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  1. Teacher Research Associates (TRAC)

    Broader source: Energy.gov [DOE]

    The goals of Fermilab's TRAC program are to provide outstanding science, mathematics, computer science, and technology teachers with professional scientific, engineering, or technical experiences...

  2. ARM - Campaign Instrument - trac

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

    would love to hear from you Send us a note below or call us at 1-888-ARM-DATA. Send Campaign Instrument : Time Resolved Aerosol Collector (TRAC) Instrument Categories Aerosols...

  3. SunTrac Solar | Open Energy Information

    Open Energy Info (EERE)

    SunTrac Solar Place: Golden,, Colorado Zip: 80403 Sector: Solar Product: Colorado based solar thermal integrator References: SunTrac Solar1 This article is a stub. You can help...

  4. How to Get to TRAC - Hanford Site

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

    How to Get to TRAC About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO How to Get to TRAC Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size Various Travel Routes to TRAC Center Head toward Pasco on I-182 East, take Exit 7 to Road 100 then turn left onto

  5. Transformer Resilience and Advanced Components (TRAC) Program...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    OE's Transformer Resilience and Advanced Components (TRAC) program supports modernization ... which are a critical component of the electricity delivery system, are a concern because ...

  6. CMS conditions data access using FroNTier

    SciTech Connect (OSTI)

    Blumenfeld, Barry J.; Dykstra, David; Lueking, Lee; Wicklund, Eric; /Fermilab

    2007-10-01

    The CMS experiment at the LHC has established an infrastructure using the FroNTier framework to deliver conditions (i.e. calibration, alignment, etc.) data to processing clients worldwide. FroNTier is a simple web service approach providing client HTTP access to a central database service. The system for CMS has been developed to work with POOL which provides object relational mapping between the C++ clients and various database technologies. Because of the read only nature of the data, Squid proxy caching servers are maintained near clients and these caches provide high performance data access. Several features have been developed to make the system meet the needs of CMS including careful attention to cache coherency with the central database, and low latency loading required for the operation of the online High Level Trigger. The ease of deployment, stability of operation, and high performance make the FroNTier approach well suited to the GRID environment being used for CMS offline, as well as for the online environment used by the CMS High Level Trigger (HLT). The use of standard software, such as Squid and various monitoring tools, make the system reliable, highly configurable and easily maintained. We describe the architecture, software, deployment, performance, monitoring and overall operational experience for the system.

  7. Samuel C.C. Ting, the J/psi Particle (Charm), and the Alpha Magnetic

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

    Spectrometer (AMS) Samuel C.C. Ting, the J/psi Particle (Charm), and the Alpha Magnetic Spectrometer (AMS) Resources with Additional Information Samuel C.C. Ting Credit: Courtesy of the Massachusetts Institute of Technology 'Samuel C.C. Ting was born ... in Ann Arbor, Michigan, ... [and] received his elementary and secondary education in China ... . He excelled in mathematics, science and history. In 1956, Ting returned to the United States to attend the University of Michigan as an

  8. TRAC-PF1 independent assessment

    SciTech Connect (OSTI)

    Knight, T.D.; Metzger, V.B.

    1985-10-01

    This report documents the Los Alamos results of the second assessment phase, independent assessment for TRAC-PF1. We documented the results of the developmental assessment for TRAC-PF1 in an earlier report. This report described calculations run with the released versions of TRAC-PF1. We analyzed separate-effects tests in the Semiscale facility to investigate natural-circulation and reflux cooling. We analyzed integral tests from the Semiscale and the Loss-of-Fluid Test facilities to explore the small- and intermediate-break loss-of-coolnt-accident (LOCA) capability and the non-LOCA capability. We also analyzed the loss-of-feedwater transient in the Crystal River plant. The results show reasonably good agreement with the data, but indicate that improvements are required for the critical-flow model and the interphasic-condensation model. 38 refs., 224 figs., 19 tabs.

  9. Samuel C.C. Ting, the J/psi Particle (Charm), and the Alpha Magnetic...

    Office of Scientific and Technical Information (OSTI)

    'Samuel C.C. Ting was born ... in Ann Arbor, Michigan, ... and received his elementary and secondary education in China ... . He excelled in mathematics, science and history. In ...

  10. Microsoft Word - summer.doc

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

    b trac ting fro m th e da ily a ve rag e hig h te m p e ra tu res fo r th e la st 10 y ea rs a n am o un t e qu al to tw ice a n estim ate o f the stan da rd de via tion for h igh...

  11. TRAC-P validation test matrix. Revision 1.0

    SciTech Connect (OSTI)

    Hughes, E.D.; Boyack, B.E.

    1997-09-05

    This document briefly describes the elements of the Nuclear Regulatory Commission`s (NRC`s) software quality assurance program leading to software (code) qualification and identifies a test matrix for qualifying Transient Reactor Analysis Code (TRAC)-Pressurized Water Reactor Version (-P), or TRAC-P, to the NRC`s software quality assurance requirements. Code qualification is the outcome of several software life-cycle activities, specifically, (1) Requirements Definition, (2) Design, (3) Implementation, and (4) Qualification Testing. The major objective of this document is to define the TRAC-P Qualification Testing effort.

  12. Ting Xu | Center for Gas SeparationsRelevant to Clean Energy...

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

    J. Am. Chem. Soc., 133, 15296-15299 (2011). 10.1021ja2063082 Xu, Ting; Zhao, Nana; Ren, Feng; Hourani, Rami; Lee, Ming Tsang; Shu, Jessica Y; Mao, Samuel; and Helms,...

  13. Transformer Resilience and Advanced Components (TRAC) Program Materials

    Broader source: Energy.gov [DOE]

    OE’s Transformer Resilience and Advanced Components (TRAC) program supports modernization and resiliency of the grid by addressing the challenges facing large power transformers (LPTs) and other...

  14. TRAC Code Modifications Made for APT Blanket Safety Analyses

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07

    This report provides documentation of the necessary source code modifications made to the TRAC-PF1/MOD2 code version 5.4.28a developed at Los Alamos National Laboratory.

  15. Software design implementation document for TRAC-M data structures

    SciTech Connect (OSTI)

    Jolly-Woodruff, S. [Ogden Environmental and Energy Services (United States); Mahaffy, J. [Pennsylvania State Univ., University Park, PA (United States); Giguere, P.; Dearing, J.; Boyack, B. [Los Alamos National Lab., NM (United States)

    1997-07-01

    The Transient Reactor Analysis Code (TRAC)-M system-wide and component data structures are to be reimplemented by using the new features of Fortran 90 (F90). There will be no changes to the conceptual design, data flow, or computational flow with respect to the current TRAC-P, except that readability, maintainability, and extensibility will be improved. However, the task described here is a basic step that does not meet all future needs of the code, especially regarding extensibility. TRAC-M will be fully functional and will produce null computational changes with respect to TRAC-P, Version 5.4.25; computational efficiency will not be degraded significantly. The existing component and functional modularity and possibilities for coarse-grained parallelism will be retained.

  16. Peach Bottom Transients Analysis with TRAC/BF1-VALKIN

    SciTech Connect (OSTI)

    Verdu, G.; Miro, R.; Sanchez, A.M.; Rosello, O.; Ginestar, D.; Vidal, V.

    2004-10-15

    The TRAC/BF1-VALKIN code is a new time domain analysis code for studying transients in a boiling water reactor. This code uses the best-estimate code TRAC/BF1 to give an account of the heat transfer and thermal-hydraulic processes and a three-dimensional neutronics module. This module has two options: the MODKIN option that makes use of a modal method based on the assumption that the neutronic flux can be approximately expanded in terms of the dominant lambda modes associated with a static configuration of the reactor core, and the NOKIN option that uses a one-step backward discretization of the neutron diffusion equation. To check the performance of the TRAC/BF1-VALKIN code, the Peach Bottom turbine trip transient has been simulated, because this transient is a dynamically complex event where neutron kinetics is coupled with thermal hydraulics in the reactor primary system, and reactor variables change very rapidly.

  17. Samuel C. Ting, 1975 | U.S. DOE Office of Science (SC)

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

    Administration | (NNSA) Samuel Bodman Sworn in as Secretary Energy Samuel Bodman Sworn in as Secretary Energy Washington, DC Samuel Bodman is sworn in as the eleventh Secretary of Energy

    Samuel C. Ting, 1975 The Ernest Orlando Lawrence Award Lawrence Award Home Nomination & Selection Guidelines Award Laureates 2010's 2000's 1990's 1980's 1970's 1960's Ceremony The Life of Ernest Orlando Lawrence Contact Information The Ernest Orlando Lawrence Award U.S. Department of Energy

  18. APT Blanket System Model Based on Initial Conceptual Design - Integrated 1D TRAC System Model

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07

    This report documents the approaches taken in establishing a 1-dimensional integrated blanket system model using the TRAC code, developed by Los Alamos National Laboratory.

  19. Prediction of MIT Pressurizer Data Using RELAP5 and TRAC-M

    SciTech Connect (OSTI)

    Shumway, Rex; Bolander, Mark; Aktas, Birol

    2002-07-01

    Tests simulating Pressurized Water Reactor pressurizers under inflow and outflow conditions have been performed at MIT. Prediction of pressurizer pressure requires accurate models of wall heat transfer as well as interfacial liquid-steam heat transfer. The US NRC has two computer programs used for predicting thermal hydraulic behavior in reactors; RELAP5 and TRAC-M. TRAC-M is the Consolidated Thermal-hydraulics Code developed by combining models from TRAC-B and RELAP5 into a modernized version of TRAC-P. The component models from RELAP5 and TRAC-B have been ported to TRAC-M but not the constitutive models. A suite of assessment cases are being developed to guide the constitutive model improvement process. Assessment against data will determine which constitutive relations need to be ported to TRAC-M. This paper compares the RELAP5 and TRAC-M codes against MIT pressurizer data. As water is injected into the bottom of the pressurizer the steam pressure in the top of the pressurizer rises. The pressure increase rate is controlled by wall and interface condensation rates. Both codes predict this complex compression process reasonably well. The effect of time step size and code options are explored in this paper. The benefits of using two codes to analyze thermal-hydraulic processes are evident from the results. (authors)

  20. Assessment of TRAC-BD1 amd RAMONA-3B codes fpr BWR ATWS application

    SciTech Connect (OSTI)

    Neymotin, L.; Hsu, C.J.; Saha, P.

    1984-01-01

    Based on comparisons between the TRAC-BD1 power imposed calculation and the RAMONA-3B results, it can be said that the thermal-hydraulic models of both RAMONA-3B and TRAC-BD1 provide adequate representation of an ATWS event in a BWR. However, for the reactor power calculation, RAMONA-3B with space-time neutron kinetics is a superior and preferable tool to the TRAC-BD1 with point kinetics for ATWS type events where the spatial core power distribution varies with time. Also, the computer running time for RAMONA-3B (with 115 hydraulic cells and 192 neutronic cells has been found to be about four times lower than TRAC-BD1 (with 63 hydraulic cells and point kinetics). Therefore, it is recommended that RAMONA-3B be further used for best-estimate analysis of BWR ATWS-type events.

  1. LOCA analysis evaluation model with TRAC-PF1/NEM

    SciTech Connect (OSTI)

    Orive Moreno, Raul; Gallego Cabezon, Ines; Garcia Sedano, Pablo

    2004-07-01

    Nowadays regulatory rules and code models development are progressing on the goal of using best-estimate approximations in applications of license. Inside this framework, IBERDROLA is developing a PWR LOCA Analysis Methodology with one double slope, by a side the development of an Evaluation Model (upper-bounding model) that covers with conservative form the different aspects from the PWR LOCA phenomenology and on the other hand, a proposal of CSAU (Code Scaling Applicability and Uncertainty) type evaluation, methodology that strictly covers the 95/95 criterion in the Peak Cladding Temperature. A structured method is established, that basically involves the following steps: 1. Selection of the Large Break LOCA like accident to analyze and of TRAC-PF1/MOD2 V99.1 NEM (PSU version) computer code like analysis tool. 2. Code Assessment, identifying the most remarkable phenomena (PIRT, Phenomena Identification and Ranking Tabulation) and estimation of a possible code deviation (bias) and uncertainties associated to the specific models that control these phenomena (critical flow mass, heat transfer, countercurrent flow, etc...). 3. Evaluation of an overall PCT uncertainty, taking into account code uncertainty, reactor initial conditions, and accident boundary conditions. Uncertainties quantification requires an excellent experiments selection that allows to define a complete evaluation matrix, and the comparison of the simulations results with the experiments measured data, as well as in the relative to the scaling of these phenomena. To simulate these experiments it was necessary to modify the original code, because it was not able to reproduce, in a qualitative way, the expected phenomenology. It can be concluded that there is a good agreement between the TRAC-PF1/NEM results and the experimental data. Once average error ({epsilon}) and standard deviation ({sigma}) for those correlations under study are obtained, these factors could be used to correct in a conservative

  2. TRAC analysis of the Crystal River Unit-3 Plant transient of February 26, 1980

    SciTech Connect (OSTI)

    Coddington, P.; Willcutt, G.J.E. Jr.

    1983-01-01

    This paper describes the application of the TRAC-PD2 and TRAC-PF1 codes to analyze the Crystal River transient. The PD2 and PF1 analyses used the three-dimensional and one-dimensional vessel models, respectively. Both calculations predicted the plant depressurization caused by the open PORV and the subsequent repressurization caused by closing the PORV and continuing high-pressure injection flow. Also, natural circulation was calculated in loop B following reestablishment of feedwater to the loop-B steam generator. After system repressurization, the codes calculated that pressure was relieved through the safety valves, and an intermittent flow occurred in loop A because of high-pressure-injection-driven density variations.

  3. Consistent generation and functionalization of one-dimensional cross sections for TRAC-BF1

    SciTech Connect (OSTI)

    Munoz-Cobo, J.L.; Verdu, G.; Pereira, C.; Escriva, A.; Rodenas, J. . Dept. of Chemical and Nuclear Engineering); Castrillo, F.; Serra, J. )

    1994-08-01

    A method of calculation of correct functionalized cross sections and diffusion coefficients for TRAC-BF1, based on the one-dimensional kinetic files of the tridimensional simulator SIMULATE-3, is developed. The method allows the user to obtain first the consistent one-dimensional cross sections, diffusion coefficients, and bucklings, which upon being inserted into TRAC-BF1 conserve the three-dimensional eigenvalues, the planar reaction rates, and the fast and thermal radially averaged fluxes at each axial node. This method also compensates for the differences between the thermal-hydraulic models of the three-dimensional simulator and the transient analysis code. The errors obtained with this method are very small.

  4. Comparison of TRAC-BF1 calculations with the LaSalle 2 instability event

    SciTech Connect (OSTI)

    Larson, J.R.

    1993-05-01

    In March of 1988 the LaSalle 2 BWR, while at about 85 percent power, was exposed to a loss of both recirculation pumps providing drive flow to the jet pumps. Within a few minutes the reactor power began to oscillate, resulting in an overpower scram. This report presents results of calculations performed with the TRAC-BF1 code to assess the capability of the code to calculate the observed behavior of the LaSalle plant during the event.

  5. Numerical simulation of fiber and wire array Z-pinches with Trac-II

    SciTech Connect (OSTI)

    Reisman, D

    1998-09-01

    Trac-II is a two dimensional axisymmetric resistive MHD code. It simulates all three spatial components (r, z, φ) of the magnetic field and fluid velocity vectors, and the plasma is treated as a single fluid with two temperatures (Te,Ti). In addition, it can optionally include a self-consistent external circuit. Recent modifications to the code include the addition of the 3-T radiation model, a 4-phase (solid-liquid-vapor-plasma) equation of state model (QEOS), a 4-phase electrical/thermal conductivity model, and an implicit solution of poloidal Bz,Br) magnetic field diffusion. These changes permit a detailed study of fiber and wire array Z-pinches. Specifically, Trac-II is used to study the wire array Z-pinch at the PBFA-Z pulse power generator at Sandia National Laboratory. First, in 1-D we examine the behavior of a single wire in the Z-pinch. Then, using these results as initial radial conditions in 2-D, we investigate the dynamics of wire array configurations in the r-z and r-θ plane. In the r-z plane we examine the growth of the m=0 or "sausage" instability in single wires within the array. In the r-θ plane we examine the merging behavior between neighboring wires. Special emphasis is placed on trying to explain how instability growth affects the performance of the Z-pinch. Lastly, we introduce Trac-III, a 3-D MHD code, and illustrate the m=1 or "kink" instability. We also discuss how Trac-III can be modified to simulate the wire array Z-pinch.

  6. Verification of the coupled 3-D neutronics and thermal-hydraulic code SKETCH-INS/TRAC-P

    SciTech Connect (OSTI)

    Nakajima, T.; Takeuchi, A.

    2006-07-01

    In order to analyze the complex transients with coupled interactions between core behavior and plant dynamics, the three-dimensional neutronics code SKETCH-INS was coupled with the thermal-hydraulic code TRAC-P. The capability SKETCH-INS code was verified against the 3-D transient benchmark problem. The capability of the coupled code SKETCH-INS/TRAC-P was verified against the NEACRP 3-D LWR core transient benchmark and OECD MSLB benchmark problems. The results of analyses were in reasonable agreement with the reference and different codes results of benchmarks. This paper provides the outline of the coupled code SKETCH-INS/TRAC-P and the results of benchmarks. (authors)

  7. Post-test analysis of semiscale tests S-UT-6 and S-UT-7 using TRAC PF1

    SciTech Connect (OSTI)

    Boyack, B.E.

    1983-01-01

    A posttest study of Semiscale Tests S-UT-6 and S-UT-7 has been completed to assess TRAC-PFl predictions of pressurized water-reactor (PWR) small-break transients. The comparisons of the TRAC calculations and experimental results show that the correct qualitative influence of upper-head injection (UHI) was predicted. The major phenomenological difference predicted was the mode of core voiding. The data show a slow boiloff from the top of the core resulting in a dryout near the top of the core only. TRAC predicted a more extensive voiding with fluid forced from the bottom of the core by a pressure increase in the upper vessel plenum. The pressure increase was the primary consequence of a failure to predict a complete clearance of the seal in the intact-loop pump-suction upflow leg. Further review of the interphasic drag correlations, entrainment correlations, and critical-flow model is recommended. 20 figures.

  8. Application of TRAC-BD1/MOD1 to a BWR/4 feedwater control failure ATWS

    SciTech Connect (OSTI)

    Rouhani, S.Z.; Giles, M.M.; Mohr, C.M. Jr.; Weaver, W.L. III

    1984-01-01

    This paper begins with a short description of the Transient Reactor Analysis Code for Boiling Water Reactors (TRAC-BWR), briefly mentioning some of its main features such as specific BWR models and input structure. Next, an input model of a BWR/4 is described, and, the assumptions used in performing an analysis of the loss of a feedwater controller without scram are listed. The important features of the calculated trends in flows, pressure, reactivity, and power are shown graphically and commented in the text. A comparison of some of the main predicted trends with the calculated results from a similar study by General Electric is also presented.

  9. Application programming interface document for the modernized Transient Reactor Analysis Code (TRAC-M)

    SciTech Connect (OSTI)

    Mahaffy, J. [Pennsylvania State Univ., University Park, PA (United States); Boyack, B.E.; Steinke, R.G. [Los Alamos National Lab., NM (United States)

    1998-05-01

    The objective of this document is to ease the task of adding new system components to the Transient Reactor Analysis Code (TRAC) or altering old ones. Sufficient information is provided to permit replacement or modification of physical models and correlations. Within TRAC, information is passed at two levels. At the upper level, information is passed by system-wide and component-specific data modules at and above the level of component subroutines. At the lower level, information is passed through a combination of module-based data structures and argument lists. This document describes the basic mechanics involved in the flow of information within the code. The discussion of interfaces in the body of this document has been kept to a general level to highlight key considerations. The appendices cover instructions for obtaining a detailed list of variables used to communicate in each subprogram, definitions and locations of key variables, and proposed improvements to intercomponent interfaces that are not available in the first level of code modernization.

  10. Analysis of a typical BWR/4 MSIV closure ATWS using RAMONA-3B and TRAC-BD1 codes

    SciTech Connect (OSTI)

    Hsu, C.J.; Neymotin, L.; Saha, P.

    1984-01-01

    Analysis of a typical BWR/4 Anticipated Transient Without Scram (ATWS) has been performed using two advanced, best-estimate computer codes, namely, RAMONA-3B and TRAC-BD1. The transient was initiated by an inadvertant closure of all Main Steam Isolation Valves (MSIVs) with subsequent failure to scram the reactor. However, all other safety features namely, the safety and relief valves, recirculation pump trip, high pressure coolant injection and the standby liquid (boron) control system were assumed to work as designed. No other operator action was assumed. It has been found that both RAMONA-3B (with three-dimensional neutron kinetics) and TRAC-BD1 (with point kinetics) yielded similar results for the global parameters such as reactor power, system pressure and the suppression pool temperature. Both calculations showed that the reactor can be brought to hot shutdown in approximately twenty to twenty-five minutes with borated water mass flow rate of 2.78 kg/s (43 gpm) with 23800 ppM of boron. The suppression pool water temperature (assuming no pool cooling) at this time could be in the range of 170 to 205/sup 0/F. An additional TRAC-BD1 calculation with RAMONA-3B reactor power indicates that the thermal-hydraulic models in RAMONA-3B, although simpler than those in TRAC-BD1, can adequately represent the system behavior during the ATWS-type transient.

  11. Preliminary LOCA analysis of the westinghouse small modular reactor using the WCOBRA/TRAC-TF2 thermal-hydraulics code

    SciTech Connect (OSTI)

    Liao, J.; Kucukboyaci, V. N.; Nguyen, L.; Frepoli, C.

    2012-07-01

    The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (> 225 MWe) integral pressurized water reactor (iPWR) with all primary components, including the steam generator and the pressurizer located inside the reactor vessel. The reactor core is based on a partial-height 17x17 fuel assembly design used in the AP1000{sup R} reactor core. The Westinghouse SMR utilizes passive safety systems and proven components from the AP1000 plant design with a compact containment that houses the integral reactor vessel and the passive safety systems. A preliminary loss of coolant accident (LOCA) analysis of the Westinghouse SMR has been performed using the WCOBRA/TRAC-TF2 code, simulating a transient caused by a double ended guillotine (DEG) break in the direct vessel injection (DVI) line. WCOBRA/TRAC-TF2 is a new generation Westinghouse LOCA thermal-hydraulics code evolving from the US NRC licensed WCOBRA/TRAC code. It is designed to simulate PWR LOCA events from the smallest break size to the largest break size (DEG cold leg). A significant number of fluid dynamics models and heat transfer models were developed or improved in WCOBRA/TRAC-TF2. A large number of separate effects and integral effects tests were performed for a rigorous code assessment and validation. WCOBRA/TRAC-TF2 was introduced into the Westinghouse SMR design phase to assist a quick and robust passive cooling system design and to identify thermal-hydraulic phenomena for the development of the SMR Phenomena Identification Ranking Table (PIRT). The LOCA analysis of the Westinghouse SMR demonstrates that the DEG DVI break LOCA is mitigated by the injection and venting from the Westinghouse SMR passive safety systems without core heat up, achieving long term core cooling. (authors)

  12. Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark

    SciTech Connect (OSTI)

    Kozlowski, Tomasz; Miller, R. Matthew; Downar, Thomas J.; Barber, Douglas A.; Joo, Han Gyu

    2004-04-15

    A generalized interface module was developed for coupling any thermal-hydraulic code to any spatial kinetic code. In the design used here the thermal-hydraulic and spatial kinetic codes function as independent processes and communicate using the Parallel Virtual Machine software. This approach helps maximize flexibility while minimizing modifications to the respective codes. Using this interface, the U.S. Nuclear Regulatory Commission (NRC) three-dimensional neutron kinetic code, Purdue Advanced Reactor Core Simulator (PARCS), has been coupled to the NRC system analysis codes RELAP5 and Modernized Transient Reactor Analysis Code (TRAC-M). Consistent comparison of code results for the Organization for Economic Cooperation and Development/Nuclear Energy Agency main steam line break benchmark problem using RELAP5/PARCS and TRAC-M/PARCS was made to assess code performance.

  13. Coupling of TRAC-PF1/MOD2, Version 5.4.25, with NESTLE

    SciTech Connect (OSTI)

    Knepper, P.L.; Hochreiter, L.E.; Ivanov, K.N.; Feltus, M.A.

    1999-09-01

    A three-dimensional (3-D) spatial kinetics capability within a thermal-hydraulics system code provides a more correct description of the core physics during reactor transients that involve significant variations in the neutron flux distribution. Coupled codes provide the ability to forecast safety margins in a best-estimate manner. The behavior of a reactor core and the feedback to the plant dynamics can be accurately simulated. For each time step, coupled codes are capable of resolving system interaction effects on neutronics feedback and are capable of describing local neutronics effects caused by the thermal hydraulics and neutronics coupling. With the improvements in computational technology, modeling complex reactor behaviors with coupled thermal hydraulics and spatial kinetics is feasible. Previously, reactor analysis codes were limited to either a detailed thermal-hydraulics model with simplified kinetics or multidimensional neutron kinetics with a simplified thermal-hydraulics model. The authors discuss the coupling of the Transient Reactor Analysis Code (TRAC)-PF1/MOD2, Version 5.4.25, with the NESTLE code.

  14. Analysis of the OECD/NRC BWR Turbine Trip Transient Benchmark with the Coupled Thermal-Hydraulics and Neutronics Code TRAC-M/PARCS

    SciTech Connect (OSTI)

    Lee, Deokjung; Downar, Thomas J.; Ulses, Anthony; Akdeniz, Bedirhan; Ivanov, Kostadin N.

    2004-10-15

    An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the U.S. Nuclear Regulatory Commission coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. The objective of the analysis was to assess the performance of TRAC-M/PARCS on a BWR transient with significance in two-phase flow and spatial variations of the neutron flux. TRAC-M/PARCS results are found to be in good agreement with measured plant data for both steady-state and transient phases of the benchmark. Additional analyses of four fictitious extreme scenarios are performed to provide a basis for code-to-code comparisons and comprehensive testing of the thermal-hydraulics/neutronics coupling. The obtained results of sensitivity studies on the effect of direct moderator heating on transient simulation indicate the importance of this modeling aspect.

  15. TRAC-PF1/MOD1 US/Japanese PWR conservative LOCA prediction

    SciTech Connect (OSTI)

    Gruen, G E; Fisher, J E

    1987-11-01

    This report documents the results of a 200%, double-ended, cold-leg-break, loss-of-coolant-accident (LOCA) calculation using the TRAC-PF1/MOD1 computer code. The reactor system represented a typical United States/Japanese pressurized water reactor with a 15 x 15 fuel bundle arrangement 12-ft long, four loops, and cold-leg Emergency Core Cooling (ECC) Systems. Conservation boundary and initial conditions were used. Reactor power was 102% of the 3250 MWt rated power, decay heat was set to 120% of American Nuclear Society Standard 5.1, highest core lifetime values for power peaking and fuel stored energy were used, and the LOCA occurred simultaneously with a loss of offsite power. Best estimate assumptions were used for the break flow model, fuel rod heat transfer and metal-water reaction correlations, and steady-state fuel temperature profiles. A flow blockage model, having the capability to account for the effects of cladding ballooning or rupturing, was not used. Except for these best estimate assumptions, the boundary and initial conditions were consistent with those used in licensing calculations. Maximum fuel rod temperatures were 1380 K (2020/sup 0/F) and 1040 K (1410/sup 0/F) on the hottest evaluation model rod and hottest best estimate rod, respectively. The high reported values or fuel cladding temperature were a direct consequence of the conservative boundary and initial conditions used for the calculation, primarily the 2% overpower condition, the core decay heat assumption, and the degraded ECCS. The calculation demonstrated successful core reflooding before 1478 K (2200/sup 0/F) cladding temperature was exceeded on any fuel rod. 7 refs., 47 figs., 5 tabs.

  16. TRAC-PF1/MOD1 independent assessment: Semiscale Mod-2A intermediate break test S-IB-3

    SciTech Connect (OSTI)

    Kmetyk, L N

    1986-02-01

    The TRAC-PF1/MOD1 independent assessment project at Sandia National Laboratories is part of an overall effort funded by the NRC to determine the ability of various system codes to predict the detailed thermal/hydraulic response of light water reactors during accident and off-normal conditions. The TRAC code is being assessed at SNLA against test data from various integral and separate effects test facilities. As part of this assessment matrix, an intermediate break test (S-IB-3), performed at the Semiscale Mod-2A facility, has been analyzed. Using an input model with a 3-D VESSEL component, the vessel and downcomer inventories during 3-IB-3 were generally well predicted, but the core heatup was underpredicted compared to data. An equivalent calculation with an all 1-D input model ran about twice as fast as our basecase analysis using a 3-D VESSEL in the input model, but the results of the two calculations diverged significantly for many parameters of interest, with the 3-D VESSEL model results in better agreement with data. 22 refs., 100 figs.

  17. International Code Assessment and Applications Program: Summary of code assessment studies concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC-B. International Agreement Report

    SciTech Connect (OSTI)

    Schultz, R.R.

    1993-12-01

    Members of the International Code Assessment Program (ICAP) have assessed the US Nuclear Regulatory Commission (USNRC) advanced thermal-hydraulic codes over the past few years in a concerted effort to identify deficiencies, to define user guidelines, and to determine the state of each code. The results of sixty-two code assessment reviews, conducted at INEL, are summarized. Code deficiencies are discussed and user recommended nodalizations investigated during the course of conducting the assessment studies and reviews are listed. All the work that is summarized was done using the RELAP5/MOD2, RELAP5/MOD3, and TRAC-B codes.

  18. TRAC-PF1/MOD1: an advanced best-estimate computer program for pressurized water reactor thermal-hydraulic analysis

    SciTech Connect (OSTI)

    Liles, D.R.; Mahaffy, J.H.

    1986-07-01

    The Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC) to provide advanced best-estimate predictions of postulated accidents in light-water reactors. The TRAC-PF1/MOD1 program provides this capability for pressurized water reactors and for many thermal-hydraulic test facilities. The code features either a one- or a three-dimensional treatment of the pressure vessel and its associated internals, a two-fluid nonequilibrium hydrodynamics model with a noncondensable gas field and solute tracking, flow-regime-dependent constitutive equation treatment, optional reflood tracking capability for bottom-flood and falling-film quench fronts, and consistent treatment of entire accident sequences including the generation of consistent initial conditions. The stability-enhancing two-step (SETS) numerical algorithm is used in the one-dimensional hydrodynamics and permits this portion of the fluid dynamics to violate the material Courant condition. This technique permits large time steps and, hence, reduced running time for slow transients.

  19. TRAC-PF1/MOD1 analysis of a 200% cold-leg break in a US/Japanese PWR with four loops and 15 x 15 fuel

    SciTech Connect (OSTI)

    Spore, J.W.; Cappiello, M.W.

    1986-01-01

    This report presents the results of a TRAC-PF1/MOD1 calculation that simulated a 200% double-ended cold-leg-break loss-of-coolant accident in a generic US/Japanese pressurized water reactor. This is a best-estimate analysis using conservative boundary conditions and minimum safeguards. The calculation shows that the peak cladding temperature (PCT) occurs during blowdown and that the core reheat is minimal during reflood. The results also show that for an evaluation-model peak rod linear power of 15.85 kW/ft, a PCT of 1084 K is reached at 3.5 s into the blowdown transient, which is approx.394 K below the design basis limit of 1478 K. 10 figs.

  20. SU-E-CAMPUS-J-05: Quantitative Investigation of Random and Systematic Uncertainties From Hardware and Software Components in the Frameless 6DBrainLAB ExacTrac System

    SciTech Connect (OSTI)

    Keeling, V; Jin, H; Hossain, S; Ahmad, S; Ali, I

    2014-06-15

    Purpose: To evaluate setup accuracy and quantify individual systematic and random errors for the various hardware and software components of the frameless 6D-BrainLAB ExacTrac system. Methods: 35 patients with cranial lesions, some with multiple isocenters (50 total lesions treated in 1, 3, 5 fractions), were investigated. All patients were simulated with a rigid head-and-neck mask and the BrainLAB localizer. CT images were transferred to the IPLAN treatment planning system where optimized plans were generated using stereotactic reference frame based on the localizer. The patients were setup initially with infrared (IR) positioning ExacTrac system. Stereoscopic X-ray images (XC: X-ray Correction) were registered to their corresponding digitally-reconstructed-radiographs, based on bony anatomy matching, to calculate 6D-translational and rotational (Lateral, Longitudinal, Vertical, Pitch, Roll, Yaw) shifts. XC combines systematic errors of the mask, localizer, image registration, frame, and IR. If shifts were below tolerance (0.7 mm translational and 1 degree rotational), treatment was initiated; otherwise corrections were applied and additional X-rays were acquired to verify patient position (XV: X-ray Verification). Statistical analysis was used to extract systematic and random errors of the different components of the 6D-ExacTrac system and evaluate the cumulative setup accuracy. Results: Mask systematic errors (translational; rotational) were the largest and varied from one patient to another in the range (−15 to 4mm; −2.5 to 2.5degree) obtained from mean of XC for each patient. Setup uncertainty in IR positioning (0.97,2.47,1.62mm;0.65,0.84,0.96degree) was extracted from standard-deviation of XC. Combined systematic errors of the frame and localizer (0.32,−0.42,−1.21mm; −0.27,0.34,0.26degree) was extracted from mean of means of XC distributions. Final patient setup uncertainty was obtained from the standard deviations of XV (0.57,0.77,0.67mm,0

  1. Low-Cost Gas Heat Pump fro Building Space Heating

    Energy Savers [EERE]

    A.O. Smith Gas Technology Institute Target MarketAudience: Residential & Light Commercial ... Partners, Subcontractors, and Collaborators: * AO Smith (OEM): Provides component design, ...

  2. SU-E-J-24: Can Fiducial Marker-Based Setup Using ExacTrac Be An Alternative to Soft Tissue-Based Setup Using Cone-Beam CT for Prostate IMRT?

    SciTech Connect (OSTI)

    Tanabe, S; Utsunomiya, S; Abe, E; Aoyama, H; Satou, H; Sakai, H; Yamada, T

    2015-06-15

    Purpose: To assess an accuracy of fiducial maker-based setup using ExacTrac (ExT-based setup) as compared with soft tissue-based setup using Cone-beam CT (CBCT-based setup) for patients with prostate cancer receiving intensity-modulated radiation therapy (IMRT) for the purpose of investigating whether ExT-based setup can be an alternative to CBCT-based setup. Methods: The setup accuracy was analyzed prospectively for 7 prostate cancer patients with implanted three fiducial markers received IMRT. All patients were treated after CBCT-based setup was performed and corresponding shifts were recorded. ExacTrac images were obtained before and after CBCT-based setup. The fiducial marker-based shifts were calculated based on those two images and recorded on the assumption that the setup correction was carried out by fiducial marker-based auto correction. Mean and standard deviation of absolute differences and the correlation between CBCT and ExT shifts were estimated. Results: A total of 178 image dataset were analyzed. On the differences between CBCT and ExT shifts, 133 (75%) of 178 image dataset resulted in smaller differences than 3 mm in all dimensions. Mean differences in the anterior-posterior (AP), superior-inferior (SI), and left-right (LR) dimensions were 1.8 ± 1.9 mm, 0.7 ± 1.9 mm, and 0.6 ± 0.8 mm, respectively. The percentages of shift agreements within ±3 mm were 76% for AP, 90% for SI, and 100% for LR. The Pearson coefficient of correlation for CBCT and ExT shifts were 0.80 for AP, 0.80 for SI, and 0.65 for LR. Conclusion: This work showed that the accuracy of ExT-based setup was correlated with that of CBCT-based setup, implying that ExT-based setup has a potential ability to be an alternative to CBCT-based setup. The further work is to specify the conditions that ExT-based setup can provide the accuracy comparable to CBCT-based setup.

  3. Microsoft Word - TRACS revise.doc

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

    RSL ENHANCES NEW YORK'S COUNTER TERRORISM OPERATIONS The National Nuclear Security Administration's Remote Sensing Laboratory (RSL) at Nellis Air Force Base has given a lift to the Big Apple's terror-fighting capabilities. RSL recently retrofitted two new high-tech speedboats, two vans and several portable backpacks with radiation detection equipment for the New York Police Department (NYPD) Counter Terrorism Division. The detection equipment formerly called the Tactical Radiological Acquisition

  4. Transformer Resilience and Advanced Components (TRAC) Program

    Broader source: Energy.gov [DOE]

    To date, much of the “smart grid” transformation has focused on applying advanced digital information and communication technologies to the power grid to improve the system’s reliability,...

  5. METALS~~~SINTEG~~~~TING~COMPANY, INC.

    Office of Legacy Management (LM)

    METALSSINTEGTINGCOMPANY, INC. April 5, 1946 War Department Manhattan &glneer District P. 0. Box 33S Church Street Annex New York 8, New Pork Attention: Major W illiam C. ...

  6. ARM: X-SAPR Vertical PoinTing scan (Dataset) | Data Explorer

    Office of Scientific and Technical Information (OSTI)

    Sponsoring Org: USDOE Office of Science (SC), Biological and Environmental Research (BER) (SC-23) Country of Publication: United States Availability: ORNL Language: English ...

  7. DockingShop: A Tool for Interactive Molecular Docking Ting-Cheng...

    Office of Scientific and Technical Information (OSTI)

    ... Covalent bond Cova lent bond Hydrogen bond Hydro gen bond monitors the position and ... Figure 3. Small blue spheres represent water. Dashed-blue lines represent hydrogen bonds ...

  8. Samuel C.C. Ting, the J/psi Particle (Charm), and the Alpha Magnetic...

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

    of Technology, began experiments at the Brookhaven National Laboratory in New York, again ... Additional Web Pages: Discovery of the Jpsi Particle, Brookhaven National Laboratory ...

  9. Development of a Fast Time-Resolved Aerosol Collector (Fast TRAC...

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

    map and times SEMEDX map and elemental analysis Xiao-Ying Yu, James Cowin PNNL Fast Framing * 240 framessec * 4 ms per frame * See 100 nm particles arriving New 100 nm...

  10. Development of a Fast Time-Resolved Aerosol Collector (Fast TRAC...

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

    map and times SEMEDX map and elemental analysis Xiao-Ying Yu & James Cowin PNNL Fast Framing * 240 framessec * 4 ms per frame * See 100 nm particles arriving New 100 nm...

  11. Novel Membranes | Center for Gas SeparationsRelevant to Clean...

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

    Novel Membranes Previous Next List Brett Helms Brett Helms Hopkinson David Hopkinson tsapatsis Michael Tsapatsis Ting Xu Ting Xu...

  12. HOPSPACK

    Energy Science and Technology Software Center (OSTI)

    002439WKSTN00 Hybrid Optimization Parallel Search PACKage https://software.sandia.dov/trac/hopspack

  13. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Lei, Ming (1) Lesner, Adam (1) Li, Song (1) Libby, Peter (1) Liu, Conglin (1) Secco, ... Tang, Ting-Ting (1) Tia, Viviane (1) Upton, Heather (1) Save Results Save this search to ...

  14. ACRO V.2.0

    Energy Science and Technology Software Center (OSTI)

    001742MLTPL01 Acro (A Common Repository for Optimizers) v. 2.0 https://software.sandia.gov/trac/acro

  15. SWQM

    Energy Science and Technology Software Center (OSTI)

    002617MLTPL00 SWQM: Source Water Quality Modeling Software https://software.sandia.gov/trac/canary/downloader/download/category/10

  16. EMPASE

    Energy Science and Technology Software Center (OSTI)

    002556MLTPL00 EMPaSE: an Extensible Multi-Paradigm Simulation Environment https://software.sandia.gov/trac

  17. MEGA

    Energy Science and Technology Software Center (OSTI)

    002444SUPER00 Modular Environment for Graph Research and Analysis with a Persistent http://software.sandia.gov/trac/megraphs

  18. Improved Technique of Hydrogen Content Analysis by Slow Neutron Scattering

    DOE R&D Accomplishments [OSTI]

    Rainwater, L. J.; Havens, W. W. Jr.

    1945-02-28

    A slow-neutron-transmission method fro determining the H content of fluorcarbons is described (G.Y.)

  19. Collegiate Wind Competition 2016 Rules and Regulations | Department...

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

    and Information Systems; Jessica Ting, Marketing and Information Systems; Njeri Warrington, Marketing and Supply Chain Management; Emelia Gold, Atmospheric and Oceanic Science. ...

  20. Lipophilic Bisphosphonates as Dual Farnesyl/Geranylgeranyl Diphosphate...

    Office of Scientific and Technical Information (OSTI)

    Michael P. ; Guo, Rey-Ting ; Krysiak, Kilannin ; Mukherjee, Sujoy ; Gao, Yi-Gui ; Robinson, Howard ; Song, Yongcheng ; No, Joo Hwan ; Bergan, Kyle ; Leon, Annette ; Cass, ...

  1. Academic Year 2009-2010 Intern Project - Charles Buhler | Center...

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

    Charles Buhler SOLAR CELL THERMOELECTRICS Charles Buhler Physics UC Santa Barbara Mentor: Je-Hyeong Bahk Chieh-Ting Lin Faculty Advisor: John Bowers Department: Electrical and ...

  2. FAST

    Energy Science and Technology Software Center (OSTI)

    002363MLTPL00 FAST - A Framework for Agile Software Testing v. 2.0 https://software.sandia.gov/trac/fast

  3. CANARY-EDS V.4.3

    Energy Science and Technology Software Center (OSTI)

    002119IBMPC01 Characterization and Analysis of Networked Array of Sensors for Event Detection (CANARY-EDS) https:/Isoftware.sandia.gov/trac/canary/

  4. Memorandum, Health and Safety Training Reciprocity Program- July 12, 2013

    Broader source: Energy.gov [DOE]

    The centerpiece of TRAC is HSS' voluntary training reciprocity program that has tremendous potential to bring consistency and standardization to health and safety training across DOE.

  5. Smart Grid e-Forum | Department of Energy

    Office of Environmental Management (EM)

    Electricity Advisory Committee Technology Development Smart Grid Demand Response Federal Smart Grid Task Force Microgrids Energy Storage TRAC Program Advanced Modeling Grid ...

  6. Colombia-World Bank Climate Projects | Open Energy Information

    Open Energy Info (EERE)

    Offset Project "The Colombia Rio Frio Carbon Offset Project aims to reduce greenhouse gas emissions fro the wastewater treatment sector in Colombia by modernizing the Rio Frio...

  7. Quadrennial

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

    RepoRt on the FiRst Quadrennial Technology review QTr Message froM the secretary of energy | i QUaDrennIaL technoLogy reVIeW 2011 Message froM the secretary of energy Steven Chu, ...

  8. Rami Hourani | Center for Gas SeparationsRelevant to Clean Energy...

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

    J. Am. Chem. Soc., 133, 15296-15299 (2011). 10.1021ja2063082 Xu, Ting; Zhao, Nana; Ren, Feng; Hourani, Rami; Lee, Ming Tsang; Shu, Jessica Y; Mao, Samuel; and Helms,...

  9. Brett Helms | Center for Gas SeparationsRelevant to Clean Energy...

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

    J. Am. Chem. Soc., 133, 15296-15299 (2011). 10.1021ja2063082 Xu, Ting; Zhao, Nana; Ren, Feng; Hourani, Rami; Lee, Ming Tsang; Shu, Jessica Y; Mao, Samuel; and Helms,...

  10. Subnanometer Porous Thin Films by the Co-assembly of Nanotube...

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

    the Co-assembly of Nanotube Subunits and Block Copolymers Previous Next List Ting Xu, Nana Zhao, Feng Ren, Rami Hourani, Ming Tsang Lee, Jessica Y. Shu, Samuel Mao, and Brett A....

  11. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Clem, Paul G. (3) campione, s (3) Bender, Daniel A. (2) Campione, Salvatore (2) Capolino, F. (2) Ihlefeld, Jon (2) Krishna, Sanjay (2) Luk, Ting S. (2) Wendt, Joel R. (2) Save ...

  12. "Multifunctional Mesoporous Silica Catalyst" Patent Awarded ...

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

    Silica Catalyst" Patent Awarded Congratulations to the late Victor Lin, Show-Ling Lee, Chih-Hsiang Tsai, Hung-Ting Chen, Marek Pruski and Takeshi Kobayashi for being awarded...

  13. Summer 2010 Intern Project- Charles Buhler | Center for Energy...

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

    ENERGY PHOTONS BACK TO THE TOP CELLS TO INCREASE PERFORMANCE FOR A FOUR-JUNCTION SOLAR CELL Charles Buhler Physics UC Santa Barbara Mentor: Chieh-Ting Lin Faculty Advisor: John ...

  14. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    cancer Ma, Qing ; Yu, Tao ; Ren, Yao-Yao ; Gong, Ting ; Zhong, Dian-Sheng, E-mail: zhongdsyx@126.com Highlights: * SAMD9 is down-regulated in human non-small cell lung cancer ...

  15. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Fractional quantum spin Hall effect in flat-band checkerboard lattice model Li, Wei ; Sheng, D. N. ; Ting, C. S. ; Chen, Yan Full Text Available August 2014 , American Physical ...

  16. H2 @ Scale … A Potential Opportunity Webinar

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    * Hydrogen is not new. o Has seen ups and downs o Most have a preconceived opinion, but ... T Generation: Jamie Holladay (lead, PNNL); Jim O'Brien (INL); Tony McDaniel (SNL); Ting He ...

  17. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Environments Terrani, Kurt A ; Keiser, James R ; Brady, Michael P ; Cheng, Ting ; Silva, G W Chinthaka M ; Pint, Bruce A ; Snead, Lance Lewis A side by side comparison of the ...

  18. SEP Success Story: "Green Launching Pad" Supports Clean Energy...

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

    John Lynch, and UNH President Mark Huddleston held at EnerTrac, Inc., in Hudson, NH. | Courtesy of University of New Hampshire Photographic Services Green Launching Pad 2.0 awards ...

  19. Terrain-Responsive Atmospheric Code

    Energy Science and Technology Software Center (OSTI)

    1991-11-20

    The Terrain-Responsive Atmospheric Code (TRAC) is a real-time emergency response modeling capability designed to advise Emergency Managers of the path, timing, and projected impacts from an atmospheric release. TRAC evaluates the effects of both radiological and non-radiological hazardous substances, gases and particulates. Using available surface and upper air meteorological information, TRAC realistically treats complex sources and atmospheric conditions, such as those found in mountainous terrain. TRAC calculates atmospheric concentration, deposition, and dose for more thanmore » 25,000 receptor locations within 80 km of the release point. Human-engineered output products support critical decisions on the type, location, and timing of protective actions for workers and the public during an emergency.« less

  20. EXPO 2014 Exhibitor Information Exhibitor Schedule

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

    the display during removal until all items are removed from the TRAC Center. 2. Exhibitor space location assignments are at the discretion of the EXPO 2014 Exhibitor Lead. 3....

  1. Fuel economy and emissions reduction of HD hybrid truck over...

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

    Compares simulated fuel economy and emissions fro conventional and hybrid Class 8 heavy trucks p-12gao.pdf (345.05 KB) More Documents & Publications Advanced HD Engine Systems and ...

  2. MEMORANDUM TO: FILE - Oh'

    Office of Legacy Management (LM)

    ... of. Law NCJW York, New York 01 MATERIALS FRO3 DOB L ....-- --. -' - Norsrbt IO, 10x1 "uos.es Ca.e YIIe . -.. . . . . . . . Env. Prot. Bureau N.Y.S. Department of Law Nev ...

  3. B

    Gasoline and Diesel Fuel Update (EIA)

    ... Coal Mine Per mits " Abando ned Coal Min es Greater Green River Basin 0 40 80 20 Miles ... Field bou ndaries based on well data from Methane Energy (S. Pappajohn); Mines fro m ...

  4. Faroe Islands: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Country Profile Name Faroe Islands Population 48,351 GDP 2,450,000,000 Energy Consumption 0.01 Quadrillion Btu 2-letter ISO code FO 3-letter ISO code FRO Numeric ISO...

  5. Callpath Library

    Energy Science and Technology Software Center (OSTI)

    2013-11-09

    The "Callpath Library" is a software abstraction layer over a number of stack tracing utilities. It allows tool develoopers to conveniently represent and mNipulate call paths gathered fro U. Wisconsin's Stackwalker API and GNU Backtrace.

  6. To:

    Office of Legacy Management (LM)

    1985 B. Fritz ', C. Young F. I-loch BUSJECT: SPENCER CHEMICAL CO., JAYHAWK WORKS FRoM: S.E. Jones The Spencer Chemical Co. Jayhawks Works, and Joplin, Missouri, located between ...

  7. Transgenic Lignin Easier to Break Down for Biofuel - Energy Innovation

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

    of Energy Transformer Resilience and Advanced Components (TRAC) Program Transformer Resilience and Advanced Components (TRAC) Program To date, much of the "smart grid" transformation has focused on applying advanced digital information and communication technologies to the power grid to improve the system's reliability, resiliency, efficiency, flexibility, and security. To achieve the full value of grid modernization, advances in grid hardware are also needed. Next-generation

  8. Best-Estimate Analysis PWR LOCA.

    Energy Science and Technology Software Center (OSTI)

    2005-11-11

    Version: 00 TRAC‑PF1 performs best estimate analyses of loss of coolant accidents and other transients in pressurized light water reactors. The program can also be used to model a wide range of thermal hydraulic experiments in reduced scale facilities. Models employed include reflood, multi‑dimensional two‑phase flow, nonequilibrium thermodynamics, generalized heat transfer, and reactor kinetics. Automatic steady‑state and dump/restart capabilities are provided. The changes reported in TRACNEWS issues through Number 7 are incorporated in this release.more » TRAC-PF1 was developed on a CDC computer at Los Alamos National Laboratory. The PC version of TRAC‑PF1 was converted at CNEN in 1989 and has not been updated since that time. The NRC no longer supports the TRAC codes. They currently develop and maintain the TRACE code system, which is the TRAC/RELAP Advanced Computational Engine. TRACE is a modernized thermal-hydraulics code designed to consolidate the capabilities of NRC's 3 legacy safety codes - TRAC-P, TRAC-B and RELAP. This is NRC's flagship thermal-hydraulics analysis tool. See the website for more information http://www.nrccodes.com/.« less

  9. Rocky Flats 1990--91 winter validation tracer study: Volume 1

    SciTech Connect (OSTI)

    Brown, K.J.

    1991-10-01

    During the winter of 1990--91, North American Weather Consultants (NAWC) and its subcontractor, ABB Environmental Services (ABBES), conducted a Winter Validation Study (WVS) for EG&G Rocky Flats involving 12 separate tracer experiments conducted between February 3 and February 19, 1991. Six experiments were conducted during nighttime hours and four experiments were conducted during daytime hours. In addition, there was one day/night and one night/day transitional experiment conducted. The primary purpose of the WVS was to gather data to further the approval process for the Terrain Responsive Atmospheric Code (TRAC). TRAC is an atmospheric dispersion model developed and operated at the Department of Energy`s (DOE`s) Rocky Flats Plant (RFP) north of Denver, Colorado. A secondary objective was to gather data that will serve to validate the TRAC model physics.

  10. The AmAzing Journey of Columbia River Salmon B O N N E V I L

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

    2 WAiTing To hATch 1 reneWing The cycLe 10 reTurn ing To spAWning grounds 9 cLimbing fish LAdders 8 sWimming upsTreAm 7 Living in The oceAn 6 yolk sac redd alevin 3 Five...

  11. University of Maryland | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Maryland University of Maryland Team roster: Andrew Dallas, Aerospace Engineering; Mario Mondal, Aerospace Engineering; Atif Salahudeen, Aerospace Engineering; Matt Shumate, Aerospace Engineering; Emily Love, Mechanical Engineering; Austin Jacobson, Mechanical Engineering; Natalie Tham, Aerospace Engineering; Angelina Bingei, Finance and Marketing; Shriya Gupta, Finance and Information Systems; Jessica Ting, Marketing and Information Systems; Njeri Warrington, Marketing and Supply Chain

  12. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Room-temperature mid-infrared "M"-type GaAsSbInGaAs quantum well lasers on InP substrate Chang, Chia-Hao ; Li, Zong-Lin ; Pan, Chien-Hung ; Lu, Hong-Ting ; Lee, Chien-Ping ; Lin, ...

  13. A:>

    Office of Legacy Management (LM)

    CG:S- trac+* xii3 the3 folkmtig fabricakm3: Qlnxny 3,-dluu4SIxeL Carp, 2 Cont?acL 110, AT(Q--1)-12 thl4hSn Steel Corp. - AT( 30-4-1279 Aneriwrl Xachine EL Fou.ndr CoqaJ - ...

  14. Sand2004-0074

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

    ... s t i e d u p i n t h e r o o t b u i l d u p and metal hardware for typical root designs. ... fro ply drops, and simplified cutting and placement, with very low material wastage. ...

  15. A Theorem and its Application to Finite Tampers

    DOE R&D Accomplishments [OSTI]

    Feynman, R. P.

    1946-08-15

    A theorem is derived which is useful in the analysis of neutron problems in which all neutrons have the same velocity. It is applied to determine extrapolated end-points, the asymptotic amplitude from a point source, and the neutron density at the surface of a medium. Formulas fro the effect of finite tampers are derived by its aid, and their accuracy discussed.

  16. DOE/EIS-0068 F

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

    ... ap proxi matel y 367 TPD of wet sl u dge fro a typ i cal l i me- stone FGD scrubber . ... I l l i no i s are dry or nearl y so for si g n i f- i c ant porti ons of the year . ...

  17. SU-E-J-39: Comparison of PTV Margins Determined by In-Room Stereoscopic Image Guidance and by On-Board Cone Beam Computed Tomography Technique for Brain Radiotherapy Patients

    SciTech Connect (OSTI)

    Ganesh, T; Paul, S; Munshi, A; Sarkar, B; Krishnankutty, S; Sathya, J; George, S; Jassal, K; Roy, S; Mohanti, B

    2014-06-01

    Purpose: Stereoscopic in room kV image guidance is a faster tool in daily monitoring of patient positioning. Our centre, for the first time in the world, has integrated such a solution from BrainLAB (ExacTrac) with Elekta's volumetric cone beam computed tomography (XVI). Using van Herk's formula, we compared the planning target volume (PTV) margins calculated by both these systems for patients treated with brain radiotherapy. Methods: For a total of 24 patients who received partial or whole brain radiotherapy, verification images were acquired for 524 treatment sessions by XVI and for 334 sessions by ExacTrac out of the total 547 sessions. Systematic and random errors were calculated in cranio-caudal, lateral and antero-posterior directions for both techniques. PTV margins were then determined using van Herk formula. Results: In the cranio-caudal direction, systematic error, random error and the calculated PTV margin were found to be 0.13 cm, 0.12 cm and 0.41 cm with XVI and 0.14 cm, 0.13 cm and 0.44 cm with ExacTrac. The corresponding values in lateral direction were 0.13 cm 0.1 cm and 0.4 cm with XVI and 0.13 cm, 0.12 cm and 0.42 cm with ExacTrac imaging. The same parameters for antero-posterior were for 0.1 cm, 0.11 cm and 0.34 cm with XVI and 0.13 cm, 0.16 cm and 0.43 cm with ExacTrac imaging. The margins estimated with the two imaging modalities were comparable within ± 1 mm limit. Conclusion: Verification of setup errors in the major axes by two independent imaging systems showed the results are comparable and within ± 1 mm. This implies that planar imaging based ExacTrac can yield equal accuracy in setup error determination as the time consuming volumetric imaging which is considered as the gold standard. Accordingly PTV margins estimated by this faster imaging technique can be confidently used in clinical setup.

  18. Untitled Document

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

    Many high performance distributed applications use only a small fraction of their available bandwidth. A common cause of this problem is not a flaw in the application design, but rather improperly tuned net- work settings. Proper tuning techniques, such as set- ting the correct TCP buffers and using parallel streams, are well known in the networking commu- nity, but outside the networking community they are infrequently applied. In this paper, we describe a service that makes the task of network

  19. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Ting, C S" Name Name ORCID Product Type: All Book/Monograph Conference/Event Journal Article Miscellaneous Patent Program Document Software Manual Technical Report Thesis/Dissertation Subject: Identifier Numbers: Site: All Alaska Power Administration, Juneau, Alaska (United States) Albany Research Center (ARC), Albany, OR (United States) Albuquerque Complex - NNSA Albuquerque Operations Office, Albuquerque, NM (United States) Amarillo National Resource Center for Plutonium, Amarillo, TX

  20. Publications | ANSER Center | Argonne-Northwestern National Laboratory

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

    Publications Home > Research > Publications Search Publications Year Any Topic Any PI Any Just Published Amorphous transparent conducting oxides in context: Work function survey, trends, and facile modification Yeh, T. C.; Zhu, Q.; Buchholz, D. B.; Martinson, A. B. F.; Chang, R. P. H.; Mason, T. O.; Applied Surface Science 2015, 330 (0), 405-410. Post metalation of solvothermally grown electroactive porphyrin metal-organic framework thin films Kung, Chung-Wei; Chang, Ting-Hsiang; Chou,

  1. Advanced Algal Systems

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Algal Systems Research and development (R&D) on advanced algal biofuels and bio- products presents an opportunity to sustainably expand biomass resource potential in the United States. The Bio- energy Technologies Office's (BETO's) Advanced Algal Systems Program is carrying out a long-term, applied R&D strategy to lower the costs of algal biofuel production by working with partners to develop revolutionary technologies and conduct crosscut- ting analyses to better understand the

  2. Bearing design for flywheel energy storage using high-TC superconductors

    DOE Patents [OSTI]

    Hull, John R.; Mulcahy, Thomas M.

    2000-01-01

    A high temperature superconductor material bearing system (38) This system (38) includes a rotor (50) having a ring permanent magnet (60), a plurality of permanent magnets (16, 20 and 70) for interacting to generate levitation forces for the system (38). This group of magnets are a push/pull bearing (75). A high temperature superconductor structure (30) interacts with the ting permanent magnet (60) to provide stabilizing forces for the system (38).

  3. ALSNews Vol. 337

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

    7 Print Guided Self-Assembly of Gold Thin Films A team of UC Berkeley and Berkeley Lab researchers have developed a relatively easy, inexpensive, and scalable technique to direct the self--assembly of gold nanoparticles into device-ready thin films, which have potential applications in fields ranging from energy harvesting to plasmonics. Read more... Contact: TIng Xu Studies Bolster Promise of Topological Insulators Topological insulators are highly promising materials for electronic

  4. ALSNews Vol. 337

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

    7 Print Guided Self-Assembly of Gold Thin Films A team of UC Berkeley and Berkeley Lab researchers have developed a relatively easy, inexpensive, and scalable technique to direct the self--assembly of gold nanoparticles into device-ready thin films, which have potential applications in fields ranging from energy harvesting to plasmonics. Read more... Contact: TIng Xu Studies Bolster Promise of Topological Insulators Topological insulators are highly promising materials for electronic

  5. ALSNews Vol. 337

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

    7 Print Guided Self-Assembly of Gold Thin Films A team of UC Berkeley and Berkeley Lab researchers have developed a relatively easy, inexpensive, and scalable technique to direct the self--assembly of gold nanoparticles into device-ready thin films, which have potential applications in fields ranging from energy harvesting to plasmonics. Read more... Contact: TIng Xu Studies Bolster Promise of Topological Insulators Topological insulators are highly promising materials for electronic

  6. ALSNews Vol. 337

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

    7 Print Guided Self-Assembly of Gold Thin Films A team of UC Berkeley and Berkeley Lab researchers have developed a relatively easy, inexpensive, and scalable technique to direct the self--assembly of gold nanoparticles into device-ready thin films, which have potential applications in fields ranging from energy harvesting to plasmonics. Read more... Contact: TIng Xu Studies Bolster Promise of Topological Insulators Topological insulators are highly promising materials for electronic

  7. ALSNews Vol. 337

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

    ALSNews Vol. 337 Print Guided Self-Assembly of Gold Thin Films A team of UC Berkeley and Berkeley Lab researchers have developed a relatively easy, inexpensive, and scalable technique to direct the self--assembly of gold nanoparticles into device-ready thin films, which have potential applications in fields ranging from energy harvesting to plasmonics. Read more... Contact: TIng Xu Studies Bolster Promise of Topological Insulators Topological insulators are highly promising materials for

  8. Center for Advanced Photophysics | Publications

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

    CASP Publications Velizhanin, Kirill A.; and Saxena, Avadh Excitonic effects in two-dimensional semiconductors: Path integral Monte Carlo approach Physical Review B, 92, 195305 (2015). [DOI: 10.1103/PhysRevB.92.195305] [CASP] more details Chen, Ting; Reich, K. V.; Kramer, Nicolaas J.; Fu, Han; Kortshagen, Uwe R.; and Shklovskii, B. I. Metal-insulator transition in films of doped semiconductor nanocrystals Nature Materials, advance online publication, (2015). [DOI: 10.1038/nmat4486] [CASP] more

  9. 2009-2010 Academic Year Internship Projects | Center for Energy Efficient

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

    Materials 2009-2010 Academic Year Internship Projects Name Mentor Advisor Major Project Title Garrett Brinkley Kristen Murphy Galen Stucky Biochemistry Elution of Bacteriophage for the Advancement of Photovoltaic Cells Nathaniel Brunner-Taulbee Jordan Lang James S. Speck Physics/Astronomy Nitride Based Solar Cells by MBE Charles Buhler Je-Hyeong Bahk / Chieh-Ting Lin John Bowers Physics Solar Cell Thermoelectrics Eneida Chesnut Dr. Mingfeng Wang Fred Wudl Chemical Engineering Synthesis of

  10. TOOKUIL: A case study in user interface development for safety code application

    SciTech Connect (OSTI)

    Gray, D.L.; Harkins, C.K.; Hoole, J.G.

    1997-07-01

    Traditionally, there has been a very high learning curve associated with using nuclear power plant (NPP) analysis codes. Even for seasoned plant analysts and engineers, the process of building or modifying an input model for present day NPP analysis codes is tedious, error prone, and time consuming. Current cost constraints and performance demands place an additional burden on today`s safety analysis community. Advances in graphical user interface (GUI) technology have been applied to obtain significant productivity and quality assurance improvements for the Transient Reactor Analysis Code (TRAC) input model development. KAPL Inc. has developed an X Windows-based graphical user interface named TOOKUIL which supports the design and analysis process, acting as a preprocessor, runtime editor, help system, and post processor for TRAC. This paper summarizes the objectives of the project, the GUI development process and experiences, and the resulting end product, TOOKUIL.

  11. Combustion modeling in waste tanks

    SciTech Connect (OSTI)

    Mueller, C.; Unal, C.; Travis, J.R. |

    1997-08-01

    This paper has two objectives. The first one is to repeat previous simulations of release and combustion of flammable gases in tank SY-101 at the Hanford reservation with the recently developed code GASFLOW-II. The GASFLOW-II results are compared with the results obtained with the HMS/TRAC code and show good agreement, especially for non-combustion cases. For combustion GASFLOW-II predicts a steeper pressure rise than HMS/TRAC. The second objective is to describe a so-called induction parameter model which was developed and implemented into GASFLOW-II and reassess previous calculations of Bureau of Mines experiments for hydrogen-air combustion. The pressure time history improves compared with the one-step model, and the time rate of pressure change is much closer to the experimental data.

  12. On the explanation and calculation of anomalous reflood hydrodynamics in large PWR cores

    SciTech Connect (OSTI)

    Rodriguez, S.E.

    1985-01-01

    Reflood hydrodynamics from large-scale (1:20) test facilities in Japan have yielded apparently anomalous behavior relative to FLECHT tests. Namely, even at reflooding rates below one inch per second, very large liquid volume fractions (10-15%) exist above the quench fronts shortly after flood begins; thus cladding temperature excursions are terminated early in the reflood phase. This paper discusses an explanation for this behavior: liquid films on the core's unheated rods. The experimental findings are shown to be correctly simulated with a new four-field (vapor, films, droplets) version of the best-estimate TRAC-PF1 computer code, TRAC-FF. These experimental and analytical findings have important implications for PWR large-break LOCA licensing.

  13. Sensivitity improvement in low-profile distributed detector systems for tracking sources in transit.

    SciTech Connect (OSTI)

    Vilim, R. B.; Klann, R.; Campos, C.; Medley, T.; Nuclear Engineering Division

    2007-01-01

    The RadTrac real-time detection and tracking software runs on a laptop computer networked to gamma-radiation detectors. A probabilistic estimate for source position is generated by combining measured count rate data with a first-principles stochastic model for the space and time dependence of count rates and knowledge of detector intrinsic efficiency. Recent development work has focused on improving RadTrac sensitivity in low-count rate situations. A method has been developed for processing count rates by energy according to that part of the energy spectrum with the greatest signal-to-noise ratio. In addition a method has been developed that places constraints on the solution that are physically appropriate when count rates approach background. In both instances experiments with a weak source confirmed the uncertainty in estimated position is reduced.

  14. EXPO 2016 Sponsors - Hanford Site

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

    2016 Sponsors About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO EXPO 2016 Sponsors Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size The EXPO Planning Team would like to thank all the companies who support the Health & Safety EXPO by providing funds,

  15. EXPO Award Criteria - Hanford Site

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

    Award Criteria About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO EXPO Award Criteria Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size WRPS won the awards for Most Interactive and Best Overall booth! WRPS won the awards for Most Interactive and Best

  16. Why Should I Participate in EXPO - Hanford Site

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

    Why Should I Participate in EXPO About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO Why Should I Participate in EXPO Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size The Health & Safety EXPO is a sharing of information, equipment, supplies, success

  17. Electronic Registration Form - Hanford Site

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

    About Us Hanford Site Wide Programs Health & Safety Exposition Electronic Registration Form About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO Electronic Registration Form Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size * Fields marked with an

  18. Exhibits - Hanford Site

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

    About Us Hanford Site Wide Programs Health & Safety Exposition Exhibits About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO Exhibits Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size If you are interested in having an exhibit in EXPO 2014, please see

  19. Charging Your Time - Hanford Site

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

    Health & Safety Exposition Charging Your Time About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO Charging Your Time Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size How Do I Charge My Time Spent at EXPO? Each Hanford Prime Contractor may have

  20. Exhibitor and Vendor Information - Hanford Site

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

    About Us Hanford Site Wide Programs Health & Safety Exposition Exhibitor and Vendor Information About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO Exhibitor and Vendor Information Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size If you are interested

  1. Fuel economy and emissions reduction of HD hybrid truck over transient

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    driving cycles and interstate roads | Department of Energy economy and emissions reduction of HD hybrid truck over transient driving cycles and interstate roads Fuel economy and emissions reduction of HD hybrid truck over transient driving cycles and interstate roads Compares simulated fuel economy and emissions fro conventional and hybrid Class 8 heavy trucks p-12_gao.pdf (345.05 KB) More Documents & Publications Advanced HD Engine Systems and Emissions Control Modeling and Analysis

  2. Testing of hollow clay tile masonry prisms

    SciTech Connect (OSTI)

    Jones, W.D.; Butala, M.B.

    1993-10-15

    This paper presents test results of 610-mm wide (24-in.) by 1219-mm high (48-in.) by 203-or 330-mm (8- or 13-in.) thick prisms constructed of hollow clay tiles. Three prisms were extracted fro existing hollow clay title walls and 69 were constructed in laboratories at The University of Tennessee and the National Institute of Standards and Technology (NIST) in Gaithersburg, Maryland. Modulus of Elasticity, E, and compressive strength f{prime}{sub m} were calculated from the results.

  3. Results of an emergency response atmospheric dispersion model comparison using a state accepted statistical protocol

    SciTech Connect (OSTI)

    Ciolek, J.T. Jr.

    1993-10-01

    The Rocky Flats Plant, located approximately 26 km northwest of downtown Denver, Colorado, has developed an emergency response atmospheric dispersion model for complex terrain applications. Plant personnel would use the model, known as the Terrain-Responsive Atmospheric Code (TRAC) (Hodgin 1985) to project plume impacts and provide off-site protective action recommendations to the State of Colorado should a hazardous material release occur from the facility. The Colorado Department of Health (CDH) entered into an interagency agreement with the Rocky Flats Plant prime contractor, EG&G Rocky Flats, and the US Department of Energy to evaluate TRAC as an acceptable emergency response tool. After exhaustive research of similar evaluation processes from other emergency response and regulatory organizations, the interagency committee devised a formal acceptance process. The process contains an evaluation protocol (Hodgin and Smith 1992), descriptions of responsibilities, an identified experimental data set to use in the evaluation, and judgment criteria for model acceptance. The evaluation protocol is general enough to allow for different implementations. This paper explains one implementation, shows protocol results for a test case, and presents results of a comparison between versions of TRAC with different wind Field codes: a two dimensional mass consistent code called WINDS (Fosberg et al. 1976) that has been extended to three dimensions, and a fully 3 dimensional mass conserving code called NUATMOS (Ross and Smith 1987, Ross et al. 1988).

  4. SU-E-J-48: Imaging Origin-Radiation Isocenter Coincidence for Linac-Based SRS with Novalis Tx

    SciTech Connect (OSTI)

    Geraghty, C; Workie, D; Hasson, B

    2015-06-15

    Purpose To implement and evaluate an image-based Winston-Lutz (WL) test to measure the displacement between ExacTrac imaging origin and radiation isocenter on a Novalis Tx system using RIT V6.2 software analysis tools. Displacement between imaging and radiation isocenters was tracked over time. The method was applied for cone-based and MLC-based WL tests. Methods The Brainlab Winston-Lutz phantom was aligned to room lasers. The ExacTrac imaging system was then used to detect the Winston- Lutz phantom and obtain the displacement between the center of the phantom and the imaging origin. EPID images of the phantom were obtained at various gantry and couch angles and analyzed with RIT calculating the phantom center to radiation isocenter displacement. The RIT and Exactrac displacements were combined to calculate the displacement between imaging origin and radiation isocenter. Results were tracked over time. Results Mean displacements between ExacTrac origin and radiation isocenter were: VRT: −0.1mm ± 0.3mm, LNG: 0.5mm ± 0.2mm, LAT: 0.2mm ± 0.2mm (vector magnitude of 0.7 ± 0.2mm). Radiation isocenter was characterized by the mean of the standard deviations of the WL phantom displacements: σVRT: 0.2mm, σLNG: 0.4mm, σLAT: 0.6mm. The linac couch base was serviced to reduce couch walkout. This reduced σLAT to 0.2mm. These measurements established a new baseline of radiation isocenter-imaging origin coincidence. Conclusion The image-based WL test has ensured submillimeter localization accuracy using the ExacTrac imaging system. Standard deviations of ExacTrac-radiation isocenter displacements indicate that average agreement within 0.3mm is possible in each axis. This WL test is a departure from the tradiational WL in that imaging origin/radiation isocenter agreement is the end goal not lasers/radiation isocenter.

  5. From the Proton Synchroton to the Large Hadron Collider - 50 Years of Nobel Memories in High-Energy Physics

    ScienceCinema (OSTI)

    None

    2011-10-06

    The seminars will be held in the Main Auditorium with transmission to : Council Chamber, IT Auditorium, Prvessin BE Auditorium , Kjell Johnssen Auditorium in Building 30, Room 40-S2-A01, and via webcast. Confirmed Speakers include: Prof. Jack Steinberger, Dr. Guenther Plass, Prof. Emilio Picasso, Dr. Steve Myers, Prof. Carlo Rubbia, Prof. Burton Richter, Dr. Lyndon Evans, Prof. Rolf-Dieter Heuer, Prof. Leon Lederman, Prof. Jim Cronin, Prof. Sheldon Glashow, Prof. Jerome Friedman, Prof. Frank Wilczek, Prof. Martinus Veltman, Prof. Gerardus 't Hooft, Prof. David Gross, Prof. Samuel Ting, Prof. Steven Weinberg (via teleconference) --- Contact: Directorate.Office@cern.ch

  6. HADRON AND PHOTON PRODUCTION OF J PARTICLES AND THE ORIGIN OF J PARTICLES

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

    COO.306?, 3'^ 7 HADRON AND PHOTON PRODUCTION OF J PARTICLES AND THE ORIGIN OF J PARTICLES Samuel C.C.Ting Department of Physics and Laboratory for Nuclear Science Massachusetts Institute of Technology RECEIVED BY TIC MlG 5 1975 A Rapporteur's Summary at the International Conference on High Energy Physics btil Palermo, Sicily. June, 1975 'W^'i'Lll DISTRIBUTION OFTHIS DOCUJvlLMi uMUMltrsP DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States

  7. From the Proton Synchroton to the Large Hadron Collider - 50 Years of Nobel Memories in High-Energy Physics

    ScienceCinema (OSTI)

    None

    2011-10-06

    The seminars will be held in the Main Auditorium with transmission to : Council Chamber, IT Auditorium, Prévessin BE Auditorium , Kjell Johnssen Auditorium in Building 30, Room 40-S2-A01, and via webcast. Confirmed Speakers include: Prof. Jack Steinberger, Dr. Guenther Plass, Prof. Emilio Picasso, Dr. Steve Myers, Prof. Carlo Rubbia, Prof. Burton Richter, Dr. Lyndon Evans, Prof. Rolf-Dieter Heuer, Prof. Leon Lederman, Prof. Jim Cronin, Prof. Sheldon Glashow, Prof. Jerome Friedman, Prof. Frank Wilczek, Prof. Martinus Veltman, Prof. Gerardus 't Hooft, Prof. David Gross, Prof. Samuel Ting, Prof. Steven Weinberg (via teleconference) --- Contact: Directorate.Office@cern.ch

  8. Summary - ASCEM Review

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ETR R Un ASCEM EM is ground world. passiv at DOE Advan Manag state-o unders transp ASCE predict identify calcula quantif The re docum Implem inform The pr and st time of condu review The pu techni projec Site: A roject: E Report Date: S ited States Peer R Why DOE M Model Diagram faced with one dwater and soi A major goal ve remediation E sites. To aid nced Simulation gement (ASCE of-the-art scien standing and p port in natural a M modeling too ting releases fr ying exposure ations, and con

  9. LOCA feasibility study of Almaraz NPP 110% power up-rate

    SciTech Connect (OSTI)

    Orive, Raul; Gallego, Ines; Garcia, Pablo; Concejal, Alberto; Martinez-Murillo, Juan-Carlos

    2006-07-01

    Knowledge about accidents and fuel response in extreme conditions has progressed in parallel with the simulation tools development and consequently results are today highly satisfactory. This fact allows nuclear power plants (NPP) to carry out optimization processes of its operation and yield improvements due to the development of new methodologies and tools. Power up-rates open a demand in areas like the analyses of Loss Of Coolant Accidents (LOCA's), which impact on plant design may limit the maximum operation power in a nuclear power plant. TRAC-PF1 is a thermal-hydraulic calculation code that allows the complete treatment of two-phase flows in balance, combining a three dimensional vessel, that simulates in detail the accident phenomena, with one dimensional components. TRAC-PF1 code capacities in the reproduction of experiments, transients and accidents have been widely proved. IBERINCO has modified the original code to develop a conservative model applicable to a 3-loop Westinghouse NPP. These circumstances have allowed Almaraz NPP to get deeper in the study of the plant behaviour during a LOCA, after a hypothetical Power Up-rate. The scope of the study includes the development of the plant model and the reproduction of several accidents with loss of coolant. These accidents have been simulated with the improved option and the conservative version of the modified code (TRAC-PF1/IBER). The limiting case at the current power is analyzed in 110% Power Up-rate conditions and different sensitivity studies are performed, focused in impact of axial power distribution, discharge coefficients and emergency core cooling system availability. These studies allow to verify the effectiveness of Almaraz NPP safety systems in LOCA scenarios to guarantee the required safety margins. (authors)

  10. An analytical study on excitation of nuclear-coupled thermal-hydraulic instability due to seismically induced resonance in BWR

    SciTech Connect (OSTI)

    Hirano, Masashi

    1997-07-01

    This paper describes the results of a scoping study on seismically induced resonance of nuclear-coupled thermal-hydraulic instability in BWRs, which was conducted by using TRAC-BF1 within a framework of a point kinetics model. As a result of the analysis, it is shown that a reactivity insertion could occur accompanied by in-surge of coolant into the core resulted from the excitation of the nuclear-coupled instability by the external acceleration. In order to analyze this phenomenon more in detail, it is necessary to couple a thermal-hydraulic code with a three-dimensional nuclear kinetics code.

  11. American Red Cross Blood Drive Hanford Health and Safety Exposition

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

    Red Cross Blood Drive Hanford Health and Safety Exposition 6600 Burden Blvd. - TRAC Center Tuesday,May13,2014 10:00 AM - 3:00 PM To schedule your appointment go online to www.redcrossblood.org/make- donation, enter EXPO for sponsor code and follow further instructions. redcrossblood.org I 1-800-RED CROSS (1-800 - 733-2767) [!] ........ Use your smartphone to scan the OR code at left, or go to redcrossblood .org/social to follow us on Facebook and Twitter. Identif ication is requ ired to don ate.

  12. Fuel performance during severe accidents. [PWR

    SciTech Connect (OSTI)

    Buescher, B.J.; Gruen, G.E.; MacDonald, P.E.

    1982-01-01

    As a result of the Three Mile Island Unit-2 (TMI-2) accident, the Nuclear Regulatory Commission has initiated a severe fuel damage test program to evaluate fuel rod and core response during severe accidents similar to TMI-2. This program is underway in the Power Burst Facility at the Idaho National Engineering Laboratory. In preparation for the first test, predictions have been performed using the TRAC-BD1 computer. This paper presents the calculated results showing a slow heatup to 2400 K over 5 hours, and the analysis includes accelerated oxidation of the zirconium cladding at temperatures above 1850 K.

  13. Meteorological conditions during the winter validation study at Rocky Flats, Colorado: An overview

    SciTech Connect (OSTI)

    Hodgin, C.R.

    1991-11-06

    The objective for the Winter Validation Study was to gather field data for validation of the Terrain-Responsive Atmospheric Code (TRAC) under winter time meteorological conditions. Twelve tracer tests were conducted during a two-week period in February 1991. Each test lasted 12 hours, with releases of SF{sub 6} tracer from the Rocky Flats Plant near Golden, Colorado. The tests included ground-based and airborne sampling to 16 km from the release point. This presentation summarizes meteorological conditions during the testing period. Forty six viewgraphs are included.

  14. Calculation of the temperature in the container unit with a modified design for the production of {sup 99}Mo at the VVR-Ts research reactor facility (IVV.10M)

    SciTech Connect (OSTI)

    Kazantsev, A. A.; Sergeev, V. V.; Kochnov, O. Yu.

    2015-12-15

    The temperature regime is calculated for two different designs of containers with uranium-bearing material for the upgraded VVR-Ts research reactor facility (IVV.10M). The containers are to be used in the production of {sup 99}Mo. It is demonstrated that the modification of the container design leads to a considerable temperature reduction and an increase in the near-wall boiling margin and allows one to raise the amount of material loaded into the container. The calculations were conducted using the international thermohydraulic contour code TRAC intended to analyze the technical safety of water-cooled nuclear power units.

  15. "Green Launching Pad" Supports Clean Energy Small Businesses | Department

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of Energy "Green Launching Pad" Supports Clean Energy Small Businesses "Green Launching Pad" Supports Clean Energy Small Businesses May 24, 2012 - 2:01pm Addthis Green Launching Pad 2.0 awards ceremony with Secretary Chu, Gov. John Lynch, and UNH President Mark Huddleston held at EnerTrac, Inc., in Hudson, NH. | Courtesy of University of New Hampshire Photographic Services Green Launching Pad 2.0 awards ceremony with Secretary Chu, Gov. John Lynch, and UNH President Mark

  16. http://www

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

    Instruments and the Probes to which they are attached CHAPS 07 G-1 Instruments rev. 07-2-20 Instrument CVI non-CVI Gases Other PI TSI-3563 Neph 1 Ogren/Andrews TSI-3010 CPC 1 Ogren/Andrews PSAP Radiance 0 Laulainen PSAP NOAA 1 Ogren/Andrews AMS 1 Lee/Alexander FIMS 1 Wang LAPA-1 1 Dubey TRAC 1 Laskin TDL H2O 1 Ogren/Andrews CVI control 1 Ogren/Andrews CVI flow meters ? Ogren/Andrews CVI pumps 2 Ogren/Andrews CVI heat 0 Ogren/Andrews CVI zero air bottle 1 Ogren/Andrews CVI data system 1

  17. ,=SIGR AKD PROL'UEim HISTORY OF

    Office of Legacy Management (LM)

    =SIGR AKD PROL'UEim HISTORY /----------. OF u. 9, coliTRAcT w-74l2-FZG-1 Dcprtrnent of Energy Savannah R' ber Operations Of fii PCIBOXA Aiken. South Carolina 29801 B. I. du Pant de Neraure sad Company Alken, SC 2980s Dear Nr. Becheyars volume II, Design and Pmcurernurt Eistory of B&ford Engineer Work# and cliuton Sed-Worka, baa been reviewed for declssslficatim ln reapouae to a request fma 6. U. 0'lUs.r. xnltial revi& request was fa-aln L. ?. shal?nn&, AES, wl.ldngtoo, tq 6. n. O'

  18. Microsoft Word - Aerosol Working Group_Norfolk 2008.doc

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

    ARM Aerosol Working Group, Agenda, Monday, March 10, 2008 15:00 0:13 Flynn 4STAR - a next-generation spectrometer for sky-scanning solar tracking radiometry 15:13 0:13 Yu FastTRAC 15:26 0:13 Obland Initial Airborne High Spectral Resolution Lidar (HSRL) Results from the Cumulus Humilis Aerosol Processing Study (CHAPS) and Cloud and Land Surface Interaction Campaign (CLASIC) 15:39 0:13 Kim Efficacy of Aerosol - Cloud Interactions Under Varying Meteorological Conditions: Southern Great Plains Vs.

  19. / J8Y.17 I E(DE86008418)

    Office of Legacy Management (LM)

    /,, DOE/EIS-0109F / J8Y.17 I E(DE86008418) O&4 .48 FINAL Environmental Impact Statement Long-Term Management of the Existing Radioactive Wastes and Residues at the Niagara Falls Storage Site ( Se(42Ho- /,02.F7fro^' t^ K- A~-) April 1986 U. S. Department of Energy Washington, D.C. 20585 DOE/EIS-0109F (DE86008418) Distribution Category UC-70A FINAL ENVIRONMENTAL IMPACT STATEMENT LONG-TERM MANAGEMENT OF THE EXISTING RADIOACTIVE WASTES AND RESIDUES AT THE NIAGARA FALLS STORAGE SITE April 1986

  20. Summary - Small Column Ion Exchange (SCIX)Technology at the SRS

    Office of Environmental Management (EM)

    ETR R Un Baseline The Sm being The SC operat which Sr, and waste critical the SC deploy Specif exchan [CST]) CST, a (mono and so (RMF) maturi readin design moving The pu techni projec Site: S roject: S E Report Date: F ited States Sma Why DOE e SCIX System Pr mall Column Io developed at S CIX system is tions (ion excha function to rem d actinides) fro and prepare th l technology ele CIX system tha yment and thes fically the critica nge on a selec ) housed in an actinide and Sr osodium titanat

  1. INTERO)CPICE CORRC-NOKNCL

    Office of Legacy Management (LM)

    s.u-or:.L~ p40.0-0(-b INTERO)CPICE CORRC-NOKNCL 7117-01.85.sej.08 TO: File cc: A. Wallo DATE: 27 March 1985 B. Fritz C. Young F. Hoch SUmJECT: SPENCER CHEMICAL CO., JAYHAWK WORKS A@-+ FRoMz S.E. Jones The Spencer Chemical Co. Jayhawks Works, and Joplin, Missouri, located between Pittsburg, Kansas was licensed b!!.the NRC undersource Material License C-4352 and Special NuclearMaterial Licenses SNM-154 to operate a uranium oxide pilot plant, and SNM-329 to process enriched uranium (for other

  2. Big Thinking: The Power of Nanoscience (LBNL Science at the Theater)

    SciTech Connect (OSTI)

    Milliron, Delia; Sanili, Babak; Weber-Bargioni, Alex; Xu, Ting

    2011-06-06

    Science at the Theater, June 6th, 2011: Berkeley Lab scientists reveal how nanoscience will bring us cleaner energy, faster computers, and improved medicine. Alex Weber-Bargioni: How can we see things at the nanoscale? Alex is pioneering new methods that provide unprecedented insight into nanoscale materials and molecular interactions. The goal is to create rules for building nanoscale materials. Babak Sanii: Nature is an expert at making nanoscale devices such as proteins. Babak is developing ways to see these biological widgets, which could help scientists develop synthetic devices that mimic the best that nature has to offer. Ting Xu: How are we going to make nanoscale devices? A future in which materials and devices are able to assemble themselves may not be that far down the road. Ting is finding ways to induce a wide range of nanoscopic building blocks to assemble into complex structures. Delia Milliron: The dividends of nanoscience could reshape the way we live, from smart windows and solar cells to artificial photosynthesis and improved medical diagnosis. Delia is at the forefront of converting fundamental research into nanotechnology. Moderated by Jim DeYoreo, interim director of the Molecular Foundry, a facility located at Berkeley Lab where scientists from around the world address the myriad challenges in nanoscience.

  3. Spent fuel pool analysis using TRACE code

    SciTech Connect (OSTI)

    Sanchez-Saez, F.; Carlos, S.; Villanueva, J. F.; Martorell, S.

    2012-07-01

    The storage requirements of Spent Fuel Pools have been analyzed with the purpose to increase their rack capacities. In the past, the thermal limits have been mainly evaluated with conservative codes developed for this purpose, although some works can be found in which a best estimate code is used. The use of best estimate codes is interesting as they provide more realistic calculations and they have the capability of analyzing a wide range of transients that could affect the Spent Fuel Pool. Two of the most representative thermal-hydraulic codes are RELAP-5 and TRAC. Nowadays, TRACE code is being developed to make use of the more favorable characteristics of RELAP-5 and TRAC codes. Among the components coded in TRACE that can be used to construct the model, it is interesting to use the VESSEL component, which has the capacity of reproducing three dimensional phenomena. In this work, a thermal-hydraulic model of the Maine Yankee spent fuel pool using the TRACE code is developed. Such model has been used to perform a licensing calculation and the results obtained have been compared with experimental measurements made at the pool, showing a good agreement between the calculations predicted by TRACE and the experimental data. (authors)

  4. Effect of bubbly/slug interfacial shear on liquid carryover predicted by RELAP5/MOD2 during reflooding

    SciTech Connect (OSTI)

    Analytis, G.T.; Richner, M.

    1986-01-01

    Analysis of very low flooding rate reflooding experiments and one boiloff experiment in the 33 electrically heated rod bundle NEPTUN at EIR with RELAP5/MOD2/36.02 has shown that the code grossly overpredicts the liquid carryover. Similar results have been reported in the analysis of a large number of boiloff experiments in NEPTUN with TRAC-BD1/MOD1. In this case, the differences between measurements and predictions were attributed to the large bubble/slug interfacial shear in TRAC-BD1 and excellent agreement with the measurements was achieved by implementing in this code a slightly modified version of a new bubbly/slug interfacial shear correlation developed for rod bundles. As far as reflooding is concerned, one of the most crucial parameters for the correct prediction of the rod surface temperature histories is the interfacial shear f/sub i/ in the different flow regimes; it is precisely this term that will largely determine the liquid fraction at a certain axial elevation, and the liquid carryover. In the paper, the authors outline the implementation of the new bubble/slug f/sub i/ correlation in RELAP5/MOD2/36.02 and assess its influence in the liquid carryover in the analysis of low flooding rate experiments in NEPTUN.

  5. Task completion report for update FXFILL

    SciTech Connect (OSTI)

    Steinke, R.G.

    1997-09-02

    The FILL component in TRAC-P defines a phasic-velocities boundary condition or total-mass-flow boundary condition. FILL option IFTY = 10 defines the total-mass flow and its composition for flow donoring from the FILL to its adjacent component by signal variables and/or control blocks. For flow from the adjacent component to the FILL component, the phasic densities of the adjacent-component cell need to be upstream donored by the IFTY = 10 option total-mass flow. Instead, the FILL-cell phasic densities are being downstream donored incorrectly by the IFTY = 10 option total-mass flow in determining the FILL-junction phasic velocities. Using the wrong donored phasic densities caused the phasic velocities determined from the total-mass flow to be evaluated incorrectly. Five errors related to phasic-density donoring into a FILL- or BREAK-component cell are corrected by update FXFILL. Seven versions of a new test problem test these corrections and show that the errors of trouble reports 189 and 190 no longer exist in TRAC-P.

  6. Computer analyses for the design, operation and safety of new isotope production reactors: A technology status review

    SciTech Connect (OSTI)

    Wulff, W.

    1990-01-01

    A review is presented on the currently available technologies for nuclear reactor analyses by computer. The important distinction is made between traditional computer calculation and advanced computer simulation. Simulation needs are defined to support the design, operation, maintenance and safety of isotope production reactors. Existing methods of computer analyses are categorized in accordance with the type of computer involved in their execution: micro, mini, mainframe and supercomputers. Both general and special-purpose computers are discussed. Major computer codes are described, with regard for their use in analyzing isotope production reactors. It has been determined in this review that conventional systems codes (TRAC, RELAP5, RETRAN, etc.) cannot meet four essential conditions for viable reactor simulation: simulation fidelity, on-line interactive operation with convenient graphics, high simulation speed, and at low cost. These conditions can be met by special-purpose computers (such as the AD100 of ADI), which are specifically designed for high-speed simulation of complex systems. The greatest shortcoming of existing systems codes (TRAC, RELAP5) is their mismatch between very high computational efforts and low simulation fidelity. The drift flux formulation (HIPA) is the viable alternative to the complicated two-fluid model. No existing computer code has the capability of accommodating all important processes in the core geometry of isotope production reactors. Experiments are needed (heat transfer measurements) to provide necessary correlations. It is important for the nuclear community, both in government, industry and universities, to begin to take advantage of modern simulation technologies and equipment. 41 refs.

  7. (The design and construction of the proposed L* detector for the Superconducting Super Collider)

    SciTech Connect (OSTI)

    Bugg, W.M.

    1990-10-23

    Dr. William M. Bugg and a group from ORNL had very productive meetings with Professor Sam Ting and other members of the L3 collaboration. The L3 detector system, subsystems, and the associated support facilities were examined in some detail. Discussions were held with scientists involved in planning for the L* detector systems and members of the L3 staff interested in positions at ORNL/UTK. The trip was very successful. A collaborative arrangement was established for UTK and ORNL to become involved in the future design and construction of the L* detector. These include hosting the main meeting of the L* collaboration at ORNL to complete the Expression-of-Interest (EOI) proposal. Several prospective candidates were interviewed and collaborative interactions were started on some detector subsystems for L*.

  8. Portable Doppler interferometer system for shock diagnostics and high speed motion

    SciTech Connect (OSTI)

    Fleming, K.J.; Crump, O.B. Jr.

    1994-05-01

    VISAR (Velocity Interferometer System for Any Reflector) is a system that uses the Doppler effect and is widely used for measuring the velocity of projectiles, detonations, flying plates, shock pressures (particle velocity) and other high speed/high acceleration motion. Other methods of measurement such as accelerometers and pressure gauges have disadvantages in that they are sensitive to radiation, electromagnetic pulses, and their mass can drastically alter the velocity of the projectile. VISAR uses single frequency-single mode laser fight focused onto a target of interest. Reflected fight from the target is collected and sent through a modified, unequal leg Michelson interferometer. In the interferometer the light is split into two components which travel through the legs of the interferometer cavity and are then recombined. When the light recombines, an interference pattern is created which can range from dark (destructive interference) to bright (constructive interference). When the target moves, the reflected laser light experiences a frequency shift (increase) with respect to the frequency from the target in a static condition. Since the Doppler shifted light is split and routed through an unequal leg interferometer cavity, there is a time lag of the light containing the Doppler information at the recombination point in the interferometer. The effect of the time lag is to create a sinusoidally changing interference pattern (commonly called fringes). Since the interferometer time delay, laser wavelength, and the speed of light are known, an accurate measurement of target velocity/acceleration may be measured by analyzing both the number of tinges and the speed of tinge generation (system accuracy is 3--4%).

  9. Status of thermalhydraulic modelling and assessment: Open issues

    SciTech Connect (OSTI)

    Bestion, D.; Barre, F.

    1997-07-01

    This paper presents the status of the physical modelling in present codes used for Nuclear Reactor Thermalhydraulics (TRAC, RELAP 5, CATHARE, ATHLET,...) and attempts to list the unresolved or partially resolved issues. First, the capabilities and limitations of present codes are presented. They are mainly known from a synthesis of the assessment calculations performed for both separate effect tests and integral effect tests. It is also interesting to list all the assumptions and simplifications which were made in the establishment of the system of equations and of the constitutive relations. Many of the present limitations are associated to physical situations where these assumptions are not valid. Then, recommendations are proposed to extend the capabilities of these codes.

  10. Code System for Best-Estimate Analysis of LOCA in BWR.

    Energy Science and Technology Software Center (OSTI)

    2001-07-23

    Version 00 TRAC-BD1 performs best estimate analyses of loss-of-coolant accidents (LOCA) and other transients in boiling water reactors (BWRs). The program provides LOCA analysis capability for BWRs and for many BWR-related thermal-hydraulic experimental facilities. The program features a three-dimensional treatment of the BWR pressure vessel, a detailed model of a BWR fuel bundle including multi-rod, multi-bundle, radiation heat transfer, and leakage path modeling capability; flow-regime-dependent constitutive equation treatment; reflood tracking capability both for falling filmsmore » and bottom flood quench fronts; and consistent treatment of the entire accident sequence. Dump/restart capabilities are also provided.« less

  11. Small-break loss-of-coolant accidents in the updated PIUS 600 advanced reactor design

    SciTech Connect (OSTI)

    Boyack, B.E.; Steiner, J.L.; Harmony, S.C.

    1995-09-01

    The PIUS advanced reactor is a 640-MWe pressurized water reactor developed by Asea Brown Boveri (ABB). A unique feature of the PIUS concept is the absence of mechanical control and shutdown rods. Reactivity is normally controlled by coolant boron concentration and the temperature of the moderator coolant. ABB submitted the PIUS design to the US Nuclear Regulatory Commission (NRC) for preapplication review, and Los Alamos supported the NRC`s review effort. Baseline analyses of small-break initiators at two locations were performed with the system neutronic and thermal-hydraulic analysis code TRAC-PF1/MOD2. In addition, sensitivity studies were performed to explore the robustness of the PIUS concept to severe off-normal conditions having a very low probability of occurrence.

  12. Improvements to mixture level tracking model

    SciTech Connect (OSTI)

    Weaver, W.L.

    1996-04-01

    The purpose of this paper is to present the results of the testing of the recent improvements made to the two-phase level tracking model in RELAP5/MOD3.2. The level model was originally developed during the development of the TRAC-BWR computer code and was subsequently modified by the Pennsylvania State University (PSU). The modifications developed at PSU concern the way in which the two-phase level is moved from volume to volume as the thermal-hydraulic conditions in the system being simulated change during the course of a transients. The other components in the level tracking model remain as described in the original implementation of the model.

  13. Multiloop integral system test (MIST): Test Group 32, SBLOCA (small-break loss-of-coolant accidents) with altered leak and HPI (high-pressure injection) configurations

    SciTech Connect (OSTI)

    Gloudemans, J.R. . Nuclear Power Div.)

    1989-07-01

    The multiloop integral system test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock Wilcox-designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, and Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock Wilcox. The unique features of the Babcock Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP-5 and TRAC, for predicting abnormal plant transients. 6 refs., 143 figs., 12 tabs.

  14. Multiloop integral system test (MIST): Test Group 36, Pump operation

    SciTech Connect (OSTI)

    Gloudemans, J.R. . Nuclear Power Div.)

    1989-07-01

    The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock Wilcox. The unique features of the Babcock Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP-5 and TRAC, for predicting abnormal plant transients. 7 refs., 321 figs., 14 tabs.

  15. Multiloop integral system test (MIST): Test Group 33, HPI-PORV cooling

    SciTech Connect (OSTI)

    Gloudemans, J.R. . Nuclear Power Div.)

    1989-07-01

    The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute and Babcock Wilcox. The unique features of the Babcock Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP-5 AND TRAC, for predicting abnormal plant transients. 5 refs., 136 figs., 13 tabs.

  16. Tank waste source term inventory validation. Volume 1. Letter report

    SciTech Connect (OSTI)

    Brevick, C.H.; Gaddis, L.A.; Johnson, E.D.

    1995-04-28

    The sample data for selection of 11 radionuclides and 24 chemical analytes were extracted from six separate sample data sets, were arranged in a tabular format and were plotted on scatter plots for all of the 149 single-shell tanks, the 24 double-shell tanks and the four aging waste tanks. The solid and liquid sample data was placed in separate tables and plots. The sample data and plots were compiled from the following data sets: characterization raw sample data, recent core samples, D. Braun data base, Wastren (Van Vleet) data base, TRAC and HTCE inventories. This document is Volume I of the Letter Report entitled Tank Waste Source Term Inventory Validation.

  17. Severe fuel-damage scoping test performance. [PWR

    SciTech Connect (OSTI)

    Gruen, G.E.; Buescher, B.J.

    1983-01-01

    As a result of the Three Mile Island Unit-2 (TMI-2) accident, the Nuclear Regulatory Commission has initiated a severe fuel damage test program to evaluate fuel rod and core response during severe accidents similar to TMI-2. The first test of Phase I of this series has been successfully completed in the Power Burst Facility at the Idaho National Engineering Laboratory. Following the first test, calculations were performed using the TRAC-BD1 computer code with actual experimental boundary conditions. This paper discusses the test conduct and performance and presents the calculated and measured test bundle results. The test resulted in a slow heatup to 2000 K over about 4 h, with an accelerated reaction of the zirconium cladding at temperatures above 1600 K in the lower part or the bundle and 2000 K in the upper portion of the bundle.

  18. Considerations for realistic ECCS evaluation methodology for LWRs

    SciTech Connect (OSTI)

    Rohatgi, U.S.; Saha, P.; Chexal, V.K.

    1985-01-01

    This paper identifies the various phenomena which govern the course of large and small break LOCAs in LWRs, and affect the key parameters such as Peak Clad Temperature (PCT) and timing of the end of blowdown, beginning of reflood, PCT, and complete quench. A review of the best-estimate models and correlations for these phenomena in the current literature has been presented. Finally, a set of models have been recommended which may be incorporated in a present best-estimate code such as TRAC or RELAP5 in order to develop a realistic ECCS evaluation methodology for future LWRs and have also been compared with the requirements of current ECCS evaluation methodology as outlined in Appendix K of 10CFR50. 58 refs.

  19. Advances in exposure and toxicity assessment of particulate matter: An overview of presentations at the 2009 Toxicology and Risk Assessment Conference

    SciTech Connect (OSTI)

    Gunasekar, Palur G.; Stanek, Lindsay W.

    2011-07-15

    The 2009 Toxicology and Risk Assessment Conference (TRAC) session on 'Advances in Exposure and Toxicity Assessment of Particulate Matter' was held in April 2009 in West Chester, OH. The goal of this session was to bring together toxicology, geology and risk assessment experts from the Department of Defense and academia to examine issues in exposure assessment and report on recent epidemiological findings of health effects associated with particulate matter (PM) exposure. Important aspects of PM exposure research are to detect and monitor low levels of PM with various chemical compositions and to assess the health risks associated with these exposures. As part of the overall theme, some presenters discussed collection methods for sand and dust from Iraqi and Afghanistan regions, health issues among deployed personnel, and future directions for risk assessment research among these populations. The remaining speakers focused on the toxicity of ultrafine PM and the characterization of aerosols generated during ballistic impacts of tungsten heavy alloys.

  20. MFISH Measurements of Chromosomal Aberrations Individuals Exposed in Utero to Gamma-ray Doses from 5 to 20 cGy

    SciTech Connect (OSTI)

    Brenner, David J.

    2009-11-17

    Our plan was to identify and obtain blood from 36 individuals from the Mayak-in-utero exposed cohort who were exposed in utero only to gamma ray does doses fro 5 to 20 cGy. Our goal is to do mFISH and in a new development, single-arm mFISH on these samples to measure stable chromosome aberrations in these now adult individuals. The results were compared with matched control individuals (same age, same gender) available from the large control population which we are studying in the context of our plutonium worker study. The long term goal was to assess the results both in terms of the sensitivity of the developing embryo/fetus to low doses of ionizing radiation, and in terms of different potential mechanisms (expanded clonal origin vs. induced instability) for an increased risk.

  1. Development and pilot testing of modular dynamic thermomechanical pulp mill model to develop energy reduction strategies. Final report

    SciTech Connect (OSTI)

    Coffin, D.W.

    1996-10-01

    With the development of on-line and real-time process simulations, one obtains the ability to predict and control the process; thus, the opportunity exists to improve energy efficiency, decrease materials wastes, and maintain product quality. Developing this capability was the objective of the this research program. A thermomechanical pulp mill was simulated using both a first principles model and a neural network. The models made use of actual process data and a model that calculated the mass and energy balance of the mill was successfully implemented and run at the mill on an hourly basis. The attempt to develop a model that accurately predicted the quality of the pulp was not successful. It was concluded that the key fro a successful implementation of a real-time control model, such as a neural net model, is availability of on-line sensors that sufficiently characterize the pulp.

  2. Accuracy of cranial coplanar beam therapy using an oblique, stereoscopic x-ray image guidance system

    SciTech Connect (OSTI)

    Vinci, Justin P.; Hogstrom, Kenneth R.; Neck, Daniel W.

    2008-08-15

    A system for measuring two-dimensional (2D) dose distributions in orthogonal anatomical planes in the cranium was developed and used to evaluate the accuracy of coplanar conformal therapy using ExacTrac image guidance. Dose distributions were measured in the axial, sagittal, and coronal planes using a CIRS (Computerized Imaging Reference Systems, Inc.) anthropomorphic head phantom with a custom internal film cassette. Sections of radiographic Kodak EDR2 film were cut, processed, and digitized using custom templates. Spatial and dosimetric accuracy and precision of the film system were assessed. BrainScan planned a coplanar-beam treatment to conformally irradiate a 2-cm-diameterx2-cm-long cylindrical planning target volume. Prior to delivery, phantom misalignments were imposed in combinations of {+-}8 mm offsets in each of the principal directions. ExacTrac x-ray correction was applied until the phantom was within an acceptance criteria of 1 mm/1 deg. (first two measurement sets) or 0.4 mm/0.4 deg. (last two measurement sets). Measured dose distributions from film were registered to the treatment plan dose calculations and compared. Alignment errors, displacement between midpoints of planned and measured 70% isodose contours ({delta}c), and positional errors of the 80% isodose line were evaluated using 49 2D film measurements (98 profiles). Comparison of common, but independent measurements of {delta}c showed that systematic errors in the measurement technique were 0.2 mm or less along all three anatomical axes and that random error averaged ({sigma}{+-}{sigma}{sub {sigma}}) 0.29{+-}0.06 mm for the acceptance criteria of 1 mm/1 deg. and 0.15{+-}0.02 mm for the acceptance criteria of 0.4 mm/0.4 deg. . The latter was consistent with independent estimates that showed the precision of the measurement system was 0.3 mm (2{sigma}). Values of {delta}c were as great as 0.9, 0.3, and 1.0 mm along the P-A, R-L, and I-S axes, respectively. Variations in {delta}c along the P

  3. Health-hazard evaluation report HETA 87-232-1948, Consolidated Freightways, Pocono Summit, Pennsylvania

    SciTech Connect (OSTI)

    Blade, L.M.; Savery, H.

    1989-02-01

    A study was made of possible hazardous working conditions at Consolidated Freightways, Pocono Summit, Pennsylvania. The request concerned potential exposure of dock workers to exhaust emissions from diesel-powered forklift trucks brought about by the health complaints of several of the workers there. Twenty-one workers were identified as symptomatic of exposure to diesel exhaust fumes. This included at least half of the midnight shift. Upper respiratory tract irritation was mentioned by all of these workers. Some reported eye irritation, cough productive of black-tinged sputum, and sore throat. These symptoms lessened during periods away from work. Airborne concentrations of all components measured at the site were well below the applicable exposure limits. A potential health hazard associated with exposure to diesel engine exhaust existed. The authors recommend that whenever a forklift truck is to be left unattended for more than the shortest of periods, the motor should be turned off. The newer forklifts should be used on a shift before the older, less emission controlled, lifts. Roof exhaust fans ordered are to be installed at the facility and their effectiveness evaluated.

  4. A flat-cathode thermionic injector for the PHERMEX Radiographic Facility

    SciTech Connect (OSTI)

    Kauppila, T.; Builta, L.; Burns, M.; Gregory, W.; Honaberger, D.; Watson, S.; Hughes, T.

    1993-06-01

    The PHERMEX (Pulsed High-Energy Radiographic Machine Emitting X-rays) standing-wave linear accelerator is a high-current electron beam generator used for flash-radiography. An improved electron gun has been designed employing a flat-thermionic cathode to replace the existing Pierce-geometry gun. The flat cathode yields increased current with the same applied voltage and cathode area as the Pierce gun. The ISIS code simulations indicate a beam current of 1.5 kA at 600 kV. The new geometry also reduces the probability for high voltage breakdown in the A-K gap. A reentrant magnet captures the expanding electron beam and a bucking coil nulls cathode-tinge field. A third coil is used to optimize the extraction field profile and reduce the effect of nonlinear space charge on the beam emittance. Time-resolved measurements of beam current and voltage have been made. In addition, a streak camera was used to measure beam emittance and spatial profile. Comparisons of measurements with simulations are presented.

  5. A flat-cathode thermionic injector for the PHERMEX Radiographic Facility

    SciTech Connect (OSTI)

    Kauppila, T.; Builta, L.; Burns, M.; Gregory, W.; Honaberger, D.; Watson, S. ); Hughes, T. )

    1993-01-01

    The PHERMEX (Pulsed High-Energy Radiographic Machine Emitting X-rays) standing-wave linear accelerator is a high-current electron beam generator used for flash-radiography. An improved electron gun has been designed employing a flat-thermionic cathode to replace the existing Pierce-geometry gun. The flat cathode yields increased current with the same applied voltage and cathode area as the Pierce gun. The ISIS code simulations indicate a beam current of 1.5 kA at 600 kV. The new geometry also reduces the probability for high voltage breakdown in the A-K gap. A reentrant magnet captures the expanding electron beam and a bucking coil nulls cathode-tinge field. A third coil is used to optimize the extraction field profile and reduce the effect of nonlinear space charge on the beam emittance. Time-resolved measurements of beam current and voltage have been made. In addition, a streak camera was used to measure beam emittance and spatial profile. Comparisons of measurements with simulations are presented.

  6. Multiloop integral system test (MIST): Final report, Inter-group comparisons

    SciTech Connect (OSTI)

    Gloudemans, J.R.

    1989-07-01

    The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock and Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The individual tests are described in detail in Volumes 2 through 8 and Volume 11, and are summarized in Volume 1. Inter-group comparisons are addressed in this document, Volume 9. These comparisons are grouped as follows: mapping versus SBLOCA transients, SBLOCA, pump effects, and the effects of noncondensible gases. Appendix A provides an index and description of the microfiched plots for each test, which are enclosed with the corresponding Volumes 2 through 8. 147 figs., 5 tabs.

  7. Summary of papers on current and anticipated uses of thermal-hydraulic codes

    SciTech Connect (OSTI)

    Caruso, R.

    1997-07-01

    The author reviews a range of recent papers which discuss possible uses and future development needs for thermal/hydraulic codes in the nuclear industry. From this review, eight common recommendations are extracted. They are: improve the user interface so that more people can use the code, so that models are easier and less expensive to prepare and maintain, and so that the results are scrutable; design the code so that it can easily be coupled to other codes, such as core physics, containment, fission product behaviour during severe accidents; improve the numerical methods to make the code more robust and especially faster running, particularly for low pressure transients; ensure that future code development includes assessment of code uncertainties as integral part of code verification and validation; provide extensive user guidelines or structure the code so that the `user effect` is minimized; include the capability to model multiple fluids (gas and liquid phase); design the code in a modular fashion so that new models can be added easily; provide the ability to include detailed or simplified component models; build on work previously done with other codes (RETRAN, RELAP, TRAC, CATHARE) and other code validation efforts (CSAU, CSNI SET and IET matrices).

  8. Reflood completion report: Volume 1. A phenomenological thermal-hydraulic model of hot rod bundles experiencing simultaneous bottom and top quenching and an optimization methodology for closure development

    SciTech Connect (OSTI)

    Nelson, R.A. Jr.; Pimentel, D.A.; Jolly-Woodruff, S.; Spore, J.

    1998-04-01

    In this report, a phenomenological model of simultaneous bottom-up and top-down quenching is developed and discussed. The model was implemented in the TRAC-PF1/MOD2 computer code. Two sets of closure relationships were compared within the study, the Absolute set and the Conditional set. The Absolute set of correlations is frequently viewed as the pure set because the correlations is frequently viewed as the pure set because the correlations utilize their original coefficients as suggested by the developer. The Conditional set is a modified set of correlations with changes to the correlation coefficient only. Results for these two sets indicate quite similar results. This report also summarizes initial results of an effort to investigate nonlinear optimization techniques applied to the closure model development. Results suggest that such techniques can provide advantages for future model development work, but that extensive expertise is required to utilize such techniques (i.e., the model developer must fully understand both the physics of the process being represented and the computational techniques being employed). The computer may then be used to improve the correlation of computational results with experiments.

  9. Trace Assessment for BWR ATWS Analysis

    SciTech Connect (OSTI)

    Cheng, L.Y.; Diamond, D.; Arantxa Cuadra, Gilad Raitses, Arnold Aronson

    2010-04-22

    A TRACE/PARCS input model has been developed in order to be able to analyze anticipated transients without scram (ATWS) in a boiling water reactor. The model is based on one developed previously for the Browns Ferry reactor for doing loss-of-coolant accident analysis. This model was updated by adding the control systems needed for ATWS and a core model using PARCS. The control systems were based on models previously developed for the TRAC-B code. The PARCS model is based on information (e.g., exposure and moderator density (void) history distributions) obtained from General Electric Hitachi and cross sections for GE14 fuel obtained from an independent source. The model is able to calculate an ATWS, initiated by the closure of main steam isolation valves, with recirculation pump trip, water level control, injection of borated water from the standby liquid control system and actuation of the automatic depres-surization system. The model is not considered complete and recommendations are made on how it should be improved.

  10. Analysis of an AP600 intermediate-size loss-of-coolant accident

    SciTech Connect (OSTI)

    Boyack, B.E.; Lime, J.F.

    1995-09-01

    A postulated double-ended guillotine break of an AP600 direct-vessel-injection line has been analyzed. This event is characterized as an intermediate-break loss-of-coolant accident. Most of the insights regarding the response of the AP600 safety systems to the postulated accident are derived from calculations preformed with the TRAC-PF1/MOD2 code. However, complementary insights derived from a scaled experiment conducted in the ROSA facility, as well as insights based upon calculations by other codes, are also presented. Based upon the calculated and experimental results, the AP600 will not experience a core heat up and will reach a safe shutdown state using only safety-class equipment. Only the early part of the long-term cooling period initiated by In-containment Refueling Water Storage Tank injection was evaluated. Thus, the observation that the core is continuously cooled should be verified for the later phase of the long-term cooling period when sump injection and containment cooling processes are important.

  11. Evaluation of atmospheric transport models for use in Phase II of the historical public exposures studies at the Rocky Flats Plant

    SciTech Connect (OSTI)

    Rood, A.S.; Killough, G.G.; Till, J.E.

    1999-08-01

    Five atmospheric transport models were evaluated for use in Phase II of the Historical Public Exposures Studies at the Rocky Flats Plant. Models included a simple straight-line Gaussian plume model (ISCST2), several integrated puff models (RATCHET, TRIAD, and INPUFF2), and a complex terrain model (TRAC). Evaluations were based on how well model predictions compared with sulfur hexafluoride tracer measurements taken in the vicinity of Rocky Flats in February 1991. Twelve separate tracer experiments were conducted, each lasting 9 hr and measured at 140 samplers in arcs 8 and 16 km from the release point at Rocky Flats. Four modeling objectives were defined based on the endpoints of the overall study: (1) the unpaired maximum hourly average concentration, (2) paired time-averaged concentration, (3) unpaired time-averaged concentration, and (4) arc-integrated concentration. Performance measures were used to evaluate models and focused on the geometric mean and standard deviation of the predicted-to-observed ratio and the correlation coefficient between predicted and observed concentrations. No one model consistently outperformed the others in all modeling objectives and performance measures. The overall performance of the RATCHET model was somewhat better than the other models.

  12. Multiloop Integral System Test (MIST): Final report

    SciTech Connect (OSTI)

    Geissler, G.O. . Nuclear Power Div. Babcock and Wilcox Co., Alliance, OH . Research and Development Div.)

    1990-08-01

    The Multiloop Integral System Test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility--the Once-Through Integral System (OTIS)--was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predication abnormal plant transients. The MIST Program is reported in 11 volumes. The program is summarized in Volume 1; Volumes 2 through 8 describes groups of tests by test type, Volume 9 presents inter-group comparisons, Volume 10 provides comparisons between the calculations of RELAP5/MOD2 and MIST observations, and Volume 11 presents the later Phase 4 tests. This Volume 11 pertains to MIST Phase IV tests performed to investigate risk dominant transients and non-LOCA events. 12 refs., 229 figs., 36 tabs.

  13. Multiloop integral system test (MIST): Test Group 31, SBLOCA (small-break loss-of-coolant accident) with varied boundary conditions

    SciTech Connect (OSTI)

    Gloudemans, J.R. . Nuclear Power Div.)

    1989-07-01

    The multiloop integral system test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox-designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock and Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility --- the once-through integral system (OTIS) --- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP-5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in 11 volumes. The program is summarized in Volume 1; Volumes 2 through 8 describe groups of tests by test type; Volume 9 presents inter-group comparisons; Volume 10 provides comparisons between the calculations of RELAP5 MOD2 and MIST observations, and Volume 11 presents the later, Phase 4 tests. This is Volume 3 pertaining to Test Group 31, Boundary Conditions Variations. The specifications, conduct, observations, and results of these tests are described. 8 refs., 328 figs., 15 tabs.

  14. Multiloop Integral System Test (MIST): MIST Facility Functional Specification

    SciTech Connect (OSTI)

    Habib, T F; Koksal, C G; Moskal, T E; Rush, G C; Gloudemans, J R

    1991-04-01

    The Multiloop Integral System Test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST was specifically designed and constructed for this program, and an existing facility -- the Once Through Integral System (OTIS) -- was also used. Data from MIST and OTIS are used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST Functional Specification documents as-built design features, dimensions, instrumentation, and test approach. It also presents the scaling basis for the facility and serves to define the scope of work for the facility design and construction. 13 refs., 112 figs., 38 tabs.

  15. Multiloop Integral System Test (MIST): Final report

    SciTech Connect (OSTI)

    Geissler, G.O.

    1990-08-01

    The Multiloop Integral System Test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock Wilcox. The unique features of the Babcock Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST and two supporting facilities were specifically designed and constructed for this program, and an existing facility -- the Once-Through Integral System (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST Program is reported in 11 volumes. The program is summarized in Volume 1; Volumes 2 through 8 describes groups of tests by test type, Volume 9 presents inter-group comparisons; Volume 10 provides comparisons between the calculations of RELAP5/MOD 2 and MIST observations, and Volume 11 presents the later Phase 4 tests. This Volume 11 addendum pertains to MIST natural circulation tests. 2 refs., 161 figs., 8 tabs.

  16. MIST final report

    SciTech Connect (OSTI)

    Gloudemans, J.R. )

    1991-08-01

    The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock Wilcox. The unique features of the Babcock Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to addresss the thermal-hydraulic SBLOCA questions. MIST was specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and OTIS are used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in eleven volumes; Volumes 2 through 8 pertain to groups of Phase 3 tests by type, Volume 9 presents inter-group comparisons. Volume 10 provides comparisons between the RELAP5 MOD2 calculations and MIST observations, and Volume 11 (with addendum) presents the later, Phase 4 tests. This is Volume 1 of the MIST final report, a summary of the entire MIST program. Major topics include: test advisory grop (TAG) issues; facility scaling and design; test matrix; observations; comparisons of RELAP5 calculations to MIST observations; and MIST versus the TAG issues. 11 refs., 29 figs., 9 tabs.

  17. Multiloop integral system test (MIST): Test Group 34, Steam generator tube rupture

    SciTech Connect (OSTI)

    Gloudemans, J.R. . Nuclear Power Div.)

    1989-07-01

    The multiloop integral system test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility--the Once Through Integral System (OTIS)--was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in 11 volumes. The program is summarized in Volume 1; Volumes 2 through 8 describes groups of tests by test type; Volume 9 presents inter-group comparisons; Volume 10 provides comparisons between the calculations of RELAP5/MOD2 and MIST observations, and Volume 11 presents the later Phase 4 tests. This Volume 6 pertains to Test Group 34, Steam Generator Tube Rupture. The specifications, conduct, observations, and results of these tests are described. 6 refs., 189 figs., 16 tabs.

  18. IJS procedure for RELAP5 to TRACE input model conversion using SNAP

    SciTech Connect (OSTI)

    Prosek, A.; Berar, O. A.

    2012-07-01

    The TRAC/RELAP Advanced Computational Engine (TRACE) advanced, best-estimate reactor systems code developed by the U.S. Nuclear Regulatory Commission comes with a graphical user interface called Symbolic Nuclear Analysis Package (SNAP). Much of efforts have been done in the past to develop the RELAP5 input decks. The purpose of this study is to demonstrate the Institut 'Josef Stefan' (IJS) conversion procedure from RELAP5 to TRACE input model of BETHSY facility. The IJS conversion procedure consists of eleven steps and is based on the use of SNAP. For calculations of the selected BETHSY 6.2TC test the RELAP5/MOD3.3 Patch 4 and TRACE V5.0 Patch 1 were used. The selected BETHSY 6.2TC test was 15.24 cm equivalent diameter horizontal cold leg break in the reference pressurized water reactor without high pressure and low pressure safety injection. The application of the IJS procedure for conversion of BETHSY input model showed that it is important to perform the steps in proper sequence. The overall calculated results obtained with TRACE using the converted RELAP5 model were close to experimental data and comparable to RELAP5/MOD3.3 calculations. Therefore it can be concluded, that proposed IJS conversion procedure was successfully demonstrated on the BETHSY integral test facility input model. (authors)

  19. MODFLOW 2. 0: A program for predicting moderator flow patterns

    SciTech Connect (OSTI)

    Peterson, P.F. . Dept. of Nuclear Engineering); Paik, I.K. )

    1991-07-01

    Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator flow pattern information with stratification effects, and tracks the location of ink plumes in the reactor. The code, written in Fortran, is compiled for Macintosh II computers, and includes subroutines for interactive control and graphical output. Removing the graphics capabilities, the code can also be compiled on other computers. With graphics, in addition to the capability to perform safety related computations, MODFLOW also provides an easy tool for becoming familiar with flow distributions in SRS reactors.

  20. Code requirements document: MODFLOW 2.1: A program for predicting moderator flow patterns

    SciTech Connect (OSTI)

    Peterson, P.F.; Paik, I.K.

    1992-03-01

    Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation of the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator flow pattern information with stratification effects, and tracks the location of ink plumes in the reactor. The code, written in Fortran, is compiled for Macintosh II computers, and includes subroutines for interactive control and graphical output. Removing the graphics capabilities, the code can also be compiled on other computers. With graphics, in addition to the capability to perform safety related computations, MODFLOW also provides an easy tool for becoming familiar with flow distributions in SRS reactors.

  1. Code requirements document: MODFLOW 2. 1: A program for predicting moderator flow patterns

    SciTech Connect (OSTI)

    Peterson, P.F. . Dept. of Nuclear Engineering); Paik, I.K. )

    1992-03-01

    Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation of the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator flow pattern information with stratification effects, and tracks the location of ink plumes in the reactor. The code, written in Fortran, is compiled for Macintosh II computers, and includes subroutines for interactive control and graphical output. Removing the graphics capabilities, the code can also be compiled on other computers. With graphics, in addition to the capability to perform safety related computations, MODFLOW also provides an easy tool for becoming familiar with flow distributions in SRS reactors.

  2. MODFLOW 2.0: A program for predicting moderator flow patterns

    SciTech Connect (OSTI)

    Peterson, P.F.; Paik, I.K.

    1991-07-01

    Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator flow pattern information with stratification effects, and tracks the location of ink plumes in the reactor. The code, written in Fortran, is compiled for Macintosh II computers, and includes subroutines for interactive control and graphical output. Removing the graphics capabilities, the code can also be compiled on other computers. With graphics, in addition to the capability to perform safety related computations, MODFLOW also provides an easy tool for becoming familiar with flow distributions in SRS reactors.

  3. Multi-dimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus during LBLOCA Reflood Phase with a DVI Injection Mode

    SciTech Connect (OSTI)

    Kwon, T.S.; Yun, B.J.; Euh, D.J.; Chu, I.C.; Song, C.H. [Korea Atomic Energy Research Institute (KAERI), Yusung P.O. Box 105, Daejeon 305-600 (Korea, Republic of)

    2002-07-01

    Multi-dimensional thermal-hydraulic behavior in the downcomer annulus of a pressurized water reactor vessel with a Direct Vessel Injection (DVI) mode is presented based on the experimental observation in the MIDAS (Multi-dimensional Investigation in Downcomer Annulus Simulation) steam-water test facility. From the steady-state test results to simulate the late reflood phase of a Large Break Loss-of-Coolant Accidents(LBLOCA), isothermal lines show the multidimensional phenomena of a phasic interaction between steam and water in the downcomer annulus very well. MIDAS is a steam-water separate effect test facility, which is 1/4.93 linearly scaled-down of 1400 MWe PWR type of a nuclear reactor, focused on understanding multi-dimensional thermalhydraulic phenomena in downcomer annulus with various types of safety injection during the refill or reflood phase of a LBLOCA. The initial and the boundary conditions are scaled from the pre-test analysis based on the preliminary calculation using the TRAC code. The superheated steam with a superheating degree of 80 K at a given downcomer pressure of 180 kPa is injected equally through three intact cold legs into the downcomer. (authors)

  4. Multidimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus During LBLOCA Reflood Phase with a Direct Vessel Injection Mode

    SciTech Connect (OSTI)

    Kwon, Tae-Soon; Yun, Byong-Jo; Euh, Dong-Jin; Chu, In-Cheol; Song, Chul-Hwa [Korea Atomic Energy Research Institute (Korea, Republic of)

    2003-07-15

    Multidimensional thermal-hydraulic behavior in the downcomer annulus of a pressurized water reactor (PWR) vessel with a direct vessel injection mode is presented based on the experimental observation in the MIDAS (multidimensional investigation in downcomer annulus simulation) steam-water test facility. From the steady-state test results to simulate the late reflood phase of a large-break loss-of-coolant accident (LBLOCA), isothermal lines show the multidimensional phenomena of a phasic interaction between steam and water in the downcomer annulus very well. MIDAS is a steam-water separate effect test facility, which is 1/4.93 linearly scaled down to a 1400-MW(electric) PWR type of a nuclear reactor, focused on understanding multidimensional thermal-hydraulic phenomena in a downcomer annulus with various types of safety injection during the refill or reflood phase of an LBLOCA. The initial and the boundary conditions are scaled from the pretest analysis based on the preliminary calculation using the TRAC code. The superheated steam with a superheating degree of 80 K at a given downcomer pressure of 180 kPa is injected equally through three intact cold legs into the downcomer.

  5. ERIP application instructions. Final report, September 12, 1990--December 31, 1991

    SciTech Connect (OSTI)

    Watt, D.M.

    1992-01-02

    This report provides background information and instructions to assist applicants in writing Energy-Related Inventions Program (ERIP) applications. Initial feedback fro usage for the new instructions shows that the best instructions would not be read and followed by all applicants. Applications from more than thirty applicants who have received the new instructions indicated that few had read the instructions. Based on this feedback, the instructions have been further revised to include a title page and table of contents. A warning was also added to advise applicants of the potential penalty of delayed review if these instructions are not followed. This revision was intended to address the possibility that some applicants did not see or bother to follow the instructions which followed the background information about ERIP. Included are two examples of ERIP applications which have been prepared for handout at workshops or mailing to applicants. Writing of example applications was time consuming and more difficult than expected for several reasons: (1) Full disclosures can be lengthy, very detailed, and technical. This contrasts with the desire to prepare examples which are comparatively short and easy for the non-technical person to read. (2) Disclosures contain confidential information which should not be published. (3) It is difficult to imagine that applicants will study examples when they do not bother to read the basic instructions.

  6. ERIP application instructions

    SciTech Connect (OSTI)

    Watt, D.M.

    1992-01-02

    This report provides background information and instructions to assist applicants in writing Energy-Related Inventions Program (ERIP) applications. Initial feedback fro usage for the new instructions shows that the best instructions would not be read and followed by all applicants. Applications from more than thirty applicants who have received the new instructions indicated that few had read the instructions. Based on this feedback, the instructions have been further revised to include a title page and table of contents. A warning was also added to advise applicants of the potential penalty of delayed review if these instructions are not followed. This revision was intended to address the possibility that some applicants did not see or bother to follow the instructions which followed the background information about ERIP. Included are two examples of ERIP applications which have been prepared for handout at workshops or mailing to applicants. Writing of example applications was time consuming and more difficult than expected for several reasons: (1) Full disclosures can be lengthy, very detailed, and technical. This contrasts with the desire to prepare examples which are comparatively short and easy for the non-technical person to read. (2) Disclosures contain confidential information which should not be published. (3) It is difficult to imagine that applicants will study examples when they do not bother to read the basic instructions.

  7. CO{sub 2} emissions from developing countries: Better understanding the role of Energy in the long term. Volume 2, Argentina, Brazil, Mexico, and Venezuela

    SciTech Connect (OSTI)

    Ketoff, A.; Sathaye, J.; Goldman, N.

    1991-07-01

    Recent years have witnessed a growing recognition of the link between emissions of carbon dioxide (CO{sub 2}) and changes in the global climate. Of all anthropogenic activities, energy production and use generate the single largest portion of these greenhouse gases. Although developing countries currently account for a small share of global carbon emissions, their contribution is increasing rapidly. Due to the rapid expansion of energy demand in these nations, the developing world`s share in global modern energy use rose from 16 to 27 percent between 1970 and 1990. If the growth rates observed over the past 20 years persist energy demand in developing will surpass that in the countries of the Organization for Economic Cooperation and Development (OECD) early in the 21st century. The study seeks to examine the forces that galvanize the growth of energy use and carbon emissions, to assess the likely future levels of energy and CO{sub 2} in selected developing nations and to identify opportunities for restraining this growth. The purpose of this report is to provide the quantitative information needed to develop effective policy options, not to identify the options themselves. These individual studies were conducted fro Argentina, Brazil, Mexico and Venezuela in Latin America.

  8. CO sub 2 emissions from developing countries: Better understanding the role of Energy in the long term

    SciTech Connect (OSTI)

    Ketoff, A.; Sathaye, J.; Goldman, N.

    1991-07-01

    Recent years have witnessed a growing recognition of the link between emissions of carbon dioxide (CO{sub 2}) and changes in the global climate. Of all anthropogenic activities, energy production and use generate the single largest portion of these greenhouse gases. Although developing countries currently account for a small share of global carbon emissions, their contribution is increasing rapidly. Due to the rapid expansion of energy demand in these nations, the developing world's share in global modern energy use rose from 16 to 27 percent between 1970 and 1990. If the growth rates observed over the past 20 years persist energy demand in developing will surpass that in the countries of the Organization for Economic Cooperation and Development (OECD) early in the 21st century. The study seeks to examine the forces that galvanize the growth of energy use and carbon emissions, to assess the likely future levels of energy and CO{sub 2} in selected developing nations and to identify opportunities for restraining this growth. The purpose of this report is to provide the quantitative information needed to develop effective policy options, not to identify the options themselves. These individual studies were conducted fro Argentina, Brazil, Mexico and Venezuela in Latin America.

  9. Heterogeneous catalytic process for alcohol fuels from syngas. Final technical report

    SciTech Connect (OSTI)

    Dombek, B.D.

    1996-03-01

    The primary objective of this project has been the pursuit of a catalyst system which would allow the selective production from syngas of methanol and isobutanol. It is desirable to develop a process in which the methanol to isobutanol weight ratio could be varied from 70/30 to 30/70. The 70/30 mixture could be used directly as a fuel additive, while, with the appropriate downstream processing, the 30/70 mixture could be utilized for methyl tertiary-butyl ether (MTBE) synthesis. The indirect manufacture of MTBE from a coal derived syngas to methanol and isobutanol process would appear to be a viable solution to MTBE feedstock limitations. To become economically attractive, a process fro producing oxygenates from coal-derived syngas must form these products with high selectivity and good rates, and must be capable of operating with a low-hydrogen-content syngas. This was to be accomplished through extensions of known catalyst systems and by the rational design of novel catalyst systems.

  10. Interaction and merging of two sinistral filaments

    SciTech Connect (OSTI)

    Jiang, Yunchun; Yang, Jiayan; Liu, Yu; Li, Haidong; Wang, Haimin; Ji, Haisheng; Li, Jianping

    2014-09-20

    In this paper, we report the interaction and subsequent merging of two sinistral filaments (F1 and F2) occurring at the boundary of AR 9720 on 2001 December 6. The two filaments were close and nearly perpendicular to each other. The interaction occurred after F1 was erupted and the eruption was impeded by a more extended filament channel (FC) standing in the way, in which F2 was embedded. The erupted material ran into FC along its axis, causing F1 and F2 to merge into a single structure that subsequently underwent a large-amplitude to-and-fro motion. A significant plasma heating process was observed in the merging process, making the mixed material largely disappear from the H? passband, but appear in Extreme Ultraviolet Telescope 195 images for a while. These observations can serve as strong evidence of merging reconnection between the two colliding magnetic structures. A new sinistral filament was formed along FC after the cooling of the merged and heated material. No coronal mass ejection was observed to be associated with the event; though, the eruption was accompanied by a two-ribbon flare with a separation motion, indicating that the eruption had failed. This event shows that, in addition to overlying magnetic fields, such an interaction is an effective restraint to make a filament eruption fail in this way.

  11. NSRD-06. Computational Capability to Substantiate DOE-HDBK-3010 Data

    SciTech Connect (OSTI)

    Louie, David L.Y.; Brown, Alexander L.

    2015-12-01

    Safety basis analysts throughout the U.S. Department of Energy (DOE) complex rely heavily on the information provided in the DOE Hand book, DOE-HDBK-3010, Airborne Release Fractions/Rates and Resp irable Fractions for Nonreactor Nuclear Facilities , to determine source terms. In calcula ting source terms, analysts tend to use the DOE Handbook's bounding values on airbor ne release fractions (ARFs) and respirable fractions (RFs) for various cat egories of insults (representing potential accident release categories). This is typica lly due to both time constraints and the avoidance of regulatory critique. Unfort unately, these bounding ARFs/RFs represent extremely conservative values. Moreover, th ey were derived from very limited small- scale table-top and bench/labo ratory experiments and/or fr om engineered judgment. Thus the basis for the data may not be re presentative to the actual unique accident conditions and configura tions being evaluated. The goal of this res earch is to develop a more ac curate method to identify bounding values for the DOE Handbook using the st ate-of-art multi-physics-based high performance computer codes. This enable s us to better understand the fundamental physics and phenomena associated with the ty pes of accidents for the data described in it. This research has examined two of the DOE Handbook's liquid fire experiments to substantiate the airborne release frac tion data. We found th at additional physical phenomena (i.e., resuspension) need to be included to derive bounding values. For the specific cases of solid powder under pre ssurized condition and mechanical insult conditions the codes demonstrated that we can simulate the phenomena. This work thus provides a low-cost method to establis h physics-justified sa fety bounds by taking into account specific geometri es and conditions that may not have been previously measured and/or are too costly to do so.

  12. A full-dimensional multilayer multiconfiguration time-dependent Hartree study on the ultraviolet absorption spectrum of formaldehyde oxide

    SciTech Connect (OSTI)

    Meng, Qingyong, E-mail: mengqingyong@dicp.ac.cn [State Key Laboratory of Molecular Reaction Dynamics, Dalian Institute of Chemical Physics, Chinese Academy of Sciences, Zhongshan Road 457, 116023 Dalian (China); Meyer, Hans-Dieter, E-mail: hans-dieter.meyer@pci.uni-heidelberg.de [Theoretische Chemie, Physikalisch-Chemisches Institut, Ruprecht-Karls Universitt Heidelberg, Im Neuenheimer Feld 229, D-69120 Heidelberg (Germany)

    2014-09-28

    Employing the multilayer multiconfiguration time-dependent Hartree (ML-MCTDH) method in conjunction with the multistate multimode vibronic coupling Hamiltonian (MMVCH) model, we perform a full dimensional (9D) quantum dynamical study on the simplest Criegee intermediate, formaldehyde oxide, in five lower-lying singlet electronic states. The ultraviolet (UV) spectrum is then simulated by a Fourier transform of the auto-correlation function. The MMVCH model is built based on extensive MRCI(8e,8o)/aug-cc-pVTZ calculations. To ensure a fast convergence of the final calculations, a large number of ML-MCTDH test calculations is performed to find an appropriate multilayer separations (ML-trees) of the ML-MCTDH nuclear wave functions, and the dynamical calculations are carefully checked to ensure that the calculations are well converged. To compare the computational efficiency, standard MCTDH simulations using the same Hamiltonian are also performed. A comparison of the MCTDH and ML-MCTDH calculations shows that even for the present not-too-large system (9D here) the ML-MCTDH calculations can save a considerable amount of computational resources while producing identical spectra as the MCTDH calculations. Furthermore, the present theoretical B{sup ~} {sup 1}A{sup ?}?X{sup ~} {sup 1}A{sup ?} UV spectral band and the corresponding experimental measurements [J. M. Beames, F. Liu, L. Lu, and M. I. Lester, J. Am. Chem. Soc. 134, 2004520048 (2012); L. Sheps, J. Phys. Chem. Lett. 4, 42014205 (2013); W.-L. Ting, Y.-H. Chen, W. Chao, M. C. Smith, and J. J.-M. Lin, Phys. Chem. Chem. Phys. 16, 1043810443 (2014)] are discussed. To the best of our knowledge, this is the first theoretical UV spectrum simulated for this molecule including nuclear motion beyond an adiabatic harmonic approximation.

  13. DEVELOPING THE NATIONAL GEOTHERMAL DATA SYSTEM ADOPTION OF CKAN FOR DOMESTIC & INTERNATIONAL DATA DEPLOYMENT

    SciTech Connect (OSTI)

    Clark, Ryan J.; Kuhmuench, Christoph; Richard, Stephen M.

    2013-01-01

    The National Geothermal Data System (NGDS) De- sign and Testing Team is developing NGDS software currently referred to as the “NGDS Node-In-A-Box”. The software targets organizations or individuals who wish to host at least one of the following: • an online repository containing resources for the NGDS; • an online site for creating metadata to register re- sources with the NGDS • NDGS-conformant Web APIs that enable access to NGDS data (e.g., WMS, WFS, WCS); • NDGS-conformant Web APIs that support dis- covery of NGDS resources via catalog service (e.g. CSW) • a web site that supports discovery and under- standing of NGDS resources A number of different frameworks for development of this online application were reviewed. The NGDS Design and Testing Team determined to use CKAN (http://ckan.org/), because it provides the closest match between out of the box functionality and NGDS node-in-a-box requirements. To achieve the NGDS vision and goals, this software development project has been inititated to provide NGDS data consumers with a highly functional inter- face to access the system, and to ease the burden on data providers who wish to publish data in the sys- tem. It is important to note that this software package constitutes a reference implementation. The NGDS software is based on open standards, which means other server software can make resources available, and other client applications can utilize NGDS data. A number of international organizations have ex- pressed interest in the NGDS approach to data access. The CKAN node implementation can provide a sim- ple path for deploying this technology in other set- tings.

  14. SU-E-J-159: Analysis of Total Imaging Uncertainty in Respiratory-Gated Radiotherapy

    SciTech Connect (OSTI)

    Suzuki, J; Okuda, T; Sakaino, S; Yokota, N

    2015-06-15

    Purpose: In respiratory-gated radiotherapy, the gating phase during treatment delivery needs to coincide with the corresponding phase determined during the treatment plan. However, because radiotherapy is performed based on the image obtained for the treatment plan, the time delay, motion artifact, volume effect, and resolution in the images are uncertain. Thus, imaging uncertainty is the most basic factor that affects the localization accuracy. Therefore, these uncertainties should be analyzed. This study aims to analyze the total imaging uncertainty in respiratory-gated radiotherapy. Methods: Two factors of imaging uncertainties related to respiratory-gated radiotherapy were analyzed. First, CT image was used to determine the target volume and 4D treatment planning for the Varian Realtime Position Management (RPM) system. Second, an X-ray image was acquired for image-guided radiotherapy (IGRT) for the BrainLAB ExacTrac system. These factors were measured using a respiratory gating phantom. The conditions applied during phantom operation were as follows: respiratory wave form, sine curve; respiratory cycle, 4 s; phantom target motion amplitude, 10, 20, and 29 mm (which is maximum phantom longitudinal motion). The target and cylindrical marker implanted in the phantom coverage of the CT images was measured and compared with the theoretically calculated coverage from the phantom motion. The theoretical position of the cylindrical marker implanted in the phantom was compared with that acquired from the X-ray image. The total imaging uncertainty was analyzed from these two factors. Results: In the CT image, the uncertainty between the target and cylindrical marker’s actual coverage and the coverage of CT images was 1.19 mm and 2.50mm, respectively. In the Xray image, the uncertainty was 0.39 mm. The total imaging uncertainty from the two factors was 1.62mm. Conclusion: The total imaging uncertainty in respiratory-gated radiotherapy was clinically acceptable. However

  15. Dialogs on the Yucca Mountain controversy. Special report No. 10

    SciTech Connect (OSTI)

    Schluter, C.M.; Szymanski, J.S.

    1993-08-01

    In an attempt to resolve the controversial issue of tectonic and hydrologic stability of the Yucca Mountain region, the National Academy of Sciences established a Panel on Coupled Hydrologic/Tectonic/HydrothermaI Systems. The Panel has recently released it`s findings in a report entitled Ground Water at Yucca Mountain: How High Can It Rise? The representation of data and the scientific validity of this report was the subject of comprehensive evaluations and reviews which has led to correspondence between Dr. Charles Archarnbeau and Dr. Frank Press, the President of the National Academy of Sciences. All such correspondence prior to April 9, 1993 is covered by TRAC Special Report No. 5, {open_quotes}Dialogs on the Yucca Mountain Controversy.{close_quotes} The present report represents a continuation of the dialog between Dr. Archambeau and Dr. Press; specifically the letter from Dr. Press to Dr. Archambeau dated April 9, 1993 and Archambeau`s response to Press, dated August 19, 1993. In addition to the correspondence between Press and Archambeau, a series of recent reports by other investigators, referred to in the correspondence from Archambeau, are included in this report and document new data and inferences of importance for resolution of the question of suitability of the Yucca Mountain site as a high level nuclear waste repository. These reports also demonstrate that other scientists, not previously associated with the government`s program at Yucca Mountain or the National Academy review of an aspect of that program, have arrived at conclusions that are different than those stated by the Academy review and DOE program scientists.

  16. SU-E-J-90: MRI-Based Treatment Simulation and Patient Setup for Radiation Therapy of Brain Cancer

    SciTech Connect (OSTI)

    Yang, Y; Cao, M; Han, F; Santhanam, A; Neylon, J; Gomez, C; Kaprealian, T; Sheng, K; Agazaryan, N; Low, D; Hu, P

    2014-06-01

    Purpose: Traditional radiation therapy of cancer is heavily dependent on CT. CT provides excellent depiction of the bones but lacks good soft tissue contrast, which makes contouring difficult. Often, MRIs are fused with CT to take advantage of its superior soft tissue contrast. Such an approach has drawbacks. It is desirable to perform treatment simulation entirely based on MRI. To achieve MR-based simulation for radiation therapy, bone imaging is an important challenge because of the low MR signal intensity from bone due to its ultra-short T2 and T1, which presents difficulty for both dose calculation and patient setup in terms of digitally reconstructed radiograph (DRR) generation. Current solutions will either require manual bone contouring or multiple MR scans. We present a technique to generate DRR using MRI with an Ultra Short Echo Time (UTE) sequence which is applicable to both OBI and ExacTrac 2D patient setup. Methods: Seven brain cancer patients were scanned at 1.5 Tesla using a radial UTE sequence. The sequence acquires two images at two different echo times. The two images were processed using in-house software. The resultant bone images were subsequently loaded into commercial systems to generate DRRs. Simulation and patient clinical on-board images were used to evaluate 2D patient setup with MRI-DRRs. Results: The majority bones are well visualized in all patients. The fused image of patient CT with the MR bone image demonstrates the accuracy of automatic bone identification using our technique. The generated DRR is of good quality. Accuracy of 2D patient setup by using MRI-DRR is comparable to CT-based 2D patient setup. Conclusion: This study shows the potential of DRR generation with single MR sequence. Further work will be needed on MR sequence development and post-processing procedure to achieve robust MR bone imaging for other human sites in addition to brain.

  17. SU-E-J-129: A Strategy to Consolidate the Image Database of a VERO Unit Into a Radiotherapy Management System

    SciTech Connect (OSTI)

    Yan, Y; Medin, P; Yordy, J; Zhao, B; Jiang, S

    2014-06-01

    Purpose: To present a strategy to integrate the imaging database of a VERO unit with a treatment management system (TMS) to improve clinical workflow and consolidate image data to facilitate clinical quality control and documentation. Methods: A VERO unit is equipped with both kV and MV imaging capabilities for IGRT treatments. It has its own imaging database behind a firewall. It has been a challenge to transfer images on this unit to a TMS in a radiation therapy clinic so that registered images can be reviewed remotely with an approval or rejection record. In this study, a software system, iPump-VERO, was developed to connect VERO and a TMS in our clinic. The patient database folder on the VERO unit was mapped to a read-only folder on a file server outside VERO firewall. The application runs on a regular computer with the read access to the patient database folder. It finds the latest registered images and fuses them in one of six predefined patterns before sends them via DICOM connection to the TMS. The residual image registration errors will be overlaid on the fused image to facilitate image review. Results: The fused images of either registered kV planar images or CBCT images are fully DICOM compatible. A sentinel module is built to sense new registered images with negligible computing resources from the VERO ExacTrac imaging computer. It takes a few seconds to fuse registered images and send them to the TMS. The whole process is automated without any human intervention. Conclusion: Transferring images in DICOM connection is the easiest way to consolidate images of various sources in your TMS. Technically the attending does not have to go to the VERO treatment console to review image registration prior delivery. It is a useful tool for a busy clinic with a VERO unit.

  18. Multiloop Integral System Test (MIST): Final report: Test group 30, mapping tests

    SciTech Connect (OSTI)

    Geissler, G.O. . Nuclear Power Div.)

    1989-12-01

    The Multiloop Integral System Test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility -- the Once Through Integral System (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in 11 volumes. The program is summarized in Volume 1; Volumes 2 through 8 describe groups of tests by test type; Volume 9 presents inter-group comparisons; Volume 10 provides comparisons between the calculations of RELAP5/MOD2 and MIST observations, and Volume 11 presents the later Phase 4 tests. This Volume 2 pertains to MIST mapping tests performed to traverse the early post-SBLOCA events slowly. The tests investigated the effect of test-to-test variations in boundary system controls, and only the primary fluid mass varied during a specific test in this test group. 5 refs., 415 figs., 12 tabs.

  19. Multiloop integral system test (MIST): Final report

    SciTech Connect (OSTI)

    Gloudemans, J.R. . Nuclear Power Div.)

    1991-04-01

    The Multiloop Integral System Test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST was specifically designed and constructed for this program, and an existing facility -- the Once Through Integral System (OTIS) -- was also used. Data from MIST and OTIS are used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in 11 volumes. Volumes 2 through 8 pertain to groups of Phase 3 tests by type; Volume 9 presents inter-group comparisons; Volume 10 provides comparisons between the RELAP5/MOD2 calculations and MIST observations, and Volume 11 (with addendum) presents the later Phase 4 tests. This is Volume 1 of the MIST final report, a summary of the entire MIST program. Major topics include, Test Advisory Group (TAG) issues, facility scaling and design, test matrix, observations, comparison of RELAP5 calculations to MIST observations, and MIST versus the TAG issues. MIST generated consistent integral-system data covering a wide range of transient interactions. MIST provided insight into integral system behavior and assisted the code effort. The MIST observations addressed each of the TAG issues. 11 refs., 29 figs., 9 tabs.

  20. Development and Assessment of the Appendix K Version of RELAP5-3D for LOCA Licensing Analysis

    SciTech Connect (OSTI)

    Liang, Thomas K.S.; Chang, C.-J.; Hung, H.-J

    2002-09-15

    In light water reactors, particularly the pressurized water reactor (PWR), the severity of a loss-of-coolant accident (LOCA) would limit how high the reactor power can operate. Although the best-estimate LOCA licensing methodology can provide the greatest margin on the peak cladding temperature (PCT) evaluation during a LOCA, it generally takes much more resources to develop. Instead, implementation of evaluation models required by Appendix K of 10CFR50 on an advanced thermal-hydraulic platform such as RELAP5, TRAC, etc., also can gain significant margin for the PCT calculation. Through compliance evaluation against Appendix K of 10CFR50, all of the required evaluation models have been implemented in RELAP5-3D. To verify and assess the development of the Appendix K version of RELAP5-3D, nine kinds of separate-effects experiments and eight sets of LOCA integral experiments were adopted. Through the assessments against separate-effects experiments, the success of the code modification in accordance with Appendix K of 10CFR50 was demonstrated. Besides, one set of a typical integral large-break LOCA from Loss-of-Fluid Test Facility experiments (L2-5) has also been applied to preliminarily evaluate the integral performance of the Appendix K version of RELAP5-3D. The PCT predicted by the evaluation models is greater than the one from best-estimate calculation in the whole LOCA history with the conservatism of 150 K, and the measured PCTs of L2-5 are also well bounded by the evaluation model calculation. Another seven sets of integral-effect experiments will be further applied in the next step to ensure the reasonable integral conservatism of the newly developed LOCA licensing analysis code (RELAP5-3DK/INER), which can cover all the phases of both large- and small LOCA in one code.

  1. Boil-off experiments with the EIR-NEPTUN Facility: Analysis and code assessment overview report

    SciTech Connect (OSTI)

    Aksan, S.N.; Stierli, F.; Analytis, G.T.

    1992-03-01

    The NEPTUN data discussed in this report are from core uncovery (boil-off) experiments designed to investigate the mixture level decrease and the heat up of the fuel rod simulators above the mixture level for conditions simulating core boil-off for a nuclear reactor under small break loss-of-coolant accident conditions. The first series of experiments performed in the NEPTUN test facility consisted of ten boil-off (uncovery) and one adiabatic heat-up tests. In these tests three parameters were varied: rod power, system pressure and initial coolant subcooling. The NEPTUN experiments showed that the external surface thermocouples do not cause a significant cooling influence in the rods to which they are attached under boil-off conditions. The reflooding tests performed later on indicated that the external surface thermocouples have some effect during reflooding for NEPTUN electrically heated rod bundle. Peak cladding temperatures are reduced by about 30--40C and quench times occur 20--70 seconds earlier than rods with embedded thermocouples. Additionally, the external surface-thermocouples give readings up to 20 K lower than those obtained with internal surface thermocouples (in the absence of external thermocouples) in the peak cladding temperature zone. Some of the boil-off data obtained from the NEPTUN test facility are used for the assessment of the thermal-hydraulic transient computer codes. These calculations were performed extensively using the frozen version of TRAC-BD1/MOD1 (version 22). A limited number of assessment calculations were done with RELAP5/MOD2 (version 36.02). In this report the main results and conclusions of these calculations are presented with the identification of problem areas in relation to models relevant to boil-off phenomena. On the basis of further analysis and calculations done, changing some of the models such as the bubbly/slug flow interfacial friction correlation which eliminate some of the problems are recommended.

  2. Report on a randomized trial comparing two forms of immobilization of the head for fractionated stereotactic radiotherapy

    SciTech Connect (OSTI)

    Bednarz, Greg; Machtay, Mitchell; Werner-Wasik, Maria; Downes, Beverly; Bogner, Joachim; Hyslop, Terry; Galvin, James; Evans, James; Curran, Walter Jr.; Andrews, David

    2009-01-15

    Fractionated stereotactic radiotherapy (SRT) requires accurate and reproducible immobilization of the patient's head. This randomized study compared the efficacy of two commonly used forms of immobilization used for SRT. Two routinely used methods of immobilization, which differ in their approach to reproduce the head position from day to day, are the Gill-Thomas-Cosman (GTC) frame and the BrainLab thermoplastic mask. The GTC frame fixates on the patient's upper dentition and thus is in direct mechanical contact with the cranium. The BrainLab mask is a two-part masking system custom fitted to the front and back of the patient's head. After patients signed an IRB-approved informed consent form, eligible patients were randomized to either GTC frame or mask for their course of SRT. Patients were treated as per standard procedure; however, prior to each treatment a set of digital kilovolt images (ExacTrac, BrainLabAB, Germany) was taken. These images were fused with reference digitally reconstructed radiographs obtained from treatment planning CT to yield lateral, longitudinal, and vertical deviations of isocenter and head rotations about respective axes. The primary end point of the study was to compare the two systems with respect to mean and standard deviations using the distance to isocenter measure. A total of 84 patients were enrolled (69 patients evaluable with detailed positioning data). A mixed-effect linear regression and two-tiled t test were used to compare the distance measure for both the systems. There was a statistically significant (p<0.001) difference between mean distances for these systems, suggesting that the GTC frame was more accurate. The mean 3D displacement and standard deviations were 3.17+1.95 mm for mask and 2.00+1.04 mm for frame. Both immobilization techniques were highly effective, but the GTC frame was more accurate. To optimize the accuracy of SRT, daily kilovolt image guidance is recommended with either immobilization system.

  3. High upwind concentrations observed during an upslope tracer event

    SciTech Connect (OSTI)

    Ciolek, J.T. Jr.

    1993-10-01

    In February of 1991 the Rocky Flats Plant conducted twelve tracer experiments to validate an emergency response dispersion model known as the Terrain-Responsive Atmospheric Code (TRAC) (Hodgin 1985). Experimenters released 140 to 260 kilograms of inert tracer gas (sulfur hexafloride) from the plant over an 11 hour period. During each release, one hundred and sixty-five samples, most of which formed concentric rings of 8 and 16 km radius from the plant, recorded cumulative hourly concentrations of the tracer at one meter above ground level (AGL). Figure 1 contains a depiction of the sampler location, the terrain, and the meteorological stations available within the tracer study area. Brown (1991) describes the experimental setup in more detail. The subject of this paper is an event that occurred early in the fifth experiment, on February 9, 1991. In this experiment, tracer material released from 13:00 to 17:00 LST appeared both downwind and upwind of the source, with the highest concentrations upwind. During the fifth experiment, high pressure in Utah produced mostly sunny skis around Rocky Flats. For most of the day, one could find moderate (5 to 10 ms{sup {minus}1}) northerly (from the North) flow within the 700 to 500 mb level of the atmosphere (approximately 3000 to 5500 meters above Mean Sea Level (MSL)). Synoptic scale motions were isolated enough from the surface layer and heating was great enough to produce a 1 km deep upslope flow (flow from the East to the West) by late afternoon. The winds reversed and became downslope at approximately 17:30 LST.

  4. Desulfurization of Illinois coals with hydroperoxides of vegetable oils and alkali, Quarterly report, March 1 - May 31, 1996

    SciTech Connect (OSTI)

    Smith, G.V.; Gaston, R.D.; Song, R.; Cheng, J.; Shi, F.; Wang, Y.

    1996-12-31

    Organic sulfur is removed from coals by treatment with aqueous base, air, and vegetable oils with minimal loss of BTU. Such results were revealed during exploratory experiments on an ICCI funded project to remove organic sulfur from Illinois coals with hydroperoxides of vegetable oils. In fact, prewashing IBC-108 coal with dilute alkali prior to treating with linseed oil and air results in 26% removal of sulfur. This new method is being investigated by treating coals with alkali, impregnating coals with polyunsaturated oils, converting the oils