened, and propagate towards the galaxy centre. Central massive black hole of sufficient mass can allow the spiral shocks to extend all the way to its immediate vicinity, and to generate gas inflow up to 0.03 M_sun/yr, which coincides with the accretion rates needed to power luminous local Active Galactic Nuclei.

Maciejewski, Witold

2004-01-01T23:59:59.000Z

175

Nuclear spirals in galaxies: gas response to asymmetric potential. II. Hydrodynamical models  

E-Print Network (OSTI)

Nuclear spirals naturally form as a gas response to non-axisymmetry in the galactic potential, even if the degree of this asymmetry is very small. Linear wave theory well describes weak nuclear spirals, but spirals induced by stronger asymmetries in the potential are clearly beyond the linear regime. Hydrodynamical models indicate spiral shocks in this latter case that, depending on how the spiral intersects the x2 orbits, either get damped, leading to the formation of the nuclear ring, or get strengthened, and propagate towards the galaxy centre. Central massive black hole of sufficient mass can allow the spiral shocks to extend all the way to its immediate vicinity, and to generate gas inflow up to 0.03 M_sun/yr, which coincides with the accretion rates needed to power luminous local Active Galactic Nuclei.

Witold Maciejewski

2004-08-05T23:59:59.000Z

176

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

177

Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test  

SciTech Connect

The purpose of this work is to characterize groundwater flow and contaminant transport at the Shoal underground nuclear test through numerical modeling using site-specific hydrologic data. The ultimate objective is the development of a contaminant boundary, a model-predicted perimeter defining the extent of radionuclide-contaminated groundwater from the underground test throughout 1,000 years at a prescribed level of confidence. This boundary will be developed using the numerical models described here, after they are approved for that purpose by DOE and NDEP.

K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

2004-03-01T23:59:59.000Z

178

Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test  

Science Conference Proceedings (OSTI)

Groundwater flow and radionuclide transport at the Shoal underground nuclear test are characterized using three-dimensional numerical models, based on site-specific hydrologic data. The objective of this modeling is to provide the flow and transport models needed to develop a contaminant boundary defining the extent of radionuclide-contaminated groundwater at the site throughout 1,000 years at a prescribed level of confidence. This boundary will then be used to manage the Project Shoal Area for the protection of the public and the environment.

K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

2004-03-01T23:59:59.000Z

179

User`s guide and documentation manual for ``PC-Gel`` simulator  

Science Conference Proceedings (OSTI)

PC-GEL is a three-dimensional, three-phase (oil, water, and gas) permeability modification simulator developed by incorporating an in-situ gelation model into a black oil simulator (BOAST) for personal computer application. The features included in the simulator are: transport of each chemical species of the polymer/crosslinker system in porous media, gelation reaction kinetics of the polymer with crosslinking agents, rheology of the polymer and gel, inaccessible pore volume to macromolecules, adsorption of chemical species on rock surfaces, retention of gel on the rock matrix, and permeability reduction caused by the adsorption of polymer and gel. The in-situ gelation model and simulator were validated against data reported in the literature. The simulator PC-GEL is useful for simulating and optimizing any combination of primary production, waterflooding, polymer flooding, and permeability modification treatments. A general background of permeability modification using crosslinked polymer gels is given in Section I and the governing equations, mechanisms, and numerical solutions of PC-GEL are given in Section II. Steps for preparing an input data file with reservoir and gel-chemical transport data, and recurrent data are described in Sections III and IV, respectively. Example data inputs are enclosed after explanations of each input line to help the user prepare data files. Major items of the output files are reviewed in Section V. Finally, three sample problems for running PC-GEL are described in Section VI, and input files and part of the output files of these problems are listed in the appendices. For the user`s reference a copy of the source code of PC-GEL computer program is attached in Appendix A.

Chang, Ming-Ming; Gao, Hong W.

1993-10-01T23:59:59.000Z

180

$?$-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

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

Nuclear liquid-gas phase transition within the lattice gas model  

E-Print Network (OSTI)

We study the nuclear liquid-gas phase transition on the basis of a two-component lattice gas model. A Metropolis type of sampling method is used to generate microscopic states in the canonical ensemble. The effective equation of state and fragment mass distributions are evaluated in a wide range of temperatures and densities. A definition of the phase coexistence region appropriate for mesoscopic systems is proposed. The caloric curve resulting from different types of freeze-out conditions are presented.

J. Borg; I. N. Mishustin; J. P. Bondorf

1998-09-25T23:59:59.000Z

182

Comparison of Decommissioning Dose Modeling Codes for Nuclear Power Plant Use: RESRAD and DandD  

Science Conference Proceedings (OSTI)

A number of power plants are currently in the decommissioning phase. As the plants seek to terminate their operating license, they need to successfully conduct definite dose assessments. To assist these utilities in selecting an analysis code and appropriate input data, EPRI conducted a code comparison. However, this report was done as the industry's input to the NRC on their evolving review and improvement of decommissioning modeling. In early 2000, EPRI will publish a report for the commercial nuclear ...

1999-10-29T23:59:59.000Z

183

Modeling Nuclear Pasta and the Transition to Uniform Nuclear Matter with the 3D Skyrme-Hartree-Fock Method at Finite Temperature I: Core-Collapse Supernovae  

E-Print Network (OSTI)

The first results of a new three-dimensional, finite temperature Skyrme-Hartree-Fock+BCS study of the properties of inhomogeneous nuclear matter at densities and temperatures leading to the transition to uniform nuclear matter are presented. Calculations are carried out in a cubic box representing a unit cell of the locally periodic structure of the matter. A constraint is placed on the two independent components of the quadrupole moment of the neutron density in order to investigate the dependence of the total energy-density of matter on the geometry of the nuclear structure in the unit cell. This approach allows self-consistent modeling of effects such as (i) neutron drip, resulting in a neutron gas external to the nuclear structure, (ii) shell effects of bound and unbound nucleons, (iii) the variety of exotic nuclear shapes that emerge, collectively termed `nuclear pasta' and (iv) the dissolution of these structures into uniform nuclear matter as density and/or temperature increase. In part I of this work ...

Stone, W G Newton J R

2009-01-01T23:59:59.000Z

184

Benchmarking GEANT4 nuclear models for carbon-therapy at 95 MeV/A  

E-Print Network (OSTI)

In carbon-therapy, the interaction of the incoming beam with human tissues may lead to the production of a large amount of nuclear fragments and secondary light particles. An accurate estimation of the biological dose deposited into the tumor and the surrounding healthy tissues thus requires sophisticated simulation tools based on nuclear reaction models. The validity of such models requires intensive comparisons with as many sets of experimental data as possible. Up to now, a rather limited set of double di erential carbon fragmentation cross sections have been measured in the energy range used in hadrontherapy (up to 400 MeV/A). However, new data have been recently obtained at intermediate energy (95 MeV/A). The aim of this work is to compare the reaction models embedded in the GEANT4 Monte Carlo toolkit with these new data. The strengths and weaknesses of each tested model, i.e. G4BinaryLightIonReaction, G4QMDReaction and INCL++, coupled to two di fferent de-excitation models, i.e. the generalized evaporation model and the Fermi break-up are discussed.

J. Dudouet; D. Cussol; D. Durand; M. Labalme

2013-09-06T23:59:59.000Z

185

NARAC Modeling During the Response to the Fukushima Dai-ichi Nuclear Power Plant Emergency  

SciTech Connect

This paper summarizes the activities of the National Atmospheric Release Advisory Center (NARAC) during the Fukushima Dai-ichi nuclear power plant crisis. NARAC provided a wide range of products and analyses as part of its support including: (1) Daily Japanese weather forecasts and hypothetical release (generic source term) dispersion predictions to provide situational awareness and inform planning for U.S. measurement data collection and field operations; (2) Estimates of potential dose in Japan for hypothetical scenarios developed by the Nuclear Regulatory Commission (NRC) to inform federal government considerations of possible actions that might be needed to protect U.S. citizens in Japan; (3) Estimates of possible plume arrival times and dose for U.S. locations; and (4) Plume model refinement and source estimation based on meteorological analyses and available field data. The Department of Energy/National Nuclear Security Administration (DOE/NNSA) deployed personnel to Japan and stood up 'home team' assets across the DOE complex to aid in assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. The DOE Nuclear Incident Team (NIT) coordinated response activities, while DOE personnel provided predictive modeling, air and ground monitoring, sample collection, laboratory analysis, and data assessment and interpretation. DOE deployed the Aerial Measuring System (AMS), Radiological Assistance Program (RAP) personnel, and the Consequence Management Response Team (CMRT) to Japan. DOE/NNSA home team assets included the Consequence Management Home Team (CMHT); National Atmospheric Release Advisory Center (NARAC); Radiation Emergency Assistance Center/Training Site (REAC/TS); and Radiological Triage. NARAC was activated by the DOE/NNSA on March 11, shortly after the Tohoku earthquake and tsunami occurred. The center remained on active operations through late May when DOE ended its deployment to Japan. Over 32 NARAC staff members, supplemented by other LLNL scientists, invested over 5000 person-hours of time and generated over 300 analyses and predictions.

Sugiyama, G; Nasstrom, J S; Probanz, B; Foster, K T; Simpson, M; Vogt, P; Aluzzi, F; Dillon, M; Homann, S

2012-02-14T23:59:59.000Z

186

SOCIAL MODELING IN ASSESSEMENT OF A STATE’S PROPENSITY FOR NUCLEAR PROLIFERATION  

SciTech Connect

This paper presents approach for assessing a State’s propensity for nuclear weapons proliferation using social modeling. We supported this modeling by first reviewing primarily literature by social scientists on factors related to the propensity of a State to proliferation and by leveraging existing relevant data compiled by social scientists. We performed a number of validation tests on our model including one that incorporates use of benchmark data defining the proliferation status of countries in the years between 1945 and 2000. We exercise the BN model against a number of country cases representing different perceived levels of proliferation risk. We also describe how the BN model could be further refined to be a proliferation assessment tool for decision making.

Dalton, Angela C.; Whitney, Paul D.; Coles, Garill A.; Brothers, Alan J.

2011-07-17T23:59:59.000Z

187

Proceedings of the Numerical Modeling for Underground Nuclear Test Monitoring Symposium  

SciTech Connect

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

188

Pre-engagement process improvement in IBM PC services  

E-Print Network (OSTI)

The front end of the IBM PC factory integration & deployment process is a pre-engagement process. In this study, the pre-engagement process, was analyzed. The organizational structure in the pre-engagement process and the ...

Zuo, Jie, M. Eng. Massachusetts Institute of Technology

2007-01-01T23:59:59.000Z

189

Development of Biometric Membrane for Near Zero PC Power Plant...  

NLE Websites -- All DOE Office Websites (Extended Search)

Biomimetic memBrane for near Zero pc power plant emissions Background CO 2 capture is the largest single cost element of the Carbon Capture and Sequestration (CCS) program,...

190

Using Normal PC to Index and Retrieval Terabyte Document ...  

Science Conference Proceedings (OSTI)

... The size of total anchor text is about 3.9G. 3 Data set reduction and reform ... CPU RAM Harddisk OS Complier PC1 AMD Athlong64 3000+ ...

2005-02-10T23:59:59.000Z

191

Large scale nuclear sensor monitoring and diagnostics by means of an ensemble of regression models based on Evolving Clustering Methods  

E-Print Network (OSTI)

signals measured at a nuclear Boiling Water Reactor (BWR) located in Oskarshamn, Sweden. A total number NLarge scale nuclear sensor monitoring and diagnostics by means of an ensemble of regression models the validation and reconstruction of 792 signals measured at the Swedish boiling water reactor located

192

The Development of Simulation Model for D2O Supply System in Heavy Water Nuclear Power Plant  

Science Conference Proceedings (OSTI)

The main purpose of this research is improvement of performance in control system for heavy water supply system of nuclear fuel change machine. Before started design of control system, the model of target system is needed because it is hard to test and ... Keywords: simulation, nuclear, heavy-water, D2O, MATLAB

Sung-Won Choi; Seong-Geun Kwak; Ji-Hyoung Ryu; Kil-To Chong; Chang-Goo Lee

2012-05-01T23:59:59.000Z

193

Validity of pair truncation of the nuclear shell model in {sup 46}Ca  

SciTech Connect

We study the validity of pair truncation of the nuclear shell model by using the semimagic nucleus {sup 46}Ca. We present low-lying states and their E2 transition rates based on both nucleon pair approximation (NPA) and exact shell-model (SM) calculations. We also calculate overlaps between wave functions of low-lying states calculated by using the NPA and those calculated by using the SM. Our calculated results show a remarkable agreement between the NPA results and the SM results, although the NPA is a drastic truncation of the SM.

Lei, Y.; Xu, Z. Y. [Department of Physics, Shanghai Jiao Tong University, Shanghai 200240 (China); Zhao, Y. M. [Department of Physics, Shanghai Jiao Tong University, Shanghai 200240 (China); Center of Theoretical Nuclear Physics, National Laboratory of Heavy Ion Accelerator, Lanzhou 730000 (China); CCAST, World Laboratory, Post Office Box 8730, Beijing 100080 (China); Arima, A. [Department of Physics, Shanghai Jiao Tong University, Shanghai 200240 (China); Science Museum, Japan Science Foundation, 2-1 Kitanomaru-koen, Chiyoda-ku, Tokyo 102-0091 (Japan)

2009-12-15T23:59:59.000Z

194

Modeling Nuclear Pasta and the Transition to Uniform Nuclear Matter with the 3D Skyrme-Hartree-Fock Method at Finite Temperature I: Core-Collapse Supernovae  

E-Print Network (OSTI)

The first results of a new three-dimensional, finite temperature Skyrme-Hartree-Fock+BCS study of the properties of inhomogeneous nuclear matter at densities and temperatures leading to the transition to uniform nuclear matter are presented. Calculations are carried out in a cubic box representing a unit cell of the locally periodic structure of the matter. A constraint is placed on the two independent components of the quadrupole moment of the neutron density in order to investigate the dependence of the total energy-density of matter on the geometry of the nuclear structure in the unit cell. This approach allows self-consistent modeling of effects such as (i) neutron drip, resulting in a neutron gas external to the nuclear structure, (ii) shell effects of bound and unbound nucleons, (iii) the variety of exotic nuclear shapes that emerge, collectively termed `nuclear pasta' and (iv) the dissolution of these structures into uniform nuclear matter as density and/or temperature increase. In part I of this work the calculation of the properties of inhomogeneous nuclear matter in the core collapse of massive stars is reported. Calculations are performed at baryon number densities of $n_{\\rm b}$ = 0.04 - 0.12 fm$^{\\rm -3}$, a proton fraction of $y_{\\rm p}=0.3$ and temperatures in the range 0 - 7.5 MeV. A wide variety of nuclear shapes are shown to emerge. It is suggested that thermodynamical properties change smoothly in the pasta regime up to the transition to uniform matter; at that transition, thermodynamic properties of the matter vary discontinuously.

W. G. Newton J. R. Stone

2009-04-30T23:59:59.000Z

195

REACTOR PHYSICS MODELING OF SPENT RESEARCH REACTOR FUEL FOR TECHNICAL NUCLEAR FORENSICS  

SciTech Connect

Technical nuclear forensics (TNF) refers to the collection, analysis and evaluation of pre- and post-detonation radiological or nuclear materials, devices, and/or debris. TNF is an integral component, complementing traditional forensics and investigative work, to help enable the attribution of discovered radiological or nuclear material. Research is needed to improve the capabilities of TNF. One research area of interest is determining the isotopic signatures of research reactors. Research reactors are a potential source of both radiological and nuclear material. Research reactors are often the least safeguarded type of reactor; they vary greatly in size, fuel type, enrichment, power, and burn-up. Many research reactors are fueled with highly-enriched uranium (HEU), up to {approx}93% {sup 235}U, which could potentially be used as weapons material. All of them have significant amounts of radiological material with which a radioactive dispersal device (RDD) could be built. Therefore, the ability to attribute if material originated from or was produced in a specific research reactor is an important tool in providing for the security of the United States. Currently there are approximately 237 operating research reactors worldwide, another 12 are in temporary shutdown and 224 research reactors are reported as shut down. Little is currently known about the isotopic signatures of spent research reactor fuel. An effort is underway at Savannah River National Laboratory (SRNL) to analyze spent research reactor fuel to determine these signatures. Computer models, using reactor physics codes, are being compared to the measured analytes in the spent fuel. This allows for improving the reactor physics codes in modeling research reactors for the purpose of nuclear forensics. Currently the Oak Ridge Research reactor (ORR) is being modeled and fuel samples are being analyzed for comparison. Samples of an ORR spent fuel assembly were taken by SRNL for analytical and radiochemical analysis. The fuel assembly was modeled using MONTEBURNS(MCNP5/ ORIGEN2.2) and MCNPX/CINDER90. The results from the models have been compared to each other and to the measured data.

Nichols, T.; Beals, D.; Sternat, M.

2011-07-18T23:59:59.000Z

196

Executive Bios: Dr. Robert N. Hill - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

197

Related Sites, Experimental Resources for Nuclear Data Studies...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

198

Executive Bios: Dr. David C. Wade - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

199

ANS President interviewed at the Argonne Booth during the Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

200

Executive Bios: Jerome L. Gaston - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

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

Executive Bios: A. C. (Paul) Raptis - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

202

Executive Bios: Dr. Hussein S. Khalil - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

203

Argonne's role in DOE/NNSA International Nuclear Safeguards and...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

204

Argonne staff members elected to American Nuclear Society governance...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

205

Reactor Safety Testing and Analysis - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

206

Executive Bios: Dr. Temitope Taiwo - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

207

Sloshing response of module-type worm tank - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

208

Executive Bios: Dr. Thomas F. Ewing - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

209

Executive Bios: Dr. John G. Stevens - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

210

Vulnerability Assessment Team (VAT) in the News - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

211

Executive Bios: Dr. Pete Heine - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

212

Executive Bios: Dr. Tanju Sofu - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

213

Risk and Safety Assessments - Nuclear Engineering Division (Argonne...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

214

Executive Bios: Dr. Ken Natesan - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

215

Fluctuations in the Gravitational, Strong and Weak Nuclear Fields through an Effective Harmonic Oscillator Model  

E-Print Network (OSTI)

We propose an effective harmonic oscillator model in order to treat the fluctuations of the gravitational, strong and weak nuclear fields. With respect to the gravitational field, first we use the model to estimate its fluctuating strength, necessary to decohere the wavefunction of a cubic centimeter of air at the standard temperature and pressure conditions. Second, the fluctuation of a point mass through a distance equal to the Planck length leads to the self-gravitational interaction of a particle, which can be related to its de Broglie frequency. Third, by making the equality of the fluctuating field strength with the gravitational field of a mass M at half of its Schwarzschild radius, we obtain an estimate of the mass of the Universe. We also consider the fluctuations of the strong nuclear field, as a means to estimate the separation in energy between the ground state and the centroid of the excitated states of the nucleon. Finally, taking into account the neutron-proton mass difference, we use the fluctuations of the weak nuclear field in order to evaluate the weak coupling constant.

P. R. Silva

2001-12-10T23:59:59.000Z

216

Recent developments of the cascade-exciton model of nuclear reactions  

Science Conference Proceedings (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

217

Geochemical modeling of the nuclear-waste repository system. A status report  

Science Conference Proceedings (OSTI)

The primary objective of the geochemical modeling task is to develop an understanding of the waste-repository geochemical system and provide a valuable tool for estimating future states of that system. There currently exists a variety of computer codes which can be used in geochemical modeling studies. Some available codes contain the framework for simulating a natural chemical system and estimating, within limits, the response of that system to environmental changes. By data-base enhancement and code development, this modeling technique can be even more usefully applied to a nuclear-waste repository. In particular, thermodynamic data on elements not presently in the data base but identified as being of particular hazard in the waste-repository system, need to be incorporated into the code to estimate the near-field as well as the far-field reactions during a hypothetical breach. A reaction-path-simulation code, which estimates the products of specific rock/water reactions, has been tested using basalt and ground water. Results show that the mass-transfer capabilities of the code will be useful in chemical-evolution studies and scenario analyses. The purpose of this report is to explain the status of geochemical modeling as it currently applies to the chemical system of a hypothetical nuclear-waste repository in basalt and to present the plan proposed for further developmet and application.

Deutsch, W.J.

1980-12-01T23:59:59.000Z

218

Analytical free energy second derivatives with respect to nuclear coordinates: Complete formulation for electrostatic continuum solvation models  

Science Conference Proceedings (OSTI)

We present the theory and the implementation of analytical free energy second derivatives with respect to nuclear displacements for a molecular solute described within the framework of the polarizable continuum model. The formulation applies to a cavity with an accurately modeled molecular shape and it permits a complete consideration of all aspects of the solvation model. In particular

B. Mennucci; R. Cammi; J. Tomasi

1999-01-01T23:59:59.000Z

219

Security Science & Technology | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Security Treaty Verification Nuclear Systems Modeling, Simulation & Validation Nuclear Systems Technology Reactor Technology Nuclear Science Home | Science & Discovery |...

220

ORNL light-duty vehicles PC system  

Science Conference Proceedings (OSTI)

This data system, designed by the Oak Ridge National Laboratory (ORNL) and funded by the US Department of Energy (DOE), monitors information on every light-duty vehicle (automobiles and light-duty trucks) sold in the United States since model year 1976. The data are specified in two days. One way is on a model basis (i.e, engine and transmission combinations) and includes data on city, highway, and combined fuel economies; engine size; drive-train; fuel type (gasoline or diesel); interior volume; body type; and other vehicle attributes. The other way is on a make basis (e.g., Ford Escort, Oldsmobile 98) and includes data on sales; Environmental Protection Agency (EPA) size class; the sales-weighted fuel economy; sales-weighted interior volume; sales-weighted engine displacement (cid); curb weight; and other attributes. A unique identification number is assigned to a specific vehicle category. This identification number contains information on the manufacturer, the location of the manufacturer (domestic or import), and the sponsorship of the vehicle (domestic or import). Fuel economies, model year sales and various vehicle characteristics for every make of the 164 million light-duty vehicles sold in the US since model year 1976 can be obtained from this data system. 2 figs., 4 tabs.

Hu, P.S.; Patterson, P.D. (Oak Ridge National Lab., TN (USA))

1989-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear model pc" from the National Library of EnergyBeta (NLEBeta).
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221

Project: Modeling Relativistic Electrons from Nuclear Explosions in the Magnetosphere  

SciTech Connect

We present a summary of the FY12 activities for DTRA-funded project 'Modeling Relativistic Electrons from Nuclear Explosions in the Magnetosphere'. We briefly review the outstanding scientific questions and discuss the work done in the last year to try to answer these questions. We then discuss the agenda for this Technical Meeting with the DTRA sponsors. In the last year, we have continued our efforts to understand artificial radiation belts from several different perspectives: (1) Continued development of Electron Source Model (ESM) and comparison to HANE test data; (2) Continued studies of relativistic electron scattering by waves in the natural radiation belts; (3) Began study of self-generated waves from the HANE electrons; and (4) Began modeling for the UCLA laser experiment.

Cowee, Misa [Los Alamos National Laboratory; Gary, S. Peter [Los Alamos National Laboratory; Winske, Dan [Los Alamos National Laboratory; Liu, Kaijun [Los Alamos National Laboratory

2012-07-17T23:59:59.000Z

222

PC-based PCM telemetry data reduction system software  

SciTech Connect

The Solar Energy Research Institute's (SERI) Wind Research Program is using pulse code modulation (PCM) telemetry systems to study horizontal-axis wind turbines. SERI has developed a low-cost PC-based PCM data-acquisition system to facilitate quick PCM data analysis in the field. The SERI PC-PCM system consists of AT-compatible hardware boards for decoding and combining PCM data streams and DOS software for control and management of data acquisition. Up to four boards can be installed in a single PC, providing the capability to combine data from four PCM streams direct to disk or memory. This paper describes the SERI Quick-Look Data Management Program, which is a comprehensive software package used to organize, acquire, process, and display information from PCM data streams. The software was designed for use in conjunction with SERI's PC-PCM hardware described in a related paper. Features of the Quick-Look program are highlighted, including those which make it useful in an experiment test environment to quickly examine and verify incoming data. Also discussed are problems and techniques associated with PC-based PCM data acquisition, processing, and real-time display. 7 refs., 4 figs., 2 tabs.

Simms, D.A.

1990-02-01T23:59:59.000Z

223

2002 EIA Models Directory - Energy Information Administration  

U.S. Energy Information Administration (EIA)

LNFCC-PC computes an electric utility's levelized nuclear fuel cost. The code computes quantities of fuel-cycle services and levelized direct costs, ...

224

THERMODYNAMIC AND KINETIC MODELING OF ADVANCED NUCLEAR FUELS - FINAL LDRD-ER REPORT  

SciTech Connect

This project enhanced our theoretical capabilities geared towards establishing the basic science of a high-throughput protocol for the development of advanced nuclear fuel that should couple modern computational materials modeling and simulation tools, fabrication and characterization capabilities, and targeted high throughput performance testing experiments. The successful conclusion of this ER project allowed us to upgrade state-of-the-art modeling codes, and apply these modeling tools to ab initio energetics and thermodynamic assessments of phase diagrams of various mixtures of actinide alloys, propose a tool for optimizing composition of complex alloys for specific properties, predict diffusion behavior in diffusion couples made of actinide and transition metals, include one new equation in the LLNL phase-field AMPE code, and predict microstructure evolution during alloy coring. In FY11, despite limited funding, the team also initiated an experimental activity, with collaboration from Texas A&M University by preparing samples of nuclear fuels in bulk forms and for diffusion couple studies and metallic matrices, and performing preliminary characterization.

Turchi, P

2011-11-28T23:59:59.000Z

225

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

Science Conference Proceedings (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

226

Models for Type I X-Ray Bursts with Improved Nuclear Physics  

DOE Green Energy (OSTI)

Multi-zone models of Type I X-ray bursts are presented that use an adaptive nuclear reaction network of unprecedented size, up to 1300 isotopes, for energy generation and include the most recent measurements and estimates of critical nuclear physics. Convection and radiation transport are included in calculations that carefully follow the changing composition in the accreted layer, both during the bursts themselves and in their ashes. Sequences of bursts, up to 15 in one case, are followed for two choices of accretion rate and metallicity, up to the point where quasi-steady state is achieved. For M = 1.75 x 10{sup -9} M{sub {circle_dot}} yr{sup -1} (and M = 3.5 x 10{sup -10} M{sub {circle_dot}} yr{sup -1}, for low metallicity), combined hydrogen-helium flashes occur. These bursts have light curves with slow rise times (seconds) and long tails. The rise times, shapes, and tails of these light curves are sensitive to the efficiency of nuclear burning at various waiting points along the rp-process path and these sensitivities are explored. Each displays ''compositional inertia'' in that its properties are sensitive to the fact that accretion occurs onto the ashes of previous bursts which contain left-over hydrogen, helium and CNO nuclei.

Woosley, S E; Heger, A; Cumming, A; Hoffman, R D; Pruet, J; Rauscher, T; Schatz, H; Brown, B A; Wiescher, M; Fisker, J L

2004-02-02T23:59:59.000Z

227

High Level Requirements for the Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS)  

Science Conference Proceedings (OSTI)

The US Department of Energy, Office of Nuclear Energy (DOE-NE), has been tasked with the important mission of ensuring that nuclear energy remains a compelling and viable energy source in the U.S. The motivations behind this mission include cost-effectively meeting the expected increases in the power needs of the country, reducing carbon emissions and reducing dependence on foreign energy sources. In the near term, to ensure that nuclear power remains a key element of U.S. energy strategy and portfolio, the DOE-NE will be working with the nuclear industry to support safe and efficient operations of existing nuclear power plants. In the long term, to meet the increasing energy needs of the U.S., the DOE-NE will be investing in research and development (R&D) and working in concert with the nuclear industry to build and deploy new, safer and more efficient nuclear power plants. The safe and efficient operations of existing nuclear power plants and designing, licensing and deploying new reactor designs, however, will require focused R&D programs as well as the extensive use and leveraging of advanced modeling and simulation (M&S). M&S will play a key role in ensuring safe and efficient operations of existing and new nuclear reactors. The DOE-NE has been actively developing and promoting the use of advanced M&S in reactor design and analysis through its R&D programs, e.g., the Nuclear Energy Advanced Modeling and Simulation (NEAMS) and Consortium for Advanced Simulation of Light Water Reactors (CASL) programs. Also, nuclear reactor vendors are already using CFD and CSM, for design, analysis, and licensing. However, these M&S tools cannot be used with confidence for nuclear reactor applications unless accompanied and supported by verification and validation (V&V) and uncertainty quantification (UQ) processes and procedures which provide quantitative measures of uncertainty for specific applications. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation (NE-KAMS) is being developed at the Idaho National Laboratory in conjunction with Bettis Laboratory, Sandia National Laboratories, Argonne National Laboratory, Utah State University and others with the objective of establishing a comprehensive and web-accessible knowledge base that will provide technical services and resources for V&V and UQ of M&S in nuclear energy sciences and engineering. The knowledge base will serve as an important resource for technical exchange and collaboration that will enable credible and reliable computational models and simulations for application to nuclear reactor design, analysis and licensing. NE-KAMS will serve as a valuable resource for the nuclear industry, academia, the national laboratories, the U.S. Nuclear Regulatory Commission (NRC) and the public and will help ensure the safe, economical and reliable operation of existing and future nuclear reactors. From its inception, NE-KAMS will directly support nuclear energy research, development and demonstration programs within the U.S. Department of Energy (DOE), including the CASL, NEAMS, Light Water Reactor Sustainability (LWRS), Small Modular Reactors (SMR), and Next Generation Nuclear Power Plant (NGNP) programs. These programs all involve M&S of nuclear reactor systems, components and processes, and it is envisioned that NE-KAMS will help to coordinate and facilitate collaboration and sharing of resources and expertise for V&V and UQ across these programs.

Rich Johnson; Hyung Lee; Kimberlyn C. Mousseau

2011-09-01T23:59:59.000Z

228

Demonstration of a PC 25 Fuel Cell in Russia  

DOE Green Energy (OSTI)

This project involved the installation of a 200kW PC25C{trademark} phosphoric-acid fuel cell power plant at Orgenergogaz, a Gazprom industrial site in Russia. In April 1997, a PC25C{trademark} was sold by ONSI Corporation to Orgenergogaz, a subsidiary of the Russian company ''Gazprom''. Due to instabilities in the Russian financial markets, at that time, the unit was never installed and started by Orgenergogaz. In October of 2001 International Fuel Cells (IFC), now known as UTC Fuel Cells (UTCFC), received a financial assistance award from the United States Department of Energy (DOE) entitled ''Demonstration of PC 25 Fuel Cell in Russia''. Three major tasks were part of this award: the inspection of the proposed site and system, start-up assistance, and installation and operation of the powerplant.

John C. Trocciola; Thomas N. Pompa; Linda S. Boyd

2004-09-01T23:59:59.000Z

229

Dynamic Modeling, Sensor Placement Design, and Fault Diagnosis of Nuclear Desalination Systems.  

E-Print Network (OSTI)

??Fault diagnosis of sensors, devices, and equipment is an important topic in the nuclear industry for effective and continuous operation of nuclear power plants. All… (more)

Li, Fan

2011-01-01T23:59:59.000Z

230

Health effects models for nuclear power plant accident consequence analysis: Low LET radiation  

SciTech Connect

This report describes dose-response models intended to be used in estimating the radiological health effects of nuclear power plant accidents. Models of early and continuing effects, cancers and thyroid nodules, and genetic effects are provided. Weibull dose-response functions are recommended for evaluating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary, and gastrointestinal syndromes -- are considered. In addition, models are included for assessing the risks of several nonlethal early and continuing effects -- including prodromal vomiting and diarrhea, hypothyroidism and radiation thyroiditis, skin burns, reproductive effects, and pregnancy losses. Linear and linear-quadratic models are recommended for estimating cancer risks. Parameters are given for analyzing the risks of seven types of cancer in adults -- leukemia, bone, lung, breast, gastrointestinal, thyroid, and other.'' The category, other'' cancers, is intended to reflect the combined risks of multiple myeloma, lymphoma, and cancers of the bladder, kidney, brain, ovary, uterus and cervix. Models of childhood cancers due to in utero exposure are also developed. For most cancers, both incidence and mortality are addressed. The models of cancer risk are derived largely from information summarized in BEIR III -- with some adjustment to reflect more recent studies. 64 refs., 18 figs., 46 tabs.

Evans, J.S. (Harvard Univ., Boston, MA (USA). School of Public Health)

1990-01-01T23:59:59.000Z

231

Nuclear Energy  

Nuclear Energy Environmental Mgmt. Study Objectives: Respond to the pressing need to refine existing corrosion models: Predict performance in wide range of environments

232

began at the PC4 facility, which is located  

NLE Websites -- All DOE Office Websites (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

233

METHANE de-NOX for Utility PC Boilers  

SciTech Connect

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

234

A Code for Analyzing Coolant and Offgas Activity in a Light Water Nuclear Reactor: Computer Manual  

Science Conference Proceedings (OSTI)

The CHIRON code meets the nuclear industry's need for a model that can estimate the number of failed fuel rods in the nuclear reactor cores of operating BWRs and PWRs. This PC-based tool -- now available in WINDOWS format -- provides this estimate by using coolant and/or offgas activity measurements. The WINDOWS version adds significant flexibility in terms of database capabilities and the code's use as a general activity release management tool. This user's manual provides a complete tutorial on the ins...

1998-06-19T23:59:59.000Z

235

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign  

SciTech Connect

Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in the nuclear industry as cladding materials for light water reactor (LWR) fuels. These materials display a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation, especially in the case of Zircaloy-4. However, over the last couple of years, in the post-Fukushima Daiichi world, energetic efforts have been undertaken to improve fuel clad oxidation resistance during off-normal temperature excursions. Efforts have also been made to improve upon the already achieved levels of mechanical behavior and reduce hydrogen uptake. In order to facilitate the development of such novel materials, it is very important to achieve not only engineering control, but also a scientific understanding of the underlying material degradation mechanisms, both in working conditions and in storage of used nuclear fuel. This report strives to contribute to these efforts by constructing the thermodynamic models of both alloys; constructing of the respective phase diagrams, and oxidation mechanisms. A special emphasis was placed upon the role of zirconium suboxides in hydrogen uptake reduction and the atomic mechanisms of oxidation. To that end, computational thermodynamics calculations were conducted concurrently with first-principles atomistic modeling.

Michael V. Glazoff

2013-08-01T23:59:59.000Z

236

Hadron structure in a simple model of quark/nuclear matter  

SciTech Connect

We study a simple model for one-dimensional hadron matter with many of the essential features needed for examining the transition from nuclear to quark matter and the limitations of models based upon hadron rather than quark degrees of freedom. The dynamics are generated entirely by the quark confining force and exchange symmetry. Using Monte Carlo techniques, the ground-state energy, single-quark momentum distribution, and quark correlation function are calculated for uniform matter as a function of density. The quark confinement scale in the medium increases substantially with increasing density. This change is evident in the correlation function and momentum distribution, in qualitative agreement with the changes observed in deep-inelastic lepton scattering. Nevertheless, the ground-state energy is smooth throughout the transition to quark matter and is described remarkably well by an effective hadron theory based on a phenomenological hadron-hadron potential.

Horowitz, C.J.; Moniz, E.J.; Negele, J.W.

1985-04-01T23:59:59.000Z

237

Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI  

Science Conference Proceedings (OSTI)

As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Station’s Independent Spent Fuel Storage Installation (ISFSI). Detailed thermal models models were developed to obtain realistic temperature predictions for actual storage systems, in contrast to conservative and bounding design basis calculations.

Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.; Cuta, Judith M.; Collins, Brian A.; Siciliano, Edward R.

2012-10-01T23:59:59.000Z

238

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

SciTech Connect

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

239

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

DOE Green Energy (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

240

Validation and Calibration of Nuclear Thermal Hydraulics Multiscale Multiphysics Models - Subcooled Flow Boiling Study  

SciTech Connect

In addition to validation data plan, development of advanced techniques for calibration and validation of complex multiscale, multiphysics nuclear reactor simulation codes are a main objective of the CASL VUQ plan. Advanced modeling of LWR systems normally involves a range of physico-chemical models describing multiple interacting phenomena, such as thermal hydraulics, reactor physics, coolant chemistry, etc., which occur over a wide range of spatial and temporal scales. To a large extent, the accuracy of (and uncertainty in) overall model predictions is determined by the correctness of various sub-models, which are not conservation-laws based, but empirically derived from measurement data. Such sub-models normally require extensive calibration before the models can be applied to analysis of real reactor problems. This work demonstrates a case study of calibration of a common model of subcooled flow boiling, which is an important multiscale, multiphysics phenomenon in LWR thermal hydraulics. The calibration process is based on a new strategy of model-data integration, in which, all sub-models are simultaneously analyzed and calibrated using multiple sets of data of different types. Specifically, both data on large-scale distributions of void fraction and fluid temperature and data on small-scale physics of wall evaporation were simultaneously used in this work’s calibration. In a departure from traditional (or common-sense) practice of tuning/calibrating complex models, a modern calibration technique based on statistical modeling and Bayesian inference was employed, which allowed simultaneous calibration of multiple sub-models (and related parameters) using different datasets. Quality of data (relevancy, scalability, and uncertainty) could be taken into consideration in the calibration process. This work presents a step forward in the development and realization of the “CIPS Validation Data Plan” at the Consortium for Advanced Simulation of LWRs to enable quantitative assessment of the CASL modeling of Crud-Induced Power Shift (CIPS) phenomenon, in particular, and the CASL advanced predictive capabilities, in general. This report is prepared for the Department of Energy’s Consortium for Advanced Simulation of LWRs program’s VUQ Focus Area.

Anh Bui; Nam Dinh; Brian Williams

2013-09-01T23:59:59.000Z

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.
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241

Build Your Own Pentium III PC, 1st edition  

Science Conference Proceedings (OSTI)

From the Publisher:Build your own Pentium III PC and save a bundle!Why pay big bucks for a Pentium III system when legendary build-it-yourself guru Aubrey Pilgrim can help you construct one at home for a fraction of dealer prices? In Build Your Own Pentium ...

Aubrey Pilgrim

1999-10-01T23:59:59.000Z

242

Reactor Technology | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

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

243

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

Science Conference Proceedings (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

244

Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System  

SciTech Connect

Indoor air quality effects on human health are of increasing concern to public health agencies and building owners. The prevention and treatment of 'sick building' syndrome and the spread of air-borne diseases in hospitals, for example, are well known priorities. However, increasing attention is being directed to the vulnerability of our public buildings/places, public security and national defense facilities to terrorist attack or the accidental release of air-borne biological pathogens, harmful chemicals, or radioactive contaminants. The Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System (IA-NBC-HMAS) was developed to serve as a health impact analysis tool for use in addressing these concerns. The overall goal was to develop a user-friendly fully functional prototype Health Modeling and Assessment system, which will operate under the PNNL FRAMES system for ease of use and to maximize its integration with other modeling and assessment capabilities accessible within the FRAMES system (e.g., ambient air fate and transport models, water borne fate and transport models, Physiologically Based Pharmacokinetic models, etc.). The prototype IA-NBC-HMAS is designed to serve as a functional Health Modeling and Assessment system that can be easily tailored to meet specific building analysis needs of a customer. The prototype system was developed and tested using an actual building (i.e., the Churchville Building located at the Aberdeen Proving Ground) and release scenario (i.e., the release and measurement of tracer materials within the building) to ensure realism and practicality in the design and development of the prototype system. A user-friendly "demo" accompanies this report to allow the reader the opportunity for a "hands on" review of the prototype system's capability.

Stenner, Robert D.; Hadley, Donald L.; Armstrong, Peter R.; Buck, John W.; Hoopes, Bonnie L.; Janus, Michael C.

2001-03-01T23:59:59.000Z

245

Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System  

SciTech Connect

Indoor air quality effects on human health are of increasing concern to public health agencies and building owners. The prevention and treatment of 'sick building' syndrome and the spread of air-borne diseases in hospitals, for example, are well known priorities. However, increasing attention is being directed to the vulnerability of our public buildings/places, public security and national defense facilities to terrorist attack or the accidental release of air-borne biological pathogens, harmful chemicals, or radioactive contaminants. The Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System (IA-NBC-HMAS) was developed to serve as a health impact analysis tool for use in addressing these concerns. The overall goal was to develop a user-friendly fully functional prototype Health Modeling and Assessment system, which will operate under the PNNL FRAMES system for ease of use and to maximize its integration with other modeling and assessment capabilities accessible within the FRAMES system (e.g., ambient air fate and transport models, water borne fate and transport models, Physiologically Based Pharmacokinetic models, etc.). The prototype IA-NBC-HMAS is designed to serve as a functional Health Modeling and Assessment system that can be easily tailored to meet specific building analysis needs of a customer. The prototype system was developed and tested using an actual building (i.e., the Churchville Building located at the Aberdeen Proving Ground) and release scenario (i.e., the release and measurement of tracer materials within the building) to ensure realism and practicality in the design and development of the prototype system. A user-friendly "demo" accompanies this report to allow the reader the opportunity for a "hands on" review of the prototype system's capability.

Stenner, Robert D.; Hadley, Donald L.; Armstrong, Peter R.; Buck, John W.; Hoopes, Bonnie L.; Janus, Michael C.

2001-03-01T23:59:59.000Z

246

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

SciTech Connect

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube`s inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

Palmrose, D.E.; Herring, J.S.

1993-05-01T23:59:59.000Z

247

The influence of material models on chemical or nuclear-explosion source functions  

SciTech Connect

Physical models of explosion sources are needed to explain the variations in the performance of existing discriminants in different regions, and to help develop more robust methods for identifying underground explosions. In this paper, we assess the sensitivity of explosion source functions to material properties by means of numerical simulations. Specifically, we have calculated the effect of varying the yield strength, overburden pressure, and gas porosity on the spectra of the reduced velocity potential for both nuclear and chemical explosions, and compared these with experimental results derived from free-field particle acceleration and regional seismic (LNN) data. The chemical-explosion calculations were intended to simulate the kiloton experiment recently conducted in Area 12 of the Nevada Test Site (NTS) that has been dubbed the Non-Proliferation Experiment (NPE). We found that the asymptotic (long period) value of the reduced displacement potential, {phi}{infinity}, for explosions with the ANFO blasting agent used in the NPE, was larger than that derived for a tamped nuclear explosion of the same yield by a factor of 1.9, in good agreement with the experimental results derived from free-field particle velocity measurements, and also with m{sub b}(P{sub n}) data from the Livermore Nevada Network (LNN).

Glenn, L.A.; Goldstein, P.

1994-04-01T23:59:59.000Z

248

The Nuclear-Matter Response in the Quark String-flip Model  

E-Print Network (OSTI)

Nuclear matter is modeled directly in terms of its constituent quarks. A many-body string-flip potential is used that confines quarks within hadrons, enables the hadrons to separate without generating van der Waals forces, and is symmetric in all quark coordinates. We present variational Monte Carlo results for the ground-state properties of large, three-dimensional systems. A phase transition from nuclear to quark matter is observed which is characterized by a dramatic rearrangement of strings. We report on exact calculations of the dynamic response of many-quark systems in one spatial dimension. At low density and small momentum transfers the response is substantially larger than that of a free Fermi gas of quarks; this suggests that there is a coherent response from all the quarks inside the hadron. This coherence, however, is incomplete, as the response is suppressed relative to that of a free Fermi gas of nucleons due to the internal quark substructure of the hadron.

Jorge Piekarewicz

1996-09-16T23:59:59.000Z

249

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

Science Conference Proceedings (OSTI)

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube's inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

Palmrose, D.E.; Herring, J.S.

1993-01-01T23:59:59.000Z

250

A Latent Source Model to Detect Multiple Spatial Clusters with Application in a Mobile Sensor Network for Surveillance of Nuclear Materials  

E-Print Network (OSTI)

to have sophisticated nuclear surveillance and detection systems deployed in major cities in the U and models to provide consistent and pervasive surveillance of nuclear materials in major cities. The network Network for Surveillance of Nuclear Materials Jerry Cheng, Minge Xie, Rong Chen and Fred Roberts 1

Xie, Minge

251

METHANE de-NOX for Utility PC Boilers  

SciTech Connect

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

252

The Nuclear Energy Advanced Modeling and Simulation Enabling Computational Technologies FY09 Report  

SciTech Connect

In this document we report on the status of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Enabling Computational Technologies (ECT) effort. In particular, we provide the context for ECT In the broader NEAMS program and describe the three pillars of the ECT effort, namely, (1) tools and libraries, (2) software quality assurance, and (3) computational facility (computers, storage, etc) needs. We report on our FY09 deliverables to determine the needs of the integrated performance and safety codes (IPSCs) in these three areas and lay out the general plan for software quality assurance to meet the requirements of DOE and the DOE Advanced Fuel Cycle Initiative (AFCI). We conclude with a brief description of our interactions with the Idaho National Laboratory computer center to determine what is needed to expand their role as a NEAMS user facility.

Diachin, L F; Garaizar, F X; Henson, V E; Pope, G

2009-10-12T23:59:59.000Z

253

Models for Relativistic Coulomb Sum Rules:Expansions in Moments of the Nuclear Momentum Density  

SciTech Connect

Relativistic Coulomb sum rules for quasielastic electron scattering from nuclei are developed using a class of relativistic models for the nuclear ground-state momentum distribution. Approximate sum rules at constant 3- or 4-momentum transfer are expressed as expansions in moments of the momentum distribution. New sum-rule functions are derived which, even for very large values of energy and momentum where relativistic effects become dominant, approach simple asymptotic values; in doing so they approximately retain the flavor of the nonrelativistic Coulomb sum rule which approaches Z. Specific ways of achieving an optimum separation of effects relating to the electromagnetic response of a single nucleon and of a many-body system of structureless particles are discussed, including a study of sensitivities to alternative parameterizations of GEn. Comparisons of results using different momentum distributions for the case of 16O are presented.

Donnelly, T. W.; Kronenberg, E. L.; van Orden, J. W.

1989-04-01T23:59:59.000Z

254

Long-Term Planning for Nuclear Energy Systems Under Deep Uncertainty  

E-Print Network (OSTI)

model . . . . . . . . . . . . . . . . . . . . . Nuclear fuelU.S. spent nuclear fuel2 The Nuclear Fuel Cycle

Kim, Lance Kyungwoo

2011-01-01T23:59:59.000Z

255

Ab Initio Enhanced calphad Modeling of Actinide-Rich Nuclear Fuels  

Science Conference Proceedings (OSTI)

The process of fuel recycling is central to the Advanced Fuel Cycle Initiative (AFCI), where plutonium and the minor actinides (MA) Am, Np, and Cm are extracted from spent fuel and fabricated into new fuel for a fast reactor. Metallic alloys of U-Pu-Zr-MA are leading candidates for fast reactor fuels and are the current basis for fast spectrum metal fuels in a fully recycled closed fuel cycle. Safe and optimal use of these fuels will require knowledge of their multicomponent phase stability and thermodynamics (Gibbs free energies). In additional to their use as nuclear fuels, U-Pu-Zr-MA contain elements and alloy phases that pose fundamental questions about electronic structure and energetics at the forefront of modern many-body electron theory. This project will validate state-of-the-art electronic structure approaches for these alloys and use the resulting energetics to model U-Pu-Zr-MA phase stability. In order to keep the work scope practical, researchers will focus on only U-Pu-Zr-{Np,Am}, leaving Cm for later study. The overall objectives of this project are to: ? Provide a thermodynamic model for U-Pu-Zr-MA for improving and controlling reactor fuels. ? Develop and validate an ab initio approach for predicting actinide alloy energetics for thermodynamic modeling.

Morgan, Dane; Yang, Yong

2013-10-28T23:59:59.000Z

256

Microscopic models and effective equation of state in nuclear collisions at FAIR energies  

E-Print Network (OSTI)

Two microscopic models, UrQMD and QGSM, were employed to study the formation of locally equilibrated hot and dense nuclear matter in heavy-ion collisions at energies from 11.6 AGeV to 160 AGeV. Analysis was performed for the fixed central cubic cell of volume V = 125 fm**3 and for the expanding cell which followed the growth of the central area with uniformly distributed energy. To decide whether or not the equilibrium was reached, results of the microscopic calculations were compared to that of the statistical thermal model. Both dynamical models indicate that the state of kinetic, thermal and chemical equilibrium is nearly approached at any bombarding energy after a certain relaxation period. The higher the energy, the shorter the relaxation time. Equation of state has a simple linear dependence P = a(sqrt{s})*e, where a = c_s**2 is the sound velocity squared. It varies from 0.12 \\pm 0.01 at E_{lab} = 11.6 AGeV to 0.145 \\pm 0.005 at E_{lab} = 160 AGeV. Change of the slope in a(sqrt{s}) behavior occurs at E_...

Bravina, L; Bleibel, J; Bleicher, M; Burau, G; Faessler, Amand; Fuchs, C; Nilsson, M S; Stöcker, H; Tywoniuk, K; Zabrodin, E

2008-01-01T23:59:59.000Z

257

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

258

Relativistic scalar-vector models of the N-N and N-nuclear interactions  

SciTech Connect

This paper for the Proceedings of Conference an Anti-Nucleon and Nucleon-Nucleus Interactions summarizes work by the principal investigator and his collaborators on the nucleon-nucleon (N-N) and nucleon-nuclear (N-eta) interactions. It draws heavily on a paper presented at the Many Body Conference in Rome in 1972 but also includes a brief review of our phenomenological N-eta interaction studies. We first summarize our 48-49 generalized scalar-vector meson field theory model of the N-N interactions. This is followed by a brief description of our phenomenological work in the 50's on the N-eta interaction sponsored by the Atomic Energy Commission (the present DOE). This work finally led to strong velocity dependent potentials with spin orbit and isospin terms for shell and optical model applications. This is followed by a section on the Emergence of One-Boson Exchange Models describing developments in the 60's of quantitative generalized one boson exchange potentials (GOBEP) including our purely relativistic N-N analyses. Then follows a section on the application of this meson field model to the N-eta interaction, in particular to spherical closed shell nuclei. This work was sponsored by AFOSR but funding was halted with the Mansfield amendment. We conclude with a discussion of subsequent collateral work by former colleagues and by others who have converged upon scalar-vector relativistic models of N-N, antiN-N, N-eta and antiN-eta interactions and some lessons learned from this extended endeavor. 61 refs.

Green, A.E.S.

1985-01-01T23:59:59.000Z

259

Health effects model for nuclear power plant accident consequence analysis. Part I. Introduction, integration, and summary. Part II. Scientific basis for health effects models  

Science Conference Proceedings (OSTI)

Analysis of the radiological health effects of nuclear power plant accidents requires models for predicting early health effects, cancers and benign thyroid nodules, and genetic effects. Since the publication of the Reactor Safety Study, additional information on radiological health effects has become available. This report summarizes the efforts of a program designed to provide revised health effects models for nuclear power plant accident consequence modeling. The new models for early effects address four causes of mortality and nine categories of morbidity. The models for early effects are based upon two parameter Weibull functions. They permit evaluation of the influence of dose protraction and address the issue of variation in radiosensitivity among the population. The piecewise-linear dose-response models used in the Reactor Safety Study to predict cancers and thyroid nodules have been replaced by linear and linear-quadratic models. The new models reflect the most recently reported results of the follow-up of the survivors of the bombings of Hiroshima and Nagasaki and permit analysis of both morbidity and mortality. The new models for genetic effects allow prediction of genetic risks in each of the first five generations after an accident and include information on the relative severity of various classes of genetic effects. The uncertainty in modeloling radiological health risks is addressed by providing central, upper, and lower estimates of risks. An approach is outlined for summarizing the health consequences of nuclear power plant accidents. 298 refs., 9 figs., 49 tabs.

Evans, J.S.; Moeller, D.W.; Cooper, D.W.

1985-07-01T23:59:59.000Z

260

Application of a Hybrid Potts-Phase Field Model to Nuclear Materials  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, Materials Science & Technology 2012. Symposium, Materials Development for Nuclear Applications and Extreme Environments.

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

Nuclear Data Program - Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (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

262

Modeling Solute Thermokinetics in LiCI-KCI Molten Salt for Nuclear Waste Separation  

SciTech Connect

Recovery of actinides is an integral part of a closed nuclear fuel cycle. Pyrometallurgical nuclear fuel recycling processes have been developed in the past for recovering actinides from spent metallic and nitride fuels. The process is essentially to dissolve the spent fuel in a molten salt and then extract just the actinides for reuse in a reactor. Extraction is typically done through electrorefining, which involves electrochemical reduction of the dissolved actinides and plating onto a cathode. Knowledge of a number of basic thermokinetic properties of salts and salt-fuel mixtures is necessary for optimizing present and developing new approaches for pyrometallurgical waste processing. The properties of salt-fuel mixtures are presently being studied, but there are so many solutes and varying concentrations that direct experimental investigation is prohibitively time consuming and expensive (particularly for radioactive elements like Pu). Therefore, there is a need to reduce the number of required experiments through modeling of salt and salt-fuel mixture properties. This project will develop first-principles-based molecular modeling and simulation approaches to predict fundamental thermokinetic properties of dissolved actinides and fission products in molten salts. The focus of the proposed work is on property changes with higher concentrations (up to 5 mol%) of dissolved fuel components, where there is still very limited experimental data. The properties predicted with the modeling will be density, which is used to assess the amount of dissolved material in the salt; diffusion coefficients, which can control rates of material transport during separation; and solute activity, which determines total solubility and reduction potentials used during electrorefining. The work will focus on La, Sr, and U, which are chosen to include the important distinct categories of lanthanides, alkali earths, and actinides, respectively. Studies will be performed using LiCl-KCl salt at the eutectic composition (58 mol% LiCl, 42 mol% KCl), which is used for treating spent EBR-II fuel. The same process being used for EBRII fuel is currently being studied for widespread international implementation. The methods will focus on first-principles and first- principles derived interatomic potential based simulations, primarily using molecular dynamics. Results will be validated against existing literature and parallel ongoing experimental efforts. The simulation results will be of value for interpreting experimental results, validating analytical models, and for optimizing waste separation by potentially developing new salt configurations and operating conditions.

Morgan, Dane; Eapen, Jacob

2013-10-01T23:59:59.000Z

263

Building Energy Software Tools Directory: Tools by Platform - PC  

NLE Websites -- All DOE Office Websites (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

264

METHANE de-NOX for Utility PC Boilers  

SciTech Connect

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

265

Evaluation of PC-Based Eddy Current Database Management Program  

Science Conference Proceedings (OSTI)

Part of the Balance-of-Plant (BOP) Heat Exchanger Condition Assessment Program for 1998 was an evaluation of commercially available PC-based eddy current database management software programs. The objective of the study was to evaluate the selected software programs for general user-friendliness, ease of tubesheet creation, inspection planning, query building and execution, printing options, import and export capabilities, documentation, network features, technical support, and product cost. Three (3) so...

1998-12-18T23:59:59.000Z

266

ELSEVIER Journal of Nuclear Materials 244 (1997) 85-100 RACLETTE: a model for evaluating the thermal response of plasma  

E-Print Network (OSTI)

ELSEVIER Journal of Nuclear Materials 244 (1997) 85-100 RACLETTE: a model for evaluating the thermal response of plasma facing components to slow high power plasma transients. Part I: Theory, in the current engineering design phase of the International Ther- monuclear Experimental Reactor (ITER

Raffray, A. René

267

Modeling Hydrogen-Induced Cracking of Titanium Alloys in Nuclear Waste Repository Environments  

DOE Green Energy (OSTI)

This paper reviews the current understanding of hydrogen-induced cracking (HIC) of Ti Grade 7 and other relevant titanium alloys within the context of the current waste package design for the repository environmental conditions anticipated within the Yucca Mountain repository. The review concentrates on corrosion processes possible in the aqueous environments expected within this site. A brief background discussion of the relevant properties of titanium alloys, the hydrogen absorption process, and the properties of passive film on titanium alloys is presented as the basis for the subsequent discussion of model developments. The key corrosion processes that could occur are addressed individually. Subsequently, the expected corrosion performance of these alloys under the specific environmental conditions anticipated at Yucca Mountain is considered. It can be concluded that, based on the conservative modeling approaches adopted, hydrogen-induced cracking of titanium alloys will not occur under nuclear waste repository conditions since there will not be sufficient hydrogen in the alloy after 10,000 years of emplacement.

F. Hua; K. Mon; P. Pasupathi; G. Gordon

2004-09-08T23:59:59.000Z

268

Caloric curve for nuclear liquid-gas phase transition in relativistic mean-field hadronic model  

E-Print Network (OSTI)

The main thermodynamical properties of the first order phase transition of the relativistic mean-field (RMF) hadronic model were explored in the isobaric, the canonical and the grand canonical ensembles on the basis of the method of the thermodynamical potentials and their first derivatives. It was proved that the first order phase transition of the RMF model is the liquid-gas type one associated with the Gibbs free energy $G$. The thermodynamical potential $G$ is the piecewise smooth function and its first order partial derivatives with respect to variables of state are the piecewise continuous functions. We have found that the energy in the caloric curve is discontinuous in the isobaric and the grand canonical ensembles at fixed values of the pressure and the chemical potential, respectively, and it is continuous, i.e. it has no plateau, in the canonical and microcanonical ensembles at fixed values of baryon density, while the baryon density in the isotherms is discontinuous in the isobaric and the canonical ensembles at fixed values of the temperature. The general criterion for the nuclear liquid-gas phase transition in the canonical ensemble was identified.

A. S. Parvan

2011-11-26T23:59:59.000Z

269

Dynamic modeling efforts for system interface studies for nuclear hydrogen production.  

DOE Green Energy (OSTI)

System interface studies require not only identifying economically optimal equipment configurations, which involves studying mainly full power steady-state operation, but also assessing the operability of a design during load change and startup and assessing safety-related behavior during upset conditions. This latter task is performed with a dynamic simulation code. This report reviews the requirements of such a code. It considers the types of transients that will need to be simulated, the phenomena that will be present, the models best suited for representing the phenomena, and the type of numerical solution scheme for solving the models to obtain the dynamic response of the combined nuclear-hydrogen plant. Useful insight into plant transient behavior prior to running a dynamics code is obtained by some simple methods that take into account component time constants and energy capacitances. Methods for determining reactor stability, plant startup time, and temperature response during load change, and tripping of the reactor are described. Some preliminary results are presented.

Vilim, R. B.; Nuclear Engineering Division

2007-08-15T23:59:59.000Z

270

Khalil named co-director of the Center for Advanced Nuclear Fuel...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

271

Experimental Resources for Nuclear Data Studies in the U.S. ...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

272

Peters and Fanning appear on NBC-5 report on Illinois nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

273

Liquid-gas phase transition in a two-components isospin lattice gas model for asymmetric nuclear matter  

E-Print Network (OSTI)

A two-components isospin lattice gas model has been employed to study the liquid-gas phase transition for asymmetric nuclear matter. An additional degree of freedom, namely, the asymmetry parameter alpha has been considered carefully for studying the phase transition. We have shown that under the mean field approximation, the liquid-gas phase transition given by this model is of second order. The entropy continues at the phase transition point. The binodal surface is addressed.

Wei Liang Qian; Ru-Keng Su

2002-10-04T23:59:59.000Z

274

Microscopic models and effective equation of state in nuclear collisions at FAIR energies  

E-Print Network (OSTI)

Two microscopic models, UrQMD and QGSM, were employed to study the formation of locally equilibrated hot and dense nuclear matter in heavy-ion collisions at energies from 11.6 AGeV to 160 AGeV. Analysis was performed for the fixed central cubic cell of volume V = 125 fm**3 and for the expanding cell which followed the growth of the central area with uniformly distributed energy. To decide whether or not the equilibrium was reached, results of the microscopic calculations were compared to that of the statistical thermal model. Both dynamical models indicate that the state of kinetic, thermal and chemical equilibrium is nearly approached at any bombarding energy after a certain relaxation period. The higher the energy, the shorter the relaxation time. Equation of state has a simple linear dependence P = a(sqrt{s})*e, where a = c_s**2 is the sound velocity squared. It varies from 0.12 \\pm 0.01 at E_{lab} = 11.6 AGeV to 0.145 \\pm 0.005 at E_{lab} = 160 AGeV. Change of the slope in a(sqrt{s}) behavior occurs at E_{lab} = 40 AGeV and can be assigned to the transition from baryon-rich to meson-dominated matter. The phase diagrams in the T - mu_B plane show the presence of kinks along the lines of constant entropy per baryon. These kinks are linked to the inelastic (i.e. chemical) freeze-out in the system.

L. Bravina; I. Arsene; J. Bleibel; M. Bleicher; G. Burau; Amand Faessler; C. Fuchs; M. S. Nilsson; H. Stoecker; K. Tywoniuk; E. Zabrodin

2008-04-09T23:59:59.000Z

275

Bayesian Analysis for the Site-Specific Dose Modeling in Nuclear Power Plant Decommissioning.  

E-Print Network (OSTI)

??Decommissioning is the process of closing down a facility. In nuclear power plant decommissioning, it must be determined that that any remaining radioactivity at a… (more)

Ling, Xianbing

2001-01-01T23:59:59.000Z

276

[en] THERMOHIDRAULIC MODEL FOR A TYPICAL STEAM GENERATOR OF PWR NUCLEAR POWER PLANTS.  

E-Print Network (OSTI)

??[pt] Muitas centrais nucleares do tipo PWR utilizam vapor produzido em geradores de vapor do tipo tubos em U invertido, com recirculação interna natural, nos… (more)

CARLOS VALOIS MACIEL BRAGA

2011-01-01T23:59:59.000Z

277

PC and monitor night status: Power management enabling and manual turn-off  

SciTech Connect

While office equipment accounts for about 7 percent of commercial building energy use, this reflects considerable energy savings from the use of automatic power management. Most of these savings were gained through the use of low-power modes that meet the criteria of the U.S. EPA's Energy Star program. Despite this success, there are large amounts of additional savings that could be gained if all equipment capable of power management use were enabled and functioning. A considerable portion of equipment is not enabled for power management at all, enabled only partially, or is enabled but prevented from functioning. Additional savings could be gained if more equipment were turned off at night manually. We compiled results from 17 studies from the office equipment literature addressing PCs and monitors. Some factors important for annual energy use, such as power levels, have been documented elsewhere and are not covered. We review methods for estimating office equipment use patterns and energy use, and present findings on night status--power management and manual turn-off rates. In early studies, PC power management was often found to function in 25 percent or less of the Energy Star compliant units (10 percent of all PCs). However, recent assessments have found higher rates, and we estimate that for Energy Star models, 35 percent of PC CPUs and 65 percent of PC monitors are enabled for power management. While the data lack statistical rigor, they can be used to estimate the magnitude of current and potential power management savings, which we did for major types of office equipment. The data also make clear that the topic of enabling rates, and the factors which influence them, deserve greater scrutiny.

Nordman, Bruce; Meier, Alan; Piette, Mary Ann

1998-07-30T23:59:59.000Z

278

Liquid-gas phase transition in hot asymmetric nuclear matter with density-dependent relativistic mean-field models  

E-Print Network (OSTI)

The liquid-gas phase transition in hot asymmetric nuclear matter is studied within density-dependent relativistic mean-field models where the density dependence is introduced according to the Brown-Rho scaling and constrained by available data at low densities and empirical properties of nuclear matter. The critical temperature of the liquid-gas phase transition is obtained to be 15.7 MeV in symmetric nuclear matter falling on the lower edge of the small experimental error bars. In hot asymmetric matter, the boundary of the phase-coexistence region is found to be sensitive to the density dependence of the symmetry energy. The critical pressure and the area of phase-coexistence region increases clearly with the softening of the symmetry energy. The critical temperature of hot asymmetric matter separating the gas phase from the LG coexistence phase is found to be higher for the softer symmetry energy.

Guang-Hua Zhang; Wei-Zhou Jiang

2012-03-17T23:59:59.000Z

279

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

Science Conference Proceedings (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

280

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

Science Conference Proceedings (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

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281

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

Science Conference Proceedings (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

282

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

NLE Websites -- All DOE Office Websites (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

283

Use of Modeling for Prevention of Solids Formation During Canyon Processing of Legacy Nuclear Materials at the Savannah River Site  

Science Conference Proceedings (OSTI)

The Savannah River Site (SRS) Environmental Management (EM) nuclear material stabilization program includes the dissolution and processing of legacy materials from various DOE sites. The SRS canyon facilities were designed to dissolve and process spent nuclear fuel and targets. As the processing of typical materials is completed, unusual and exotic nuclear materials are being targeted for stabilization. These unusual materials are often difficult to dissolve using historical flowsheet conditions and require more aggressive dissolver solutions. Solids must be prevented in the dissolver to avoid expensive delays associated with the build-up of insoluble material in downstream process equipment. Moreover, it is vital to prevent precipitation of all solids, especially plutonium-bearing solids, since their presence in dissolver solutions raises criticality safety issues. To prevent precipitation of undesirable solids in aqueous process solutions, the accuracy of computer models to predict precipitate formation requires incorporation of plant specific fundamental data. These data are incorporated into a previously developed thermodynamic computer program that applies the Pitzer correlation to derive activity coefficient parameters. This improved predictive model will reduce unwanted precipitation in process solutions at DOE sites working with EM nuclear materials in aqueous solutions.

Rhodes, W. D.; Crooks III, W. J.; Christian, J. D.

2002-02-26T23:59:59.000Z

284

TOWARD END-TO-END MODELING FOR NUCLEAR EXPLOSION MONITORING: SIMULATION OF UNDERGROUND NUCLEAR EXPLOSIONS AND EARTHQUAKES USING HYDRODYNAMIC AND ANELASTIC SIMULATIONS, HIGH-PERFORMANCE COMPUTING AND THREE-DIMENSIONAL EARTH MODELS  

Science Conference Proceedings (OSTI)

This paper describes new research being performed to improve understanding of seismic waves generated by underground nuclear explosions (UNE) by using full waveform simulation, high-performance computing and three-dimensional (3D) earth models. The goal of this effort is to develop an end-to-end modeling capability to cover the range of wave propagation required for nuclear explosion monitoring (NEM) from the buried nuclear device to the seismic sensor. The goal of this work is to improve understanding of the physical basis and prediction capabilities of seismic observables for NEM including source and path-propagation effects. We are pursuing research along three main thrusts. Firstly, we are modeling the non-linear hydrodynamic response of geologic materials to underground explosions in order to better understand how source emplacement conditions impact the seismic waves that emerge from the source region and are ultimately observed hundreds or thousands of kilometers away. Empirical evidence shows that the amplitudes and frequency content of seismic waves at all distances are strongly impacted by the physical properties of the source region (e.g. density, strength, porosity). To model the near-source shock-wave motions of an UNE, we use GEODYN, an Eulerian Godunov (finite volume) code incorporating thermodynamically consistent non-linear constitutive relations, including cavity formation, yielding, porous compaction, tensile failure, bulking and damage. In order to propagate motions to seismic distances we are developing a one-way coupling method to pass motions to WPP (a Cartesian anelastic finite difference code). Preliminary investigations of UNE's in canonical materials (granite, tuff and alluvium) confirm that emplacement conditions have a strong effect on seismic amplitudes and the generation of shear waves. Specifically, we find that motions from an explosion in high-strength, low-porosity granite have high compressional wave amplitudes and weak shear waves, while an explosion in low strength, high-porosity alluvium results in much weaker compressional waves and low-frequency compressional and shear waves of nearly equal amplitude. Further work will attempt to model available near-field seismic data from explosions conducted at NTS, where we have accurate characterization of the sub-surface from the wealth of geological and geophysical data from the former nuclear test program. Secondly, we are modeling seismic wave propagation with free-surface topography in WPP. We have model the October 9, 2006 and May 25, 2009 North Korean nuclear tests to investigate the impact of rugged topography on seismic waves. Preliminary results indicate that the topographic relief causes complexity in the direct P-waves that leads to azimuthally dependent behavior and the topographic gradient to the northeast, east and southeast of the presumed test locations generate stronger shear-waves, although each test gives a different pattern. Thirdly, we are modeling intermediate period motions (10-50 seconds) from earthquakes and explosions at regional distances. For these simulations we run SPECFEM3D{_}GLOBE (a spherical geometry spectral element code). We modeled broadband waveforms from well-characterized and well-observed events in the Middle East and central Asia, as well as the North Korean nuclear tests. For the recent North Korean test we found that the one-dimensional iasp91 model predicts the observed waveforms quite well in the band 20-50 seconds, while waveform fits for available 3D earth models are generally poor, with some exceptions. Interestingly 3D models can predict energy on the transverse component for an isotropic source presumably due to surface wave mode conversion and/or multipathing.

Rodgers, A; Vorobiev, O; Petersson, A; Sjogreen, B

2009-07-06T23:59:59.000Z

285

Environmental Aspects of Advanced Nuclear Fuel Cycles: Parametric Modeling and Preliminary Analysis  

E-Print Network (OSTI)

Nuclear power has the potential to help reduce rising carbon emissions, but to be considered sustainable, it must also demonstrate the availability of an indefinite fuel supply as well as not produce any significant negative environmental effects. The objective of this research was to evaluate the sustainability of nuclear power and to explore the nuclear fuel cycles that best meet this goal. First, the study quantified current and promising nuclear fuel cycles to be further evaluated and developed a set of objective metrics to describe the environmental effects of each cycle. The metrics included such factors as the amount of waste generated and the isotopic composition of the waste. Next, the evaluation used the International Atomic Energy Agency's Nuclear Fuel Cycle Simulation System to compute nuclide compositions at various stages of the fuel cycles. Finally, the study looked at the radioactivity of the waste generated and used this and other characteristics to determine which fuel cycle meets the objectives of sustainability. Results confirm that incorporating recycling into the fuel cycle would help reduce the volume of waste needing to be stored long-term. Also, calculations made with data from the Nuclear Fuel Cycle Simulation System predicted that the waste from fuel cycles using recycling would be slightly more radiotoxic than the open fuel cycle?s waste. However, the small increase in radiotoxicity is a manageable issue and would not detract from the benefits of recycling. Therefore, recycling and reprocessing spent fuel must be incorporated into the nuclear fuel cycle to achieve sustainability.

Yancey, Kristina D.

2010-05-01T23:59:59.000Z

286

Tough2/PC application simulation project for Heber geothermal field, California, a progress report  

SciTech Connect

A numerical simulation model for the Heber geothermal field in Southern California is being developed under a technology transfer agreement between the Department of Energy/Lawrence Berkeley National Laboratory (LBNL) and the California Department of Conservation, Division of Oil, Gas, and Geothermal Resources (DOGGR). The main objectives of the cooperation are (1) to train DOGGR personnel in the use of the TOUGH2PC computer code; and (2) to develop a module compatible with TOUGH2 to investigate the effects of production/injection operations on the ground surface subsidence-rebound phenomenon observed in the Heber geothermal field. Initial-state calibration (undisturbed system) runs are being conducted to calibrate the model.

Boardman, Timothy S.; Khan, M. Ali; Antunez, Emilio

1996-01-24T23:59:59.000Z

287

Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant  

SciTech Connect

Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

Nathan V. Hoffer; Piyush Sabharwall; Nolan A. Anderson

2011-01-01T23:59:59.000Z

288

Nuclear Forces and Nuclear Systems  

NLE Websites -- All DOE Office Websites (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

289

National Nuclear Data Center  

NLE Websites -- All DOE Office Websites (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!

290

Virtual Construction: Linking the 3D Model of the AP600 Nuclear Plant Design To its Construction Schedule  

Science Conference Proceedings (OSTI)

This report documents the results of an eight-month virtual construction study performed by Westinghouse for EPRI. Westinghouse performed this study as part of EPRI's interest in advancing the use of computer-aided processes to reduce the cost of nuclear power plants. EPRI believed that if one could relate appropriate portions of an advanced light water reactor plant design model to activities in its construction sequence and this relationship could be portrayed visually, then optimization of the constru...

2000-06-27T23:59:59.000Z

291

Phase-Field Modeling of Void Migration in Nuclear Fuels Due to a ...  

Science Conference Proceedings (OSTI)

Symposium, Materials Science Challenges for Nuclear Applications ... This is consistent with theoretical prediction and experiments. ... CASL: The Consortium for Advanced Simulation of Light Water Reactors: A U.S. Department of Energy ...

292

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

293

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

SciTech Connect

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

294

Health effects models for nuclear power plant accident consequence analysis: Modifications of models resulting from recent reports on health effects of ionizing radiation  

Science Conference Proceedings (OSTI)

The Nuclear Regulatory Commission has sponsored several studies to identify and quantify the potential health effects of accidental releases of radionuclides from nuclear power plants. The most recent health effects models resulting from these efforts were published in two reports, NUREG/CR-4214, Rev. 1, Part 1 (1990) and Part 2 (1989). Several major health effects reports have been published recently that may impact the health effects models presented in these reports. This addendum to the Part 2 (1989) report, provides a review of the 1986 and 1988 reports by the United Nations Scientific Committee on the Effects of Atomic Radiation, the National Academy of Sciences/National Research Council BEAR 5 Committee report and Publication 60 of the International Commission on Radiological Protection as they relate to this report. The three main sections of this addendum discuss early occurring and continuing effects, late somatic effects, and genetic effects. The major changes to the NUREG/CR-4214 health effects models recommended in this addendum are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies like that on the Japanese A-bomb survivors. The results presented in this addendum should be used with the basic NUREG/CR-4214 reports listed above to obtain the most recent views on the potential health effects of radionuclides released accidentally from nuclear power plants. 48 refs., 4 figs., 24 tabs.

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))

1991-08-01T23:59:59.000Z

295

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

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

296

Power-cable-carrier control (PC/sup 3/) system  

DOE Green Energy (OSTI)

A control system has been developed that uses a carrier signal imposed on an existing ac power circuit to transmit commands. This system was specifically developed to control an entire solar collector field by sending sun-tracking information to the trough collectors or by commanding them to assume safe positions (STOW) if out-of-limit conditions were encountered. Objectives were to develop a control system that operates reliably and has enough functions to control an entire collector field, yet do it at less cost than for conventional approaches. Development, design, operating characteristics, and field testing and results of the new system, the Power Cable Carrier Control (PC/sup 3/) System are described.

Alvis, R.L.; Wally, K.; Rosborough, J.R.

1981-04-01T23:59:59.000Z

297

Development of PC 4 dual-fuel engine  

SciTech Connect

Recently, utilization of natural gas, which is considered to be one of most important alternative fuels for petroleum, has been marked. As thermal efficiency of dual-fuel engine is higher than those of other prime movers with gaseous fuel, i.e., spark-ignited gas engine or gas turbine, it is possible to construct fuel-economical gas power plants with dual-fuel engines. However, its horsepower has been limited to the rather lower range. In 1984, NKK succeeded in developing large-sized dual-fuel engines based on the Pielstick PC4 diesel engine. The horsepower is 1200 HP/cyl, i.e. 21,600 HP for 18-cyclinder engine.

Nishikawa, T.; Utsuyama, S.; Maruyama, S.; Ono, T.; Kitahara, S.

1985-01-01T23:59:59.000Z

298

Argonne Chemical Sciences & Engineering - Nuclear & Environmental...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Fuel Cycle * Overview * Fissile Material * Chemical Process Models * Chemistry at Interfaces * Improved Safeguards Nuclear & Environmental Processes Home Closing the...

299

TWO-DIMENSIONAL MAPPING OF YOUNG STARS IN THE INNER 180 pc OF NGC 1068: CORRELATION WITH MOLECULAR GAS RING AND STELLAR KINEMATICS  

SciTech Connect

We report the first two-dimensional mapping of the stellar population and non-stellar continua within the inner 180 pc (radius) of NGC 1068 at a spatial resolution of 8 pc, using integral field spectroscopy in the near-infrared. We have applied the technique of spectral synthesis to data obtained with the instrument NIFS and the adaptive optics module ALTAIR at the Gemini North Telescope. Two episodes of recent star formation are found to dominate the stellar population contribution: the first occurred 300 Myr ago, extending over most of the nuclear region; the second occurred just 30 Myr ago, in a ring-like structure at Almost-Equal-To 100 pc from the nucleus, where it is coincident with an expanding ring of H{sub 2} emission. Inside the ring, where a decrease in the stellar velocity dispersion is observed, the stellar population is dominated by the 300 Myr age component. In the inner 35 pc, the oldest age component (age {>=} 2 Gyr) dominates the mass, while the flux is dominated by blackbody components with temperatures in the range 700 K {<=} T {<=} 800 K which we attribute to the dusty torus. We also find some contribution from blackbody and power-law components beyond the nucleus which we attribute to dust emission and scattered light.

Storchi-Bergmann, Thaisa; Riffel, Rogerio; Vale, Tiberio Borges [Departamento de Astronomia, Universidade Federal do Rio Grande do Sul, IF, CP 15051, 91501-970 Porto Alegre, RS (Brazil); Riffel, Rogemar A.; Diniz, Marlon R. [Departamento de Fisica, Centro de Ciencias Naturais e Exatas, Universidade Federal de Santa Maria, 97105-900 Santa Maria, RS (Brazil); McGregor, Peter J., E-mail: thaisa@ufrgs.br [Research School of Astronomy and Astrophysics, Australian National University, Cotter Road, Weston Creek, ACT 2611 (Australia)

2012-08-20T23:59:59.000Z

300

Science based integrated approach to advanced nuclear fuel development - integrated multi-scale multi-physics hierarchical modeling and simulation framework Part III: cladding  

Science Conference Proceedings (OSTI)

Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Reactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems to develop predictive tools is critical. Not only are fabrication and performance models needed to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. In this paper we review the current status of the advanced modeling and simulation of nuclear reactor cladding, with emphasis on what is available and what is to be developed in each scale of the project, how we propose to pass information from one scale to the next, and what experimental information is required for benchmarking and advancing the modeling at each scale level.

Tome, Carlos N [Los Alamos National Laboratory; Caro, J A [Los Alamos National Laboratory; Lebensohn, R A [Los Alamos National Laboratory; Unal, Cetin [Los Alamos National Laboratory; Arsenlis, A [LLNL; Marian, J [LLNL; Pasamehmetoglu, K [INL

2010-01-01T23:59:59.000Z

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.


301

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

302

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

NLE Websites -- All DOE Office Websites (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

303

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

Science Conference Proceedings (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

304

PC Electronic Data Reporting Option (PEDRO) System User’s Guide  

U.S. Energy Information Administration (EIA)

PC Electronic Data Reporting Option (PEDRO) System User’s Guide Version 6.2 Energy Information Administration U.S. Department of Energy Washington, ...

305

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

SciTech Connect

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

306

Review of air quality modeling techniques. Volume 8. [Assessment of environmental effects of nuclear, geothermal, and fossil-fuel power plants  

DOE Green Energy (OSTI)

Air transport and diffusion models which are applicable to the assessment of the environmental effects of nuclear, geothermal, and fossil-fuel electric generation are reviewed. The general classification of models and model inputs are discussed. A detailed examination of the statistical, Gaussian plume, Gaussian puff, one-box and species-conservation-of-mass models is given. Representative models are discussed with attention given to the assumptions, input data requirement, advantages, disadvantages and applicability of each.

Rosen, L.C.

1977-01-01T23:59:59.000Z

307

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

308

Argonne hosting Modeling, Experimentation and Validation (MeV...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

309

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

Science Conference Proceedings (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

310

[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

311

On the periodic variations of secondary cosmic rays and the geomagnetic Pc4 pulsations in BMAr  

E-Print Network (OSTI)

On the periodic variations of secondary cosmic rays and the geomagnetic Pc4 pulsations in BMAr I. M are accompanied by the geomagnetic Pc4 pulsations and have similar periodicity. The phenomenon was observed over of geomagnetic ®eld were observed simultaneously with apparent peri- odicity in the count rates of charged

Paris-Sud XI, Université de

312

Health effects models for nuclear power plant accident consequence analysis: Low LET radiation: Part 2, Scientific bases for health effects models  

Science Conference Proceedings (OSTI)

This report provides dose-response models intended to be used in estimating the radiological health effects of nuclear power plant accidents. Models of early and continuing effects, cancers and thyroid nodules, and genetic effects are provided. Two-parameter Weibull hazard functions are recommended for estimating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary and gastrointestinal syndromes -- are considered. Linear and linear-quadratic models are recommended for estimating cancer risks. Parameters are given for analyzing the risks of seven types of cancer in adults -- leukemia, bone, lung, breast, gastrointestinal, thyroid and ''other''. The category, ''other'' cancers, is intended to reflect the combined risks of multiple myeloma, lymphoma, and cancers of the bladder, kidney, brain, ovary, uterus and cervix. Models of childhood cancers due to in utero exposure are also provided. For most cancers, both incidence and mortality are addressed. Linear and linear-quadratic models are also recommended for assessing genetic risks. Five classes of genetic disease -- dominant, x-linked, aneuploidy, unbalanced translocation and multifactorial diseases --are considered. In addition, the impact of radiation-induced genetic damage on the incidence of peri-implantation embryo losses is discussed. The uncertainty in modeling radiological health risks is addressed by providing central, upper, and lower estimates of all model parameters. Data are provided which should enable analysts to consider the timing and severity of each type of health risk. 22 refs., 14 figs., 51 tabs.

Abrahamson, S.; Bender, M.; Book, S.; Buncher, C.; Denniston, C.; Gilbert, E.; Hahn, F.; Hertzberg, V.; Maxon, H.; Scott, B.

1989-05-01T23:59:59.000Z

313

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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.

314

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

Science Conference Proceedings (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

315

Health effects models for nuclear power plant accident consequence analysis. Part 1, Introduction, integration, and summary: Revision 2  

SciTech Connect

This report is a revision of NUREG/CR-4214, Rev. 1, Part 1 (1990), Health Effects Models for Nuclear Power Plant Accident Consequence Analysis. This revision has been made to incorporate changes to the Health Effects Models recommended in two addenda to the NUREG/CR-4214, Rev. 1, Part 11, 1989 report. The first of these addenda provided recommended changes to the health effects models for low-LET radiations based on recent reports from UNSCEAR, ICRP and NAS/NRC (BEIR V). The second addendum presented changes needed to incorporate alpha-emitting radionuclides into the accident exposure source term. As in the earlier version of this report, models are provided for early and continuing effects, cancers and thyroid nodules, and genetic effects. Weibull dose-response functions are recommended for evaluating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary, and gastrointestinal syndromes are considered. Linear and linear-quadratic models are recommended for estimating the risks of seven types of cancer in adults - leukemia, bone, lung, breast, gastrointestinal, thyroid, and ``other``. For most cancers, both incidence and mortality are addressed. Five classes of genetic diseases -- dominant, x-linked, aneuploidy, unbalanced translocations, and multifactorial diseases are also considered. Data are provided that should enable analysts to consider the timing and severity of each type of health risk.

Evans, J.S. [Harvard School of Public Health, Boston, MA (United States); Abrahmson, S. [Wisconsin Univ., Madison, WI (United States); Bender, M.A. [Brookhaven National Lab., Upton, NY (United States); Boecker, B.B.; Scott, B.R. [Inhalation Toxicology Research Inst., Albuquerque, NM (United States); Gilbert, E.S. [Battelle Pacific Northwest Lab., Richland, WA (United States)

1993-10-01T23:59:59.000Z

316

Conceptual Design of Oxygen-Based PC Boiler  

Science Conference Proceedings (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

317

A Latent Model to Detect Multiple Spatial Clusters with Application in a Mobile Sensor Network for Surveillance of Nuclear Materials  

E-Print Network (OSTI)

surveillance of nuclear materials in major cities. The network consists of a large number of vehicles on which for Surveillance of Nuclear Materials Jerry Cheng, Minge Xie, Rong Chen and Fred Roberts1 Abstract Nuclear attacks to infrastructure. To deter such threats, it becomes increasingly vital to have sophisticated nuclear surveillance

318

PC-DYMAC: Personal Computer---DYnamic Materials ACcounting  

SciTech Connect

This manual was designed to provide complete documentation for the computer system used by the EBR-II Fuels and Materials Department, Argonne National Laboratory-West (ANL-W) for accountability of special nuclear materials (SNM). This document includes background information on the operation of the Fuel Manufacturing Facility (FMF), instructions on computer operations in correlation with production and a detailed manual for DYMAC operation. 60 figs.

Jackson, B.G.

1989-11-01T23:59:59.000Z

319

Modeling of Digital Instrumentation and Control in Nuclear Power Plant Probabilistic Risk Assessments  

Science Conference Proceedings (OSTI)

Probabilistic risk assessment (PRA) typically models hardware components in terms of their failure probability and the effects that any given component failure has on the system it resides in. Digital systems, which include both hardware and software, bring new modeling challenges: determination of the appropriate level of detail to use in the logic models, and estimation of failure rates for software components. Failure probabilities for hardware are typically based on operating experience with componen...

2012-07-30T23:59:59.000Z

320

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

NLE Websites -- All DOE Office Websites (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.


321

Groundwater monitoring program plan and conceptual site model for the Al-Tuwaitha Nuclear Research Center in Iraq.  

Science Conference Proceedings (OSTI)

The Radiation Protection Center of the Iraqi Ministry of Environment is developing a groundwater monitoring program (GMP) for the Al-Tuwaitha Nuclear Research Center located near Baghdad, Iraq. The Al-Tuwaitha Nuclear Research Center was established in about 1960 and is currently being cleaned-up and decommissioned by Iraq's Ministry of Science and Technology. This Groundwater Monitoring Program Plan (GMPP) and Conceptual Site Model (CSM) support the Radiation Protection Center by providing:A CSM describing the hydrogeologic regime and contaminant issues,recommendations for future groundwater characterization activities, anddescriptions of the organizational elements of a groundwater monitoring program. The Conceptual Site Model identifies a number of potential sources of groundwater contamination at Al-Tuwaitha. The model also identifies two water-bearing zones (a shallow groundwater zone and a regional aquifer). The depth to the shallow groundwater zone varies from approximately 7 to 10 meters (m) across the facility. The shallow groundwater zone is composed of a layer of silty sand and fine sand that does not extend laterally across the entire facility. An approximately 4-m thick layer of clay underlies the shallow groundwater zone. The depth to the regional aquifer varies from approximately 14 to 17 m across the facility. The regional aquifer is composed of interfingering layers of silty sand, fine-grained sand, and medium-grained sand. Based on the limited analyses described in this report, there is no severe contamination of the groundwater at Al-Tuwaitha with radioactive constituents. However, significant data gaps exist and this plan recommends the installation of additional groundwater monitoring wells and conducting additional types of radiological and chemical analyses.

Copland, John Robin; Cochran, John Russell

2013-07-01T23:59:59.000Z

322

Groundwater monitoring program plan and conceptual site model for the Al-Tuwaitha Nuclear Research Center in Iraq.  

SciTech Connect

The Radiation Protection Center of the Iraqi Ministry of Environment is developing a groundwater monitoring program (GMP) for the Al-Tuwaitha Nuclear Research Center located near Baghdad, Iraq. The Al-Tuwaitha Nuclear Research Center was established in about 1960 and is currently being cleaned-up and decommissioned by Iraq's Ministry of Science and Technology. This Groundwater Monitoring Program Plan (GMPP) and Conceptual Site Model (CSM) support the Radiation Protection Center by providing:A CSM describing the hydrogeologic regime and contaminant issues,recommendations for future groundwater characterization activities, anddescriptions of the organizational elements of a groundwater monitoring program. The Conceptual Site Model identifies a number of potential sources of groundwater contamination at Al-Tuwaitha. The model also identifies two water-bearing zones (a shallow groundwater zone and a regional aquifer). The depth to the shallow groundwater zone varies from approximately 7 to 10 meters (m) across the facility. The shallow groundwater zone is composed of a layer of silty sand and fine sand that does not extend laterally across the entire facility. An approximately 4-m thick layer of clay underlies the shallow groundwater zone. The depth to the regional aquifer varies from approximately 14 to 17 m across the facility. The regional aquifer is composed of interfingering layers of silty sand, fine-grained sand, and medium-grained sand. Based on the limited analyses described in this report, there is no severe contamination of the groundwater at Al-Tuwaitha with radioactive constituents. However, significant data gaps exist and this plan recommends the installation of additional groundwater monitoring wells and conducting additional types of radiological and chemical analyses.

Copland, John Robin; Cochran, John Russell

2013-07-01T23:59:59.000Z

323

Simulation, Modeling, and Crystal Growth of Cd0.9Zn0.1Te for Nuclear Spectrometers  

Science Conference Proceedings (OSTI)

High-quality, large (10 cm long and 2.5 cm diameter), nuclear spectrometer grade Cd{sub 0.9}Zn{sub 0.1}Te (CZT) single crystals have been grown by a controlled vertical Bridgman technique using in-house zone refined precursor materials (Cd, Zn, and Te). A state-of-the-art computer model, multizone adaptive scheme for transport and phase-change processes (MASTRAP), is used to model heat and mass transfer in the Bridgman growth system and to predict the stress distribution in the as-grown CZT crystal and optimize the thermal profile. The model accounts for heat transfer in the multiphase system, convection in the melt, and interface dynamics. The grown semi-insulating (SI) CZT crystals have demonstrated promising results for high-resolution room-temperature radiation detectors due to their high dark resistivity ({rho} {approx} 2.8 x 10{sup 11} {Theta} cm), good charge-transport properties, electron and hole mobility-life-time product, {mu}{tau}{sub e} {approx} (2-5) x 10{sup -3} and {mu}{tau}{sub h} {approx} (3-5) x 10{sup -5} respectively, and low cost of production. Spectroscopic ellipsometry and optical transmission measurements were carried out on the grown CZT crystals using two-modulator generalized ellipsometry (2-MGE). The refractive index n and extinction coefficient k were determined by mathematically eliminating the {approx}3-nm surface roughness layer. Nuclear detection measurements on the single-element CZT detectors with {sup 241}Am and {sup 137}Cs clearly detected 59.6 and 662 keV energies with energy resolution (FWHM) of 2.4 keV (4.0%) and 9.2 keV (1.4%), respectively.

Mandal, Krishna [EIC Laboratories, Inc.; Kang, Sung Hoon [EIC Laboratories, Inc.; Choi, Michael [EIC Laboratories, Inc.; Bello, Job [EIC Laboratories, Inc.; Zheng, Lili [State University of New York, Stony Brook; Zhang, Hui [State University of New York, Stony Brook; Groza, Michael [Fisk University, Nashville, TN; Roy, Utpal N. [Fisk University, Nashville, TN; Burger, Arnold [Fisk University, Nashville, TN; Jellison Jr, Gerald Earle [ORNL; Holcomb, David Eugene [ORNL; Wright, Gomez W [ORNL; Williams, Joseph A [ORNL

2006-01-01T23:59:59.000Z

324

Development of design and simulation model and safety study of large-scale hydrogen production using nuclear power.  

DOE Green Energy (OSTI)

Before this LDRD research, no single tool could simulate a very high temperature reactor (VHTR) that is coupled to a secondary system and the sulfur iodine (SI) thermochemistry. Furthermore, the SI chemistry could only be modeled in steady state, typically via flow sheets. Additionally, the MELCOR nuclear reactor analysis code was suitable only for the modeling of light water reactors, not gas-cooled reactors. We extended MELCOR in order to address the above deficiencies. In particular, we developed three VHTR input models, added generalized, modular secondary system components, developed reactor point kinetics, included transient thermochemistry for the most important cycles [SI and the Westinghouse hybrid sulfur], and developed an interactive graphical user interface for full plant visualization. The new tool is called MELCOR-H2, and it allows users to maximize hydrogen and electrical production, as well as enhance overall plant safety. We conducted validation and verification studies on the key models, and showed that the MELCOR-H2 results typically compared to within less than 5% from experimental data, code-to-code comparisons, and/or analytical solutions.

Gelbard, Fred; Oh, Seungmin (Purdue University, West Lafayette, IN); Rodriguez, Salvador B.; Revankar, Shripad T. (Purdue University, West Lafayette, IN); Gauntt, Randall O.; Cole, Randall K., Jr.; Espinosa, Flor (University of New Mexico, Albuquerque, NM); Drennen, Thomas E.; Tournier, Jean-Michel (University of New Mexico, Albuquerque, NM); Hogan, Kevin (Texas A& M University, College Station, TX); Archuleta, Louis (OMICRON Safety and Risk, Inc., Albuquerque, NM); Malczynski, Leonard A.; Vierow, Karen (Texas A& M University, College Station, TX); McFadden, Katherine Letizia; Martin, William Joseph; El-Genk, Mohamed S. (University of New Mexico, Albuquerque, NM); Louie, David L. Y. (OMICRON Safety and Risk, Inc., Albuquerque, NM)

2007-10-01T23:59:59.000Z

325

Directory of Energy Information Administration models, 1990  

Science Conference Proceedings (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

326

Quantum chaos in the nuclear collective model: I. Classical-quantum correspondence  

E-Print Network (OSTI)

Spectra of the geometric collective model of atomic nuclei are analyzed to identify chaotic correlations among nonrotational states. The model has been previously shown to exhibit a high degree of variability of regular and chaotic classical features with energy and control parameters. Corresponding signatures are now verified also on the quantum level for different schemes of quantization and with a variable classicality constant.

Pavel Stransky; Petr Hruska; Pavel Cejnar

2009-02-23T23:59:59.000Z

327

Digital control systems in nuclear power plants: Failure information, modeling concepts, and applications. Revision 1  

SciTech Connect

This report briefly describes some current applications of advanced computerized digital display and control systems at US commercial nuclear power plants and presents the results of a literature search that was made to gather information on the reliability of these systems. Both hardware and software reliability were addressed in this review. Only limited failure rate information was found, with the chemical process industry being the primary source of information on hardware failure rates and expert opinion the primary source for software failure rates. Safety-grade digital control systems are typically installed on a functional like-for-like basis, replacing older analog systems without substantially changing interactions with other plant systems. Future work includes performing a limited probabilistic risk assessment of a representative DCS to assess its risk significance.

Galyean, W.J.

1993-06-23T23:59:59.000Z

328

The Build-Up of Nuclear Stellar Cusps in Extreme Starburst Galaxies and Major Mergers  

E-Print Network (OSTI)

Nuclear stellar cusps are defined as central excess light component in the stellar light profiles of galaxies and are suggested to be stellar relics of intense compact starbursts in the central ~100-500 pc region of gas-rich major mergers. Here we probe the build-up of nuclear cusps during the actual starburst phase for a complete sample of Luminous Infrared Galaxy systems (85 LIRGs, with 11.4nuclear stellar light imaged in the near-infrared by the Hubble Space Telescope and have been combined with mid-IR diagnostics for AGN/starburst characterization. We find that nuclear stellar cusps are resolved in 76% of LIRGs (merger and non-interacting galaxies). The cusp strength and luminosity increases with far-IR luminosity (excluding AGN) and merger stage, confirming theoretical models that starburst activity is associated with the build-up of nuclear stellar cusps. Evidence for ultra compact nuclear starb...

Haan, S; Surace, J A; Charmandaris, V; Evans, A S; Diaz-Santos, T; Melbourne, J L; Mazzarella, J M; Howell, J H; Stierwalt, S; Kim, D C; Vavilkin, T; Sanders, D B; Petric, A; Murphy, E J; Braun, R; Bridge, C R; Inami, H

2013-01-01T23:59:59.000Z

329

Point of Contact: Doug Kothe CASL Director 865-241-9392 kothe@ornl.gov www.casl.gov A DOE Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors  

E-Print Network (OSTI)

Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors CASL became a DOE Energy Innovation energy, and national security; universities with preeminent nuclear engineering programs; and vendor,Tennessee Valley Authority [TVA], and Electric Power Research Institute). As laboratory leaders in science, nuclear

330

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

NLE Websites -- All DOE Office Websites (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

331

A self-confined Fermi-gas model for nuclear collective motion  

E-Print Network (OSTI)

The main result of this study consists in working out a microscopic description of collective motion in hot nuclei, allowing to express the parameters of a phenomenological collective model in terms of nucleonic quantities.

V. P. Aleshin

2008-11-24T23:59:59.000Z

332

Numerical modeling of gas migration at a proposed repository for low and intermediate level nuclear wastes at Oberbauenstock, Switzerland  

Science Conference Proceedings (OSTI)

Hydrologic impacts of corrosive gas release from a hypothetical L/ILW nuclear waste repository at Oberbauenstock are explored by means of numerical simulation. A schematic two dimensional vertical section through the mountain is modeled with the simulator TOUGH, which describes two-phase flow of water and gas in porous and fractured media. Two reference cases are considered which represent the formations as a porous and as a fractured-porous (dual permeability) medium, respectively. Both cases predict similar and rather modest pressure increases, from ambient 10 bars to near 25 bars at the repository level. These results are to be considered preliminary because important parameters affecting two-phase flow, such as relative permeabilities of a fractured medium, are not well known at present. 24 refs., 15 figs., 5 tabs.

Pruess, K.

1990-03-01T23:59:59.000Z

333

Summary of the environmental dose models used at DOE nuclear sites in 1979  

SciTech Connect

Methods for assessing public exposure to radiation from normal operations at DOE facilities are reviewed in this report. This review includes a summary of the methods used in 1979 as described in annual environmental reports submitted by Department of Energy (DOE) contractors. The methods used ranged from estimating public doses based on environmental measurements and comparison to the DOE concentration guides, to complex methods using environmental pathway modeling and estimated radionuclide releases. No two sites used the same combination of measurements and pathway models in their analysis. While most sites used an atmospheric dispersion model to predict air concentrations of radioactive material, only about half of the sites provided enough information about the model used to permit proper model evaluation. The waterborne pathways related to drinking water or ingestion of fish were generally well described, while the external exposure or terrestrial food pathways were often not considered. The major recommendation resulting from this review was that complete documentations of the models used should be included either within the annual reports or as separate readily available documents. In addition, most sites could make better use of graphics (i.e., tables and figures) to better communicate the findings of their analyses.

Kennedy, W.E. Jr.; Mueller, M.A.

1982-09-01T23:59:59.000Z

334

Nuclear Shadowing and Diffraction  

E-Print Network (OSTI)

The relation between diffraction in lepton-proton collisions and shadowing of nuclear structure functions which arises from Gribov inelastic shadowing, is described. A model realizing such relation, which produces a parameter-free description of experimental data on nuclear structure functions at small $x$, is presented. The application to the description of multiplicities in nuclear collisions is discussed and related to other approaches.

J. L. Albacete; N. Armesto; A. Capella; A. B. Kaidalov; C. A. Salgado

2004-10-12T23:59:59.000Z

335

A PC-Based Interactive Imaging System Designed for INSAT Data Analysis and Monsoon Studies  

Science Conference Proceedings (OSTI)

A PC-based interactive image processing system has been developed for aiding the analysis of Indian Geosynchronous Satellite (INSAT) data for Asian monsoon studies. In view of its diminutive stature, the system has been given the name “MIDGET,” ...

Eric A. Smith; Kyung Whan Oh; Matthew R. Smith

1989-09-01T23:59:59.000Z

336

Substrate effect on the electronic structures of CuPc/graphene interfaces  

SciTech Connect

The interfacial electronic structures of copper phthalocyanine (CuPc) deposited on a single-layer graphene (SLG) film prepared on Cu and SiO{sub 2} substrates (SLG/Cu and SLG/SiO{sub 2}) were investigated using ultraviolet photoelectron spectroscopy. The ionization energy of CuPc on SLG/Cu and SLG/SiO{sub 2} substrate is, respectively, 5.62 eV and 4.97 eV. The energy level alignments at the two interfaces were estimated. The results revealed that the height of the electron (hole) injection barriers are 1.20 (1.10) and 1.38 (0.92) eV at CuPc/SLG/Cu and CuPc/SLG/SiO{sub 2} interfaces, respectively.

Wu Qihui; Hong Guo; Ng, T. W.; Lee, S. T. [Center of Super-Diamond and Advanced Films (COSDAF) and Department of Physics and Materials Science, City University of Hong Kong (Hong Kong)

2012-04-16T23:59:59.000Z

337

Nuclear spirals as feeding channels to the Supermassive Black Hole: the case of the galaxy NGC 6951  

E-Print Network (OSTI)

We report the discovery of gas streaming motions along nuclear spiral arms towards the LINER nucleus of the galaxy NGC 6951. The observations, obtained using the GMOS integral field spectrograph on the Gemini North telescope, yielded maps of the flux distributions and gas kinematics in the Halpha, [NII]6584 and [SII]6717,31 emission lines of the inner 7x5 arcsec^2 of the galaxy. This region includes a circumnuclear star-forming ring with radius 500pc, a nuclear spiral inside the ring and the LINER nucleus. The kinematics of the ionized gas is dominated by rotation, but subtraction of a kinematic model of a rotating exponential disk reveals deviations from circular rotation within the nuclear ring which can be attributed to (1) streaming motions along the nuclear spiral arms and (2) a bipolar outflow which seems to be associated to a nuclear jet. On the basis of the observed streaming velocities and geometry of the spiral arms we estimate a mass inflow rate of ionized gas of 3x10^(-4) Msun/yr, which is of the order of the accretion rate necessary to power the LINER nucleus of NGC 6951. Similar streaming motions towards the nucleus of another galaxy with LINER nucleus -- NGC 1097 -- have been reported by our group in a previous paper. Taken together, these results support a scenario in which nuclear spirals are channels through which matter is transferred from galactic scales to the nuclear region to feed the supermassive black hole.

Thaisa Storchi-Bergmann; Oli L. Dors Jr.; Rogemar A. Riffel; Kambiz Fathi; David J. Axon; Andrew Robinson; Alessandro Marconi; Goran Ostlin

2007-07-27T23:59:59.000Z

338

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

Open Energy Info (EERE)

additional parameters solved in the inversion. Initial inversion results for the Coso data set qualitatively resemble previous models from 2-D inversion stitches and from massively...

339

Secondary system modeling and method for a nuclear power plant training simulator. [PWR  

SciTech Connect

Disclosed is a method and system for the real-time simulation of the dynamic operation of a nuclear power plant in which a secondary system for operating the steam turbine includes reheaters for increasing the steam temperature and pressure between the low and high pressure turbine stages, an electrohydraulic controller for operating the turbine at required speed, a condenser for condensing turbine exhaust steam, a condensate and feedwater system for pumping condensed steam back to the secondary side of a steam generator, a gland steam system for preventing leakage from and to the atmosphere, and a cooling system for the main generator, utilizes apparatus that includes a digital computer for calculating output data corresponding to physical values for the operation of the plant in accordance with input data. A control console includes automatic and manually operable devices corresponding to plant control devices for varying the input data, and indicating devices responsive to the output data for monitoring the operation of the plant. 40 claims, 45 figures.

Johnson, S.J.

1977-08-16T23:59:59.000Z

340

Nuclear data for nuclear transmutation  

Science Conference Proceedings (OSTI)

Current status on nuclear data for the study of nuclear transmutation of radioactive wastes is reviewed

Hideo Harada

2009-01-01T23:59:59.000Z

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.


341

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

342

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

E-Print Network (OSTI)

Deeply Embedded Nuclear Power Plant Structures. ” NUREG/CR–6896, BNL–NUREG–75410–2006, Brookhaven National Laboratory,

Keldrauk, Eric Scott

2012-01-01T23:59:59.000Z

343

PC Active Management Technology AMT vAMT vAMT  

E-Print Network (OSTI)

vAMT vAMT CIM 4 vAMT CIM 5 vAMT 6 7 2 PC 2.1 AMT AMT vPro PC AMT AMT System Management BIOS SMBIOS (CIM [3] AMT AMT vAMT 3 VM 3.1 CIM CIM CIM CIM #12;CIM Managed Object Format MOF MOF BNF CIM CIM MOF 4 CIM Processor CIM Chip CIM Realizes 4 CIM Processor CIM CIM LogicalDevice CPU Number CPU Enable Number

Kourai, Kenichi

344

A PC-based telemetry system for acquiring and reducing data from multiple PCM streams  

DOE Green Energy (OSTI)

The Solar Energy Research Institute's (SERI) Wind Research Program is using Pulse Code Modulation (PCM) telemetry data-acquisition systems to study horizontal-axis wind turbines. Many PCM systems are combined for use in test installations that require accurate measurements from a variety of different locations. SERI has found them ideal for data-acquisition from multiple wind turbines and meteorological towers in wind parks. A major problem has been in providing the capability to quickly combine and examine incoming data from multiple PCM sources in the field. To solve this problem, SERI has developed a low-cost PC-based PCM telemetry data-reduction system to facilitate quick, in-the-field multiple-channel data analysis. Called the PC-PCM System,'' it consists of two basic components. First, PC-compatible hardware boards are used to decode and combine multiple PCM data streams. Up to four hardware boards can be installed in a single PC, which provides the capability to combine data from four PCM streams directly to PC disk or memory. Each stream can have up to 62 data channels. Second, a software package written for use under DOS was developed to simplify data-acquisition control and management. The software provides a quick, easy-to-use interface between the PC and multiple PCM data streams. Called the Quick-Look Data Management Program,'' it is a comprehensive menu-driven package used to organize, acquire, process, and display information from incoming PCM data streams. The paper describes both hardware and software aspects of the SERI PC-PCM system, concentrating on features that make it useful in an experiment test environment to quickly examine and verify incoming data from multiple PCM streams. Also discussed are problems and techniques associated with PC-based telemetry data-acquisition, processing, and real-time display. 11 refs., 2 figs., 3 tabs.

Simms, D A; Butterfield, C P

1991-07-01T23:59:59.000Z

345

Nuclear scales  

Science Conference Proceedings (OSTI)

Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the {pi}-{gamma} force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

Friar, J.L.

1998-12-01T23:59:59.000Z

346

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

E-Print Network (OSTI)

monitored at a Finnish nuclear Pressurized Water Reactor (PWR) and 920 simulated signals of the Swedish the reconstruction of a data set of 215 signals measured at a Finnish nuclear Pressurized Water Reactor (PWR) located at a nuclear Pressurized Water Reactor (PWR) located in Loviisa, Finland; the second addresses

347

Anti-symmetric spin-orbit force in the effective interaction for the shell model and its effect on nuclear structure  

Science Conference Proceedings (OSTI)

Anti-symmetric spin-orbit force (ALS) in the effective interaction for the shell model and its effect on nuclear structure is discussed. We investigate possible origins of the ALS and the effects on the level schemes of several nuclei.

Tsunoda, N.; Shimizu, N. [Department of Science, University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, I-80126 (Japan); Otsuka, T. [Department of Science, University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, I-80126 (Japan); Center for Nuclear Study, University of Tokyo, Hongo, Bunkyo-ku Tokyo, 113-0033 (Japan) and National Superconducting Cyclotron Laboratory, Michigan State University, East Lansing, MI (United States); Suzuki, T. [Department of Physics, College of Humanities and Sciences, Nihon University, Sakurajosui 3, Tokyo 156-8550 (Japan)

2011-05-06T23:59:59.000Z

348

Modeling a Printed Circuit Heat Exchanger with RELAP5-3D for the Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

The main purpose of this report is to design a printed circuit heat exchanger (PCHE) for the Next Generation Nuclear Plant and carry out Loss of Coolant Accident (LOCA) simulation using RELAP5-3D. Helium was chosen as the coolant in the primary and secondary sides of the heat exchanger. The design of PCHE is critical for the LOCA simulations. For purposes of simplicity, a straight channel configuration was assumed. A parallel intermediate heat exchanger configuration was assumed for the RELAP5 model design. The RELAP5 modeling also required the semicircular channels in the heat exchanger to be mapped to rectangular channels. The initial RELAP5 run outputs steady state conditions which were then compared to the heat exchanger performance theory to ensure accurate design is being simulated. An exponential loss of pressure transient was simulated. This LOCA describes a loss of coolant pressure in the primary side over a 20 second time period. The results for the simulation indicate that heat is initially transferred from the primary loop to the secondary loop, but after the loss of pressure occurs, heat transfers from the secondary loop to the primary loop.

Not Available

2010-12-01T23:59:59.000Z

349

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.  

SciTech Connect

This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational 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. Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologic-chemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.

Criscenti, Louise Jacqueline; Sassani, David Carl; Arguello, Jose Guadalupe, Jr.; Dewers, Thomas A.; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Wang, Yifeng; Schultz, Peter Andrew

2011-02-01T23:59:59.000Z

350

Medium energy nuclear data for applications  

SciTech Connect

The types of medium energy nuclear data required for applications are discussed. Features of analysis tools, consisting of both detailed nuclear model codes and simple formulas based on nuclear systematics are presented. The activities of the Medium Energy Nuclear Data Working Group (MENDWG) are described including the recent benchmark comparison of nuclear model codes. 40 refs., 7 figs.

Pearlstein, S.

1988-01-01T23:59:59.000Z

351

"Ask Argonne" - Dave Grabaskas, Nuclear Engineer, Part 2 | Argonne...  

NLE Websites -- All DOE Office Websites (Extended Search)

--Manufacturing -Energy sources --Renewable energy ---Bioenergy ---Solar energy --Fossil fuels ---Natural Gas --Nuclear energy ---Nuclear energy modeling & simulation...

352

A fully microscopical simulation of nuclear collisions by a new QMD model  

E-Print Network (OSTI)

Nucleon-ion and ion-ion collisions at non relativistic bombarding energies can be described by means of Monte Carlo approaches, such as those based on the Quantum Molecular Dynamics (QMD) model. We have developed a QMD code, to simulate the fast stage of heavy-ion reactions, and we have coupled it to the de-excitation module available in the FLUKA Monte Carlo transport and interaction code. The results presented in this work span the projectile bombarding energy range within 200 - 600 MeV/A, allowing to investigate the capabilities and limits of our non-relativistic QMD approach.

M. V. Garzelli

2007-04-30T23:59:59.000Z

353

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

354

Overview of Reactor and Nuclear  

E-Print Network (OSTI)

and Safety Gary Mays Nuclear Data and Criticality Safety Mike Dunn Nuclear Security Modeling Tim Valentine - Office of Environmental Management - Office of Intelligence · National Nuclear Security AdministrationOverview of Reactor and Nuclear Systems Division Cecil Parks RNS Division Director parkscv

355

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

Science Conference Proceedings (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

356

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL  

SciTech Connect

The work reported here is an investigation of the sensitivity of component temperatures of a storage system, including fuel cladding temperatures, in response to age-related changes that could degrade the design-basis thermal behavior of the system. Three specific areas of interest were identified for this study. • degradation of the canister backfill gas from pure helium to a mixture of air and helium, resulting from postulated leakage due to stress corrosion cracking (SCC) of canister welds • changes in surface emissivity of system components, resulting from corrosion or other aging mechanisms, which could cause potentially significant changes in temperatures and temperature distributions, due to the effect on thermal radiation exchange between components • changes in fuel and basket temperatures due to changes in fuel assembly position within the basket cells in the canister The purpose of these sensitivity studies is to provide a realistic example of how changes in the physical properties or configuration of the storage system components can affect temperatures and temperature distributions. The magnitudes of these sensitivities can provide guidance for identifying appropriate modeling assumptions for thermal evaluations extending long term storage out beyond 50, 100, 200, and 300 years.

Cuta, Judith M.; Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.

2013-08-15T23:59:59.000Z

357

Fluid-Structure Interaction Modeling of High-Aspect Ratio Nuclear Fuel Plates Using COMSOL  

SciTech Connect

The High Flux Isotope Reactor at the Oak Ridge National Lab is in the research stage of converting its fuel from high-enriched uranium to low-enriched uranium. Due to different physical properties of the new fuel and changes to the internal fuel plate design, the current safety basis must be re-evaluated through rigorous computational analyses. One of the areas being explored is the fluid-structure interaction phenomenon due to the interaction of thin fuel plates (50 mils thickness) and the cooling fluid (water). Detailed computational fluid dynamics and fluid-structure interaction simulations have only recently become feasible due to improved numerical algorithms and advancements in computing technology. For many reasons including the already built-in fluid-structure interaction module, COMSOL has been chosen for this complex problem. COMSOL's ability to solve multiphysics problems using a fully-coupled and implicit solution algorithm is crucial in obtaining a stable and accurate solution. Our initial findings show that COMSOL can accurately model such problems due to its ability to closely couple the fluid dynamics and the structural dynamics problems.

Curtis, Franklin G [ORNL] ORNL; Ekici, Kivanc [ORNL] ORNL; Freels, James D [ORNL] ORNL

2013-01-01T23:59:59.000Z

358

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel ... nuclear reactors, generation, spent fuel. Total Energy. Comprehensive data summaries, comparisons, analysis, and projections ...

359

Advanced Reactor Development and Technology - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Nuclear Data Program Advanced Reactor Development Overview Advanced Fast Reactor...

360

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

Science Conference Proceedings (OSTI)

The Surtsey Test Facility is used to perform scaled experiments simulating High Pressure Melt Ejection accidents in a nuclear power plant (NPP). The experiments investigate the effects of direct containment heating (DCH) on the containment load. The results from Zion and Surry experiments can be extrapolated to other Westinghouse plants, but predicted containment loads cannot be generalized to all Combustion Engineering (CE) plants. Five CE plants have melt dispersal flow paths which circumvent the main mitigation of containment compartmentalization in most Westinghouse PWRs. Calvert Cliff-like plant geometries and the impact of codispersed water were addressed as part of the DCH issue resolution. Integral effects tests were performed with a scale model of the Calvert Cliffs NPP inside the Surtsey test vessel. The experiments investigated the effects of codispersal of water, steam, and molten core stimulant materials on DCH loads under prototypic accident conditions and plant configurations. The results indicated that large amounts of coejected water reduced the DCH load by a small amount. Large amounts of debris were dispersed from the cavity to the upper dome (via the annular gap). 22 refs., 84 figs., 30 tabs.

Blanchat, T.K.; Pilch, M.M.; Allen, M.D.

1997-02-01T23:59:59.000Z

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.


361

Folding model study of the charge-exchange scattering to the isobaric analog state and implication for the nuclear symmetry energy  

E-Print Network (OSTI)

The Fermi transition (\\Delta L=\\Delta S=0 and \\Delta T=1) between the nuclear isobaric analog states (IAS), induced by the charge-exchange (p,n) or (3He,t) reaction, can be considered as "elastic" scattering of proton or 3He by the isovector term of the optical potential (OP) that flips the projectile isospin. The accurately measured (p,n) or (3He,t) scattering cross-section to the IAS can be used, therefore, to probe the isospin dependence of the proton or 3He optical potential. Within the folding model, the isovector part of the OP is determined exclusively by the neutron-proton difference in the nuclear densities and the isospin dependence of the effective nucleon-nucleon (NN) interaction. Because the isovector coupling explicitly links the isovector part of the proton or 3He optical potential to the cross section of the charge-exchange (p,n) or (3He,t) scattering to the IAS, the isospin dependence of the effective (in-medium) NN interaction can be well tested in the folding model analysis of these charge-exchange reactions. On the other hand, the same isospin- and density dependent NN interaction can also be used in a Hartree-Fock calculation of asymmetric nuclear matter, to estimate the nuclear matter energy and its asymmetry part (the nuclear symmetry energy). As a result, the fine-tuning of the isospin dependence of the effective NN interaction against the measured (p,n) or (3He,t) cross sections should allow us to make some realistic prediction of the nuclear symmetry energy and its density dependence.

Dao T. Khoa; Bui Minh Loc; Dang Ngoc Thang

2013-07-01T23:59:59.000Z

362

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

Science Conference Proceedings (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

363

Models and Results Database (MAR-D), Version 4. 0  

SciTech Connect

The Nuclear Regulatory Commission's Office of Nuclear Regulatory Research (NRC-RES) is presently funding the development of the Models and Results Database (MAR-D) at the Idaho National Engineering Laboratory. MAR-D's primary function is to create a data repository for NUREG-1150 and other permanent data by providing input, conversion, and output capabilities for data used by IRRAS, SARA, SETS, and FRANTIC personal computer (PC) codes. As probabilistic risk assessments and individual plant examinations are submitted to the NRC for review, MAR-D can be used to convert the models and results from the study for use with IRRAS and SARA. Then, these data can be easily accessed by future studies and will be in a form that will enhance the analysis process. This reference manual provides an overview of the function available within MAR-D and step-by-step operating instructions.

Branham-Haar, K.A.; Dinneen, R.A.; Russell, K.D.; Skinner, N.L. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-05-01T23:59:59.000Z

364

Nuclear power and nuclear weapons  

SciTech Connect

The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described.

Vaughen, V.C.A.

1983-01-01T23:59:59.000Z

365

Nuclear Data | More Science | ORNL  

NLE Websites -- All DOE Office Websites (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

366

Nuclear medium effects in $\  

E-Print Network (OSTI)

We study the nuclear medium effects in the weak structure functions $F_2(x,Q^2)$ and $F_3(x,Q^2)$ in the deep inelastic neutrino/antineutrino reactions in nuclei. We use a theoretical model for the nuclear spectral functions which incorporates the conventional nuclear effects, such as Fermi motion, binding and nucleon correlations. We also consider the pion and rho meson cloud contributions calculated from a microscopic model for meson-nucleus self-energies. The calculations have been performed using relativistic nuclear spectral functions which include nucleon correlations. Our results are compared with the experimental data of NuTeV and CDHSW.

Haider, H; Athar, M Sajjad; Vacas, M J Vicente

2011-01-01T23:59:59.000Z

367

Computer-Based Procedures for Field Workers in Nuclear Power Plants: Development of a Model of Procedure Usage and Identification of Requirements  

SciTech Connect

The nuclear industry is constantly trying to find ways to decrease the human error rate, especially the human errors associated with procedure use. As a step toward the goal of improving procedure use performance, researchers, together with the nuclear industry, have been looking at replacing the current paper-based procedures with computer-based procedure systems. The concept of computer-based procedures is not new by any means; however most research has focused on procedures used in the main control room. Procedures reviewed in these efforts are mainly emergency operating procedures and normal operating procedures. Based on lessons learned for these previous efforts we are now exploring a more unknown application for computer based procedures - field procedures, i.e. procedures used by nuclear equipment operators and maintenance technicians. The Idaho National Laboratory and participants from the U.S. commercial nuclear industry are collaborating in an applied research effort with the objective of developing requirements and specifications for a computer-based procedure system to be used by field workers. The goal is to identify the types of human errors that can be mitigated by using computer-based procedures and how to best design the computer-based procedures to do so. This paper describes the development of a Model of Procedure Use and the qualitative study on which the model is based. The study was conducted in collaboration with four nuclear utilities and five research institutes. During the qualitative study and the model development requirements and for computer-based procedures were identified.

Katya Le Blanc; Johanna Oxstrand

2012-04-01T23:59:59.000Z

368

A new PowerPC microprocessor for low power computing systems  

Science Conference Proceedings (OSTI)

A new PowerPC microprocessor is designed for desktop companions and high end embedded multimedia applications such as high performance video games with graphics intensive operations. It features a low power consumption of 1.2 watts at 66 MHz at 3.3 volts. ... Keywords: 0.5 micron, 66 MHz, CMOS integrated circuits, CMOS technology, PowerPC microprocessor, data caches, desktop companions, graphics intensive operations, high end embedded multimedia applications, low power computing systems, low power consumption, microprocessor chips, video games

D. Ogden; B. Kuttanna; A. J. Loper; S. Mallick; M. Putrino

1995-03-01T23:59:59.000Z

369

NNS computing facility manual P-17 Neutron and Nuclear Science  

SciTech Connect

This document describes basic policies and provides information and examples on using the computing resources provided by P-17, the Neutron and Nuclear Science (NNS) group. Information on user accounts, getting help, network access, electronic mail, disk drives, tape drives, printers, batch processing software, XSYS hints, PC networking hints, and Mac networking hints is given.

Hoeberling, M.; Nelson, R.O.

1993-11-01T23:59:59.000Z

370

MARVEL: A PC-based interactive software package for life-cycle evaluations of hybrid/electric vehicles  

SciTech Connect

As a life-cycle analysis tool, MARVEL has been developed for the evaluation of hybrid/electric vehicle systems. It can identify the optimal combination of battery and heat engine characteristics for different vehicle types and performance requirements, on the basis of either life-cycle cost or fuel efficiency. Battery models that allow trade-offs between specific power and specific energy, between cycle life and depth of discharge, between peak power and depth of discharge, and between other parameters, are included in the software. A parallel hybrid configuration, using an internal combustion engine and a battery as the power sources, can be simulated with a user-specified energy management strategy. The PC-based software package can also be used for cost or fuel efficiency comparisons among conventional, electric, and hybrid vehicles.

Marr, W.W.; He, J.

1995-07-01T23:59:59.000Z

371

Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS) Code Verification and Validation Data Standards and Requirements: Fluid Dynamics Version 1.0  

SciTech Connect

V&V and UQ are the primary means to assess the accuracy and reliability of M&S and, hence, to establish confidence in M&S. Though other industries are establishing standards and requirements for the performance of V&V and UQ, at present, the nuclear industry has not established such standards or requirements. However, the nuclear industry is beginning to recognize that such standards are needed and that the resources needed to support V&V and UQ will be very significant. In fact, no single organization has sufficient resources or expertise required to organize, conduct and maintain a comprehensive V&V and UQ program. What is needed is a systematic and standardized approach to establish and provide V&V and UQ resources at a national or even international level, with a consortium of partners from government, academia and industry. Specifically, what is needed is a structured and cost-effective knowledge base that collects, evaluates and stores verification and validation data, and shows how it can be used to perform V&V and UQ, leveraging collaboration and sharing of resources to support existing engineering and licensing procedures as well as science-based V&V and UQ processes. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation (NE-KAMS) is being developed at the Idaho National Laboratory in conjunction with Bettis Laboratory, Sandia National Laboratories, Argonne National Laboratory, Utah State University and others with the objective of establishing a comprehensive and web-accessible knowledge base to provide V&V and UQ resources for M&S for nuclear reactor design, analysis and licensing. The knowledge base will serve as an important resource for technical exchange and collaboration that will enable credible and reliable computational models and simulations for application to nuclear power. NE-KAMS will serve as a valuable resource for the nuclear industry, academia, the national laboratories, the U.S. Nuclear Regulatory Commission (NRC) and the public and will help ensure the safe, economical and reliable operation of existing and future nuclear reactors.

Greg Weirs; Hyung Lee

2011-09-01T23:59:59.000Z

372

REDUCTION OF INHERENT MERCURY EMISSIONS IN PC COMBUSTION  

DOE Green Energy (OSTI)

Mercury emission compliance is one of the major potential challenges raised by the 1990 Clean Air Act Amendments. Simple ways of controlling emissions have not been identified. The variability in the field data suggests that inherent mercury emissions may be reduced if the source of this inherent capture can be identified and controlled. The key mechanisms appear to involve the oxidation of the mercury to Hg{sup 2}, generally producing the more reactive HgCl{sub 2} , followed by its capture by certain components of the fly ash or char. This research focuses on identifying the rate-limiting steps associated with the oxidation step. Work in this reporting period focused on the development and application of a kinetics model to the oxidation data developed in the present program and literature data under MSW conditions. The results indicate that the pathway Hg + Cl = HgCl followed by HgCl + HCl = HgCl{sub 2} + H predominates over Hg + Cl{sub 2} under high-temperature conditions. This primarily occurs because Cl{sub 2} concentrations are too low under the present conditions to contribute significantly.

John C. Kramlich; Rebecca N. Sliger; David J. Going

1999-08-06T23:59:59.000Z

373

Two dose-estimation models CSA-N288.1 and Nureg 1.109, 1.113 - compared for chronic aquatic releases from nuclear facilities  

E-Print Network (OSTI)

Both the Canadian Standards Association (CSA) and the United States Nuclear Regulatory Commission (US-NRC) have published guidelines for the calculation of doses to the public due to emissions from nuclear facilities. In the sale of CANDU reactors overseas, either of these guidelines may be used as part of the approval process in the recipient country. This study compares the aquatic exposure pathways described in the guidelines. These include direct consumption of contaminated water and food, and exposure to contaminated sediments. The CSA and US-NRC guidelines for estimating dilution of aquatic emissions are of a general nature and the choice of model used to quantify dilution is left to the user. The models prescribed for the different exposure pathways by these two regulatory guides are similar in many attributes. Many of the recommended parameter values are identical and many of the formulations are either identical, or become identical under general conditions. However, despite these similarities, there...

Sheppard, S C; Peterson, S R

2000-01-01T23:59:59.000Z

374

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

375

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)

2010-07-13T23:59:59.000Z

376

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

377

Development of 5kWh Flywheel Energy Storage System Using MATLAB/xPC Target  

Science Conference Proceedings (OSTI)

A 5kWh class FESS(Flywheel Energy Storage System) with the operating speed range of 9,000~15,000rpm has been developed. The system consists of a composite flywheel rotor, active magnetic bearings, a motor/generator and its controller. Because Active ... Keywords: FESS, Magnetic bearing, rotor dynamics, Imbalace Response, xPC Target

Cheol Hoon Park; Sang-Kyu Choi; Young Su Son; Young Hee Han

2009-03-01T23:59:59.000Z

378

Phone n' Computer: teaming up an information appliance with a PC  

Science Conference Proceedings (OSTI)

Facing the ever growing complexity and usability problems of the PC, some propose specialized computers as a solution, while others argue that such "information appliances" are unnecessary. Rather than pitting information appliances and PCs against each ... Keywords: Device integration, Information appliance, Phone

Min Yin; Jeffrey Pierce; Shumin Zhai

2010-10-01T23:59:59.000Z

379

A Portable, PC-Based System for Making Optical and Electromagnetic Measurements of Lightning  

Science Conference Proceedings (OSTI)

A digital video camcorder, a four-channel analog-to-digital (A/D) converter, and a GPS time/position receiver have been interfaced to a portable personal computer (PC) to provide a mobile data-collection platform for making precise time-...

Nathan G. Parker; E. Philip Krider

2003-06-01T23:59:59.000Z

380

PC-Cluster-Based Real-Time Simulation of an 8 synchronous machines network with HVDC link using  

E-Print Network (OSTI)

Abstract—In this paper, we detail the real-time simulation results of a medium-sized network composed of 8 synchronous machines and an HVDC link. The model is composed of two Kundur-like 4 machines networks connected together with a 12pulse HVDC link. The complete network is modeled with SimPowerSystems with ARTEMIS real-time plug-in and is simulated in real-time on a RT-LAB InfiniBand PC-cluster composed of 3 dual-CPU dual-core Opteron PCs. The network model includes the HVDC control and protection systems as well as the synchronous machine regulators and power stabilizers. It also includes typical fault simulation capability like HVDC DC faults, thyristor misfires and AC faults. This model is excellent to study the complex interactions between an HVDC link and AC network under normal and transient conditions. The real-time simulation is controlled and monitored with a TestDrive interface from Opal-RT. This interface, based on LabView, permits easy monitoring and control of the complete system and enables Python-based scripting for automated tests. The proposed simulator can be interfaced with external equipments and controllers by direct reconfiguration of a FPGA I/O card with Xilinx System Generator blockset.

Christian Dufour; Jean-nicolas Paquin; Vincent Lapointe; Jean Bélanger; Loic Schoen

2007-01-01T23:59:59.000Z

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.


381

Formation of Nuclear Disks and Supermassive Black Hole Binaries in Multi-Scale Hydrodynamical Galaxy Mergers  

E-Print Network (OSTI)

(Abridged) We review the results of the first multi-scale, hydrodynamical simulations of mergers between galaxies with central supermassive black holes (SMBHs) to investigate the formation of SMBH binaries in galactic nuclei. We demonstrate that strong gas inflows produce nuclear disks at the centers of merger remnants whose properties depend sensitively on the details of gas thermodynamics. In numerical simulations with parsec-scale spatial resolution in the gas component and an effective equation of state appropriate for a starburst galaxy, we show that a SMBH binary forms very rapidly, less than a million years after the merger of the two galaxies. Binary formation is significantly suppressed in the presence of a strong heating source such as radiative feedback by the accreting SMBHs. We also present preliminary results of numerical simulations with ultra-high spatial resolution of 0.1 pc in the gas component. These simulations resolve the internal structure of the resulting nuclear disk down to parsec scales and demonstrate the formation of a central massive object (~ 10^8 Mo) by efficient angular momentum transport. This is the first time that a radial gas inflow is shown to extend to parsec scales as a result of the dynamics and hydrodynamics involved in a galaxy merger, and has important implications for the fueling of SMBHs. Due to the rapid formation of the central clump, the density of the nuclear disk decreases significantly in its outer region, reducing dramatically the effect of dynamical friction and leading to the stalling of the two SMBHs at a separation of ~1 pc. We discuss how the orbital decay of the black holes might continue in a more realistic model which incorporates star formation and the multi-phase nature of the ISM.

Lucio Mayer; Stelios Kazantzidis; Andres Escala

2008-07-22T23:59:59.000Z

382

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

383

Parallel database processing on a 100 Node PC cluster: cases for decision support query processing and data mining  

Science Conference Proceedings (OSTI)

We developed a PC cluster system consists of 100 PCs. Each PC employs the 200MHz Pentium Pro CPU and is connected with others through an ATM switch. We picked up two kinds of data intensive applications. One is decision support query processing. And ...

Takayuki Tamura; Masato Oguchi; Masaru Kitsuregawa

1997-11-01T23:59:59.000Z

384

Nuclear Reactions  

NLE Websites -- All DOE Office Websites (Extended Search)

Reactions Nuclear reactions and nuclear scattering are used to measure the properties of nuclei. Reactions that exchange energy or nucleons can be used to measure the energies of...

385

Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE))

Nuclear Safety information site that provides assistance and resources to field elements in implementation of requirements and resolving nuclear safety, facility safety, and quality assurance issues.

386

Nuclear Materials  

Science Conference Proceedings (OSTI)

Materials and Fuels for the Current and Advanced Nuclear Reactors III ... response of oxide ceramics for nuclear applications through experiment, theory, and ...

387

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

NLE Websites -- All DOE Office Websites (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

388

A historical application of social amplification of risk model: Economic impacts of risk events at nuclear weapons facilities?  

Science Conference Proceedings (OSTI)

Public perceptions of risk have proven to be a critical barrier to the federal government`s extensive, decade-long, technical and scientific effort to site facilities for the interim storage and permanent disposal of high-level radioactive waste (HLW). The negative imagery, fear, and anxiety that are linked to ``nuclear`` and ``radioactive`` technologies, activities, and facilities by the public originate from the personal realities and experiences of individuals and the information they receive. These perceptions continue to be a perplexing problem for those responsible for making decisions about federal nuclear waste management policies and programs. The problem of understanding and addressing public perceptions is made even more difficult because there are decidedly different opinions about HLW held by the public and nuclear industry and radiation health experts.

Metz, W.C.

1996-12-31T23:59:59.000Z

389

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

390

Accomplishments | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

models and high-fidelity databases were developed and implemented to support National Technical Nuclear Forensics (NTNF) activities. In FY2010, ASC continued to...

391

Nuclear Forensics | More Science | ORNL  

NLE Websites -- All DOE Office Websites (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

392

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

393

Modular Modeling System (MMS): A Code for the Dynamic Simulation of Fossil and Nuclear Power Plants, Volume 2: Programmer's Manual  

Science Conference Proceedings (OSTI)

Now complete and fully documented, the MMS code is available for the dynamic simulation of both fossil-fired and nuclear power plants. The broad range of applications, from troubleshooting new designs to analysis of startup tests, has made this easy-to use code a utility standard since its first-stage release in 1983.

1987-05-01T23:59:59.000Z

394

Modular Modeling System (MMS): A Code for the Dynamic Simulation of Fossil and Nuclear Power Plants, Volume 1: Theory Manual  

Science Conference Proceedings (OSTI)

Now complete and fully documented, the MMS code is available for the dynamic simulation of both fossil-fired and nuclear power plants. The broad range of applications, from troubleshooting new designs to analysis of startup tests, has made this easy-to use code a utility standard since its first-stage release in 1983.

1987-04-01T23:59:59.000Z

395

INTERDICTION MODELING FOR SMUGGLED NUCLEAR MATERIAL Nedialko B. Dimitrov, Marc A. Gonzalez, Dennis P. Michalopoulos, David P. Morton,  

E-Print Network (OSTI)

1990s, Russia inherited roughly 600- 850 metric tons of highly-enriched uranium (HEU) and plutonium [9% of these involved nuclear material and 18 involved weapons-grade uranium or plutonium. Sometimes a smuggler's intent (SNM), i.e., weapons-grade plutonium (WGPu), reactor-grade plutonium, natural uranium, low

Morton, David

396

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

397

Amid all the IGCC talk, PC remains the go-to-guy  

SciTech Connect

Globally, more than 100 sites have integrated gasification combined cycle (IGCC) installations, including more than a dozen locations that produce power. IGCC 'buzz' has now reached a crescendo, as evidenced by attendance of over 700 at the recent Gasification Technologies conference. However, coal plants currently being developed in the United States are mostly subcritical or supercritical pulverized coal plants, with a handful of CFBs. The article describes some recent developments in IGCC and goes on to address the debate between IGCC and PC. IGCC has the inherent ability to capture CO{sub 2} before combustion, but PC may well be able to capture just as well CO{sub 2} post combustion. More work is needed on a sequestering carbon in the ground, according to Nancy Mohn and others whose opinions are reported. 1 photo.

Blankinship, S.

2006-04-15T23:59:59.000Z

398

PERSPECTIVES OF NUCLEAR PHYSICS  

E-Print Network (OSTI)

The organizers of this meeting have asked me to present perspectives of nuclear physics. This means to identify the areas where nuclear physics will be expanding in the next future. In six chapters a short overview of these areas will be given, where I expect that nuclear physics will develop quite fast: (1) Quantum Chromodynamics and effective field theories in the confinement region. (2) Nuclear structure at the limits. (3) High energy heavy ion collisions. (4) Nuclear astrophysics. (5) Neutrino physics. (6) Test of physics beyond the standard model by rare processes. After a survey over these six points I will pick out a few topics where I will go more in details. There is no time to give for all six points detailed examples. I shall discuss the following examples of the six topics mentionned above: (1) The perturbative chiral quark model and the nucleon ?-term. (2) VAMPIR (Variation After Mean field Projection In Realistic model spaces and with realistic forces) as an example of the nuclear structure renaissance. (3) Measurement of important astrophysical nuclear reactions in the Gamow peak. (4) The solar neutrino problem. As examples for testing new physics beyond the standard model by rare processes I had prepared to speak about the measurement of the electric neutron dipole moment and of the neutrinoless double beta decay. But the time is limited and so I have to skip these points, although they are extremely interesting.

Amand Faessler

2002-01-01T23:59:59.000Z

399

Sodium Reaction Experimental Test Facility (SRETF) - Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Form Modeling Departments Engineering Analysis Nuclear Systems Analysis Research & Test Reactor Nonproliferation and National Security Detection & Diagnostic Systems...

400

Chemical Sciences and Engineering - Nuclear and Environmental...  

NLE Websites -- All DOE Office Websites (Extended Search)

Simulation & Equipment Design * Members * Overview * Chemical Process Models * Chemistry at Interfaces Nuclear & Environmental Processes Home Process Simulation and Equipment...

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

Materials Development for Nuclear Applications and Extreme ...  

Science Conference Proceedings (OSTI)

Presentations that combine experiment with theory, modeling and simulation to enhance our understanding of ... Lifetime extension of existing nuclear reactors

402

Materials Development and Degradation Management for Nuclear ...  

Science Conference Proceedings (OSTI)

Mar 31, 2013 ... Presentations that combine experiment with theory, modeling and ... for Accident Tolerant Fuel Cladding in Commercial Nuclear Reactors.

403

Accelerated Materials Evaluation for Nuclear Application Utilizing ...  

Science Conference Proceedings (OSTI)

Jul 15, 2013... of accelerated nuclear materials testing for fission and fusion reactors. Presentations combining experiment with theory, modeling and ...

404

VENTURE/PC manual: A multidimensional multigroup neutron diffusion code system. Version 3  

SciTech Connect

VENTURE/PC is a recompilation of part of the Oak Ridge BOLD VENTURE code system, which will operate on an IBM PC or compatible computer. Neutron diffusion theory solutions are obtained for multidimensional, multigroup problems. This manual contains information associated with operating the code system. The purpose of the various modules used in the code system, and the input for these modules are discussed. The PC code structure is also given. Version 2 included several enhancements not given in the original version of the code. In particular, flux iterations can be done in core rather than by reading and writing to disk, for problems which allow sufficient memory for such in-core iterations. This speeds up the iteration process. Version 3 does not include any of the special processors used in the previous versions. These special processors utilized formatted input for various elements of the code system. All such input data is now entered through the Input Processor, which produces standard interface files for the various modules in the code system. In addition, a Standard Interface File Handbook is included in the documentation which is distributed with the code, to assist in developing the input for the Input Processor.

Shapiro, A.; Huria, H.C.; Cho, K.W. [Cincinnati Univ., OH (United States)

1991-12-01T23:59:59.000Z

405

Nuclear Analytical Chemistry Portal  

Science Conference Proceedings (OSTI)

NIST Home > Nuclear Analytical Chemistry Portal. Nuclear Analytical Chemistry Portal. ... see all Nuclear Analytical Chemistry news ... ...

2010-08-02T23:59:59.000Z

406

Transactions of the fourth symposium on space nuclear power systems  

DOE Green Energy (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

407

Transactions of the fifth symposium on space nuclear power systems  

Science Conference Proceedings (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

408

ON THE MICROSCOPIC AND MACROSCOPIC ASPECTS OF NUCLEAR STRUCTURE WITH APPLICATIONS TO SUPERHEAVY NUCLEI  

E-Print Network (OSTI)

Liquid-Drop Theory of Nuclear Fission, Lawrence Radiationemployed in the study of nuclear fission. determined some ofusual liquid drop model of nuclear fission assumes a charged

Tsang, Chin-Fu.

2010-01-01T23:59:59.000Z

409

Nuclear Instruments and Methods in Physics Research A 582 (2007) 629637 Monte Carlo and analytical models of neutron detection with organic  

E-Print Network (OSTI)

unfolding, which have a variety of applications, including nuclear nonproliferation and homeland security materials in applications such as nuclear nonproliferation, homeland security, and basic physics research

Pázsit, Imre

410

Future of Nuclear Data for Nuclear Astrophysics  

Science Conference Proceedings (OSTI)

Nuclear astrophysics is an exciting growth area in nuclear science. Because of the enormous nuclear data needs of this field

Michael S. Smith

2005-01-01T23:59:59.000Z

411

Nuclear Detonation Detection | National Nuclear Security Administratio...  

National Nuclear Security Administration (NNSA)

Nuclear Nonproliferation Program Offices > Office of Nonproliferation Research & Development > Nuclear Detonation Detection Nuclear Detonation Detection Develop, Demonstrate, and...

412

Countering Nuclear Terrorism | National Nuclear Security Administratio...  

NLE Websites -- All DOE Office Websites (Extended Search)

Countering Nuclear Terrorism | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

413

Chernobyl Nuclear Accident | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

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

414

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

SciTech Connect

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

415

Technosocial predictive analytics for illicit nuclear trafficking  

Science Conference Proceedings (OSTI)

Illicit nuclear trafficking networks are a national security threat. These networks can directly lead to nuclear proliferation, as state or nonstate actors attempt to identify and acquire nuclear weapons-related expertise, technologies, components, and ... Keywords: analytical gaming, decision making, illicit trafficking, knowledge management, modeling, nuclear proliferation, predictive analytics

Antonio Sanfilippo; Scott Butner; Andrew Cowell; Angela Dalton; Jereme Haack; Sean Kreyling; Rick Riensche; Amanda White; Paul Whitney

2011-03-01T23:59:59.000Z

416

Nuclear Science  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

417

SAFER-PC Version 2.2, Stress and Fracture Evaluation of Rotors - Personal Computer, Version 2.2  

Science Conference Proceedings (OSTI)

The Stress and Fracture Evaluation of RotorsPersonal Computer (SAFER-PC), Version 2.2 software will evaluate the remaining life of steam turbine and generator rotors. Version 2.2 is an upgrade of existing analysis software. SAFER-PC combines transient thermal-elastic finite element stress analysis, fracture mechanics, material property data, and the clustering and linking of surface defects identified from nondestructive examination (NDE) data to assess remaining usable life of steam turbine or generator...

2006-12-22T23:59:59.000Z

418

Nuclear forces  

Science Conference Proceedings (OSTI)

These lectures present an introduction into the theory of nuclear forces. We focus mainly on the modern approach

2013-01-01T23:59:59.000Z

419

2002 EIA Models Directory  

U.S. Energy Information Administration (EIA)

The Personal Computer International Nuclear Model (PCINM) is a deterministic model used by the Energy Information Administration (EIA) to project ...

420

Nuclear weapons, nuclear effects, nuclear war  

SciTech Connect

This paper provides a brief and mostly non-technical description of the militarily important features of nuclear weapons, of the physical phenomena associated with individual explosions, and of the expected or possible results of the use of many weapons in a nuclear war. Most emphasis is on the effects of so-called ``strategic exchanges.``

Bing, G.F.

1991-08-20T23:59:59.000Z

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

Nuclear Cluster Physics  

Science Conference Proceedings (OSTI)

Predictive power of theory needs good models and accurate calculation methods to solve the Schroedinger equations of the systems concerned. We present some examples of successful predictions based on the nuclear cluster models of light nuclei and hypernuclei and on the calculation methods that have been developed by Kyushu group.

Kamimura, Masayasu [RIKEN Nishina Center, RIKEN, Wako 351-0198 (Japan); Department of Physics, Kyushu University, Fukuoka 812-8581 (Japan)

2011-05-06T23:59:59.000Z

422

(Mfactor: A PC-based program for general spectral mismatch corrections)  

DOE Green Energy (OSTI)

Reference cells are frequently used to determine incident light intensity during solar cell performance measurements. A problem arises when comparisons are made between cells tested under different spectral irradiances (spectra). This paper describes an IBM-PC compatible computer program, called Mfactor, developed in the Photovoltaic Device Measurement Laboratory (PDML) at Sandia that uses a generalized procedure for making spectral mismatch corrections. The program operation is described, and several examples are given. A new method to calibrate primary reference cells using a National Institute of Standards and Technology (NIST) lamp in conjunction with Mfactor is also presented. 4 refs., 4 figs., 6 tabs.

Not Available

1991-01-01T23:59:59.000Z

423

Atomistic Simulations of Radiation Effects in Ceramics for Nuclear ...  

Science Conference Proceedings (OSTI)

This work is supported by the DOE Nuclear Energy Advanced Modeling and ... Simulations of Radiation Effects in Ceramics for Nuclear Waste Disposal.

424

Mark Peters testifies before Congress on nuclear energy | Argonne...  

NLE Websites -- All DOE Office Websites (Extended Search)

energy ---Nuclear energy modeling & simulation ---Nuclear fuel cycle ---Reactors -Energy usage --Energy storage ---Batteries ----Lithium-ion batteries ----Lithium-air...

425

Materials for Nuclear Power: Digital Resource Center Text Topic - TMS  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Office of Nuclear Energy and Office of Advanced Scientific Computing Research. Simulation and Modeling for Advanced Nuclear Energy ...

426

Materials for Nuclear Power: Digital Resource Center - PDF ...  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Office of Nuclear Energy and Office of Advanced Scientific Computing Research. Simulation and Modeling for Advanced Nuclear Energy ...

427

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

428

Perspectives of Nuclear Physics  

E-Print Network (OSTI)

The organizers of this meeting have asked me to present perspectives of nuclear physics. This means to identify the areas where nuclear physics will be expanding in the next future. In six chapters a short overview of these areas will be given, where I expect that nuclear physics willdevelop quite fast: A. Quantum Chromodynamics and effective field theories in the confinement region; B. Nuclear structure at the limits; C. High energy heavy ion collisions; D. Nuclear astrophysics; E. Neutrino physics; F. Test of physics beyond the standard model by rare processes. After a survey over these six points I will pick out a few topics where I will go more in details. There is no time to give for all six points detailed examples. I shall discuss the following examples of the six topics mentionned above: 1. The perturbative chiral quark model and the nucleon $\\Sigma$-term, 2. VAMPIR (Variation After Mean field Projection In Realistic model spaces and with realistic forces) as an example of the nuclear structure renais...

Faessler, A

2002-01-01T23:59:59.000Z

429

Nuclear Deterrence  

NLE Websites -- All DOE Office Websites (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

430

An overlooked brown dwarf neighbour (T7.5 at d~5pc) of the Sun and two further T dwarfs at about 10pc  

E-Print Network (OSTI)

Although many new brown dwarf (BD) neighbours have been recently discovered thanks to new sky surveys in the mid- and near-infrared (MIR, NIR), their numbers are still more than five times lower than those of stars in the same volume. We aim at detecting and classifying new BDs to eventually complete their census in the immediate Solar neighbourhood. We combine multi-epoch data from sky surveys at different wavelengths to detect BD neighbours of the Sun by their high proper motion (HPM). We concentrate at relatively bright MIR (w2<13.5) BD candidates from WISE expected to be so close to the Sun that they may also be seen in older NIR (2MASS, DENIS) or even red optical (SDSS i- and z-band, SSS I-band) surveys. With low-resolution NIR spectroscopy we classify the new BDs and estimate their distances and velocities. We have discovered the HPM (pm~470mas/yr) T7.5 dwarf WISE J0521+1025 at d=5.0+-1.3pc from the Sun, and two early-T dwarfs WISE J0457-0207 (T2) and WISE J2030+0749 (T1.5) with proper motions of ~12...

Bihain, Gabriel; Storm, Jesper; Schnurr, Olivier

2013-01-01T23:59:59.000Z

431

A 500 pc filamentary gas wisp in the disk of the Milky Way  

E-Print Network (OSTI)

Star formation occurs in molecular gas. In previous studies, the structure of the molecular gas has been studied in terms of molecular clouds, but has been overlooked beyond the cloud scale. We present an observational study of the molecular gas at 49.5 degree = 500 pc) filamentary gas wisp. This has a large physical extent and a velocity dispersion of ~5 km/s. The eastern part of the filamentary gas wisp is located ~130 pc above the Galactic disk (which corresponds to 1.5-4 e-folding scale-heights), and the total mass of the gas wisp is >= 1 X 10^5 M_sun. It is composed of two molecular clouds and an expanding bubble. The velocity structure of the gas wisp can be explained as a smooth quiescent component disturbed by the expansion of a bubble. That the length of the gas wisp exceeds by much the thickness of the molecular disk of the Milky Way is consistent with the cloud-formation scenario in which the gas is cold prior to the formation of molecular clouds. Star formation in the filamentary gas wisp occurs a...

Li, Guang-Xing; Menten, Karl; Belloche, Arnaud

2013-01-01T23:59:59.000Z

432

Analysis of Surface Leaching Processes in Vitrified High-Level Nuclear Wastes Using In-Situ Raman Imaging and Atomistic Modeling - Final Report  

SciTech Connect

The in situ analysis of surface conditions of vitrified nuclear wastes can provide an important check of the burial status of radioactive objects without risk of radiation exposure. Raman spectroscopy was initially chosen as the most promising method for testing the surface conditions of glasses undergoing chemical corrosion, and was used extensively during the first year. However, it was determined that infrared reflection spectroscopy was better suited to this particular need and was used for the remaining two years to investigate the surface corrosion behavior of model silicate glasses for extension to nuclear waste glasses. The developed methodology is consistent with the known theory of optical propagation of dielectric media and uses the Kramers-Kronig formalism. The results show that it is possible to study the corrosion of glass by analyzing the glass surface using reflection fast Fourier infrared measurements and the newly developed ''dispersion analysis method.'' The data show how this analysis can be used to monitor the corrosion behavior of vitrified waste glasses over extended periods of storage.

Simmons, Joseph H.

2001-04-24T23:59:59.000Z

433

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

434

United States Nuclear Regulatory Commission  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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.

435

Development and Testing of a Groundwater Management Model for the Faultless Underground Nuclear Test, Central Nevada Test Area  

DOE Green Energy (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

436

Dipole rescattering and the nuclear structure function  

Science Conference Proceedings (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

437

Comparison of MELCOR modeling techniques and effects of vessel water injection on a low-pressure, short-term, station blackout at the Grand Gulf Nuclear Station  

SciTech Connect

A fully qualified, best-estimate MELCOR deck has been prepared for the Grand Gulf Nuclear Station and has been run using MELCOR 1.8.3 (1.8 PN) for a low-pressure, short-term, station blackout severe accident. The same severe accident sequence has been run with the same MELCOR version for the same plant using the deck prepared during the NUREG-1150 study. A third run was also completed with the best-estimate deck but without the Lower Plenum Debris Bed (BH) Package to model the lower plenum. The results from the three runs have been compared, and substantial differences have been found. The timing of important events is shorter, and the calculated source terms are in most cases larger for the NUREG-1150 deck results. However, some of the source terms calculated by the NUREG-1150 deck are not conservative when compared to the best-estimate deck results. These results identified some deficiencies in the NUREG-1150 model of the Grand Gulf Nuclear Station. Injection recovery sequences have also been simulated by injecting water into the vessel after core relocation started. This marks the first use of the new BH Package of MELCOR to investigate the effects of water addition to a lower plenum debris bed. The calculated results indicate that vessel failure can be prevented by injecting water at a sufficiently early stage. No pressure spikes in the vessel were predicted during the water injection. The MELCOR code has proven to be a useful tool for severe accident management strategies.

Carbajo, J.J.

1995-06-01T23:59:59.000Z

438

Experiments to investigate direct containment heating phenomena with scaled models of the Zion Nuclear Power Plant in the Surtsey Test Facility  

SciTech Connect

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

439

Nuclear Reactors  

NLE Websites -- All DOE Office Websites (Extended Search)

Reactors Nuclear reactors created not only large amounts of plutonium needed for the weapons programs, but a variety of other interesting and useful radioisotopes. They produced...

440

Nuclear Astrophysics  

Science Conference Proceedings (OSTI)

I review progress that has been made in nuclear astrophysics over the past few years and summarize some of the questions that remain. Topics selected include solar neutrinos

W. C. Haxton

2006-01-01T23:59:59.000Z

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.


441

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Table 17. Purchases of enrichment services by owners and operators of U.S. civilian nuclear power reactors by contract type in delivery year, 2012

442

Nuclear Weapons  

NLE Websites -- All DOE Office Websites (Extended Search)

nuclear science that has had a significant global influence. Following the observation of fission products of uranium by Hahn and Strassmann in 1938, a uranium fission weapon...

443

NUCLEAR ENERGY  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

could improve the economic and safety performance of these advanced reactors. Nuclear power can reduce GHG emissions from electricity production and possibly in co-generation...

444

U.S. Nuclear Regulatory Commission Extremely Low Probability of Rupture pilot study : xLPR framework model user's guide.  

Science Conference Proceedings (OSTI)

For the U.S. Nuclear Regulatory Commission (NRC) Extremely Low Probability of Rupture (xLPR) pilot study, Sandia National Laboratories (SNL) was tasked to develop and evaluate a probabilistic framework using a commercial software package for Version 1.0 of the xLPR Code. Version 1.0 of the xLPR code is focused assessing the probability of rupture due to primary water stress corrosion cracking in dissimilar metal welds in pressurizer surge nozzles. Future versions of this framework will expand the capabilities to other cracking mechanisms, and other piping systems for both pressurized water reactors and boiling water reactors. The goal of the pilot study project is to plan the xLPR framework transition from Version 1.0 to Version 2.0; hence the initial Version 1.0 framework and code development will be used to define the requirements for Version 2.0. The software documented in this report has been developed and tested solely for this purpose. This framework and demonstration problem will be used to evaluate the commercial software's capabilities and applicability for use in creating the final version of the xLPR framework. This report details the design, system requirements, and the steps necessary to use the commercial-code based xLPR framework developed by SNL.

Kalinich, Donald A.; Sallaberry, Cedric M.; Mattie, Patrick D.

2010-12-01T23:59:59.000Z

445

Modeling the effects of uncertainty on fear of nuclear waste: Differences among science, business and environmental group members  

SciTech Connect

This paper analyzes the relationships between the subjective assessment of riskiness of managing nuclear waste and the level of certainty regarding the assessment. Uncertainty can be operationalized in two ways. The direct approach asks a person to assess their own subjective beliefs about a potential hazard. The indirect approach assesses how readily an individual will change his or her beliefs when confronted with new information that conflicts with prior beliefs. This paper tests for the relationships between these two distinct operationalizations of uncertainty and overall assessments of the risks posed by radioactive wastes. First we analyze the relationships between stated levels of uncertainty about the effects of radiation on the level of perceived risks from radioactive wastes. Second, we assess the linkage between willingness to alter prior beliefs about the risks of radioactive wastes in response to new information provided by ``a neutral source`` (or responsiveness of beliefs) and uncertainty. Using data taken from random mail surveys of members of scientific, business, and environmental groups in Colorado and New Mexico in the summer of 1990, we test hypotheses that (a) greater uncertainty is associated with greater perceived risks, and (b) greater responsiveness of beliefs to new information is associated with greater uncertainty. The import of these hypotheses concerns the dynamics of uncertainty in controversial technical policy issues, wherein perceived risks are a primary ingredient in policy positions taken by participants in policy disputes.

Bassett, G. [Illinois Univ., Chicago, IL (United States). Dept. of Economics]|[Argonne National Lab., IL (United States); Jenkins-Smith, H. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Political Science]|[Argonne National Lab., IL (United States)

1992-10-01T23:59:59.000Z

446

Modeling the effects of uncertainty on fear of nuclear waste: Differences among science, business and environmental group members  

SciTech Connect

This paper analyzes the relationships between the subjective assessment of riskiness of managing nuclear waste and the level of certainty regarding the assessment. Uncertainty can be operationalized in two ways. The direct approach asks a person to assess their own subjective beliefs about a potential hazard. The indirect approach assesses how readily an individual will change his or her beliefs when confronted with new information that conflicts with prior beliefs. This paper tests for the relationships between these two distinct operationalizations of uncertainty and overall assessments of the risks posed by radioactive wastes. First we analyze the relationships between stated levels of uncertainty about the effects of radiation on the level of perceived risks from radioactive wastes. Second, we assess the linkage between willingness to alter prior beliefs about the risks of radioactive wastes in response to new information provided by a neutral source'' (or responsiveness of beliefs) and uncertainty. Using data taken from random mail surveys of members of scientific, business, and environmental groups in Colorado and New Mexico in the summer of 1990, we test hypotheses that (a) greater uncertainty is associated with greater perceived risks, and (b) greater responsiveness of beliefs to new information is associated with greater uncertainty. The import of these hypotheses concerns the dynamics of uncertainty in controversial technical policy issues, wherein perceived risks are a primary ingredient in policy positions taken by participants in policy disputes.

Bassett, G. (Illinois Univ., Chicago, IL (United States). Dept. of Economics Argonne National Lab., IL (United States)); Jenkins-Smith, H. (New Mexico Univ., Albuquerque, NM (United States). Dept. of Political Science Argonne National Lab., IL (United States))

1992-10-01T23:59:59.000Z

447

Nuclear Weapons Journal Archive  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Weapons Journal Archive Nuclear Weapons Journal The Nuclear Weapons Journal ceased publication after Issue 2, 2009. Below are Nuclear Weapons Journal archived issues. Issue...

448

Nonreactor Nuclear Facilities Division  

NLE Websites -- All DOE Office Websites (Extended Search)

role in developing science and technology for nuclear power programs, nuclear propulsion, nuclear medicine, and the nation's nuclear weapon program among others. Many...

449

U.S. Department of Energy DOE/PC90542-T1 THE REMOVAL OF SO  

NLE Websites -- All DOE Office Websites (Extended Search)

U.S. Department of Energy DOE/PC90542-T1 THE REMOVAL OF SO 2 USING GAS SUSPENSION ABSORPTION TECHNOLOGY DEMONSTRATION PROJECT A DOE ASSESSMENT Prepared by: The Office of Clean Coal technology Pittsburgh Energy Technology Center Pittsburgh, PA 15236 September 1996 EXECUTIVE SUMMARY This document serves as a DOE post-project assessment of a project in Round 3 of the Clean Coal Technology (CCT) Demonstration Program titled, "Demonstration of SO 2 Removal Using Gas Suspension Absorption Technology." In October 1990, AirPol Inc. entered into a cooperative agreement to conduct the study, with the Tennessee Valley Authority (TVA) as the host and co-sponsor. The 10 MWe plant scale demonstration was conducted from November 1992 to March 1994 at TVA's National Center for Emissions

450

The role of the cytoskeleton in volume regulation and beading transitions in PC12 neurites  

E-Print Network (OSTI)

We present investigations on volume regulation and beading shape transitions in PC12 neurites conducted using a flow-chamber technique. By disrupting the cell cytoskeleton with specific drugs we investigate the role of its individual components in the volume regulation response. We find that microtubule disruption increases both swelling rate and maximum volume attained, but does not affect the ability of the neurite to recover its initial volume. In addition, investigation of axonal beading --also known as pearling instability-- provides additional clues on the mechanical state of the neurite. We conclude that the initial swelling phase is mechanically slowed down by microtubules, while the volume recovery is driven by passive diffusion of osmolites. Our experiments provide a framework to investigate the role of cytoskeletal mechanics in volume homeostasis.

Pablo Fernandez; Pramod A. Pullarkat

2010-06-08T23:59:59.000Z

451

Expert PC Troubleshooter With Fuzzy-Logic And Self-Learning Support  

E-Print Network (OSTI)

Expert systems use human knowledge often stored as rules within the computer to solve problems that generally would entail human intelligence. Today, with information systems turning out to be more pervasive and with the myriad advances in information technologies, automating computer fault diagnosis is becoming so fundamental that soon every enterprise has to endorse it. This paper proposes an expert system called Expert PC Troubleshooter for diagnosing computer problems. The system is composed of a user interface, a rule-base, an inference engine, and an expert interface. Additionally, the system features a fuzzy-logic module to troubleshoot POST beep errors, and an intelligent agent that assists in the knowledge acquisition process. The proposed system is meant to automate the maintenance, repair, and operations (MRO) process, and free-up human technicians from manually performing routine, laborious, and timeconsuming maintenance tasks. As future work, the proposed system is to be parallelized so as to boo...

Bassil, Youssef

2012-01-01T23:59:59.000Z

452

Theoretical studies in nuclear reactions and nuclear structure. Progress report  

Science Conference Proceedings (OSTI)

Research in the Maryland Nuclear Theory Group focusses on problems in four basic areas of current relevance. Hadrons in nuclear matter; the structure of hadrons; relativistic nuclear physics and heavy ion dynamics and related processes. The section on hadrons in nuclear matter groups together research items which are aimed at exploring ways in which the properties of nucleons and the mesons which play a role in the nuclear force are modified in the nuclear medium. A very interesting result has been the finding that QCD sum rules supply a new insight into the decrease of the nucleon`s mass in the nuclear medium. The quark condensate, which characterizes spontaneous chiral symmetry breaking of the late QCD vacuum, decreases in nuclear matter and this is responsible for the decrease of the nucleon`s mass. The section on the structure of hadrons contains progress reports on our research aimed at understanding the structure of the nucleon. Widely different approaches are being studied, e.g., lattice gauge calculations, QCD sum rules, quark-meson models with confinement and other hedgehog models. A major goal of this type of research is to develop appropriate links between nuclear physics and QCD. The section on relativistic nuclear physics represents our continuing interest in developing an appropriate relativistic framework for nuclear dynamics. A Lorentz-invariant description of the nuclear force suggests a similar decrease of the nucleon`s mass in the nuclear medium as has been found from QCD sum rules. Work in progress extends previous successes in elastic scattering to inelastic scattering of protons by nuclei. The section on heavy ion dynamics and related processes reports on research into the e{sup +}e{sup {minus}} problem and heavy ion dynamics.

Not Available

1992-05-01T23:59:59.000Z

453

Theoretical studies in nuclear reactions and nuclear structure  

Science Conference Proceedings (OSTI)

Research in the Maryland Nuclear Theory Group focusses on problems in four basic areas of current relevance. Hadrons in nuclear matter; the structure of hadrons; relativistic nuclear physics and heavy ion dynamics and related processes. The section on hadrons in nuclear matter groups together research items which are aimed at exploring ways in which the properties of nucleons and the mesons which play a role in the nuclear force are modified in the nuclear medium. A very interesting result has been the finding that QCD sum rules supply a new insight into the decrease of the nucleon's mass in the nuclear medium. The quark condensate, which characterizes spontaneous chiral symmetry breaking of the late QCD vacuum, decreases in nuclear matter and this is responsible for the decrease of the nucleon's mass. The section on the structure of hadrons contains progress reports on our research aimed at understanding the structure of the nucleon. Widely different approaches are being studied, e.g., lattice gauge calculations, QCD sum rules, quark-meson models with confinement and other hedgehog models. A major goal of this type of research is to develop appropriate links between nuclear physics and QCD. The section on relativistic nuclear physics represents our continuing interest in developing an appropriate relativistic framework for nuclear dynamics. A Lorentz-invariant description of the nuclear force suggests a similar decrease of the nucleon's mass in the nuclear medium as has been found from QCD sum rules. Work in progress extends previous successes in elastic scattering to inelastic scattering of protons by nuclei. The section on heavy ion dynamics and related processes reports on research into the e{sup +}e{sup {minus}} problem and heavy ion dynamics.

Not Available

1992-05-01T23:59:59.000Z

454

Economic Analysis for Conceptual Design of Supercritical O2-Based PC Boiler  

SciTech Connect

This report determines the capital and operating costs of two different oxygen-based, pulverized coal-fired (PC) power plants and compares their economics to that of a comparable, air-based PC plant. Rather than combust their coal with air, the oxygen-based plants use oxygen to facilitate capture/removal of the plant CO{sub 2} for transport by pipeline to a sequestering site. To provide a consistent comparison of technologies, all three plants analyzed herein operate with the same coal (Illinois No 6), the same site conditions, and the same supercritical pressure steam turbine (459 MWe). In the first oxygen-based plant, the pulverized coal-fired boiler operates with oxygen supplied by a conventional, cryogenic air separation unit, whereas, in the second oxygen-based plant, the oxygen is supplied by an oxygen ion transport membrane. In both oxygen-based plants a portion of the boiler exhaust gas, which is primarily CO{sub 2}, is recirculated back to the boiler to control the combustion temperature, and the balance of the flue gas undergoes drying and compression to pipeline pressure; for consistency, both plants operate with similar combustion temperatures and utilize the same CO{sub 2} processing technologies. The capital and operating costs of the pulverized coal-fired boilers required by the three different plants were estimated by Foster Wheeler and the balance of plant costs were budget priced using published data together with vendor supplied quotations. The cost of electricity produced by each of the plants was determined and oxygen-based plant CO{sub 2} mitigation costs were calculated and compared to each other as well as to values published for some alternative CO{sub 2} capture technologies.

Andrew Seltzer; Archie Robertson

2006-09-01T23:59:59.000Z

455

Nuclear hadrodynamics  

Science Conference Proceedings (OSTI)

The role of hadron dynamics in the nucleus is illustrated to show the importance of nuclear medium effects in hadron interactions. The low lying hadron spectrum is considered to provide the natural collective variable for nuclear systems. Recent studies of nucleon?nucleon and delta?nucleon interactions are reviewed

D. F. Geesaman

1984-01-01T23:59:59.000Z

456

PROBING DENSE NUCLEAR MATTER VIA NUCLEAR COLLISIONS  

E-Print Network (OSTI)

University of California. LBL-12095 Probing Dense NuclearMatter Nuclear Collisions* v~a H. Stocker, M.Gyulassy and J. Boguta Nuclear Science Division Lawrence

Stocker, H.

2012-01-01T23:59:59.000Z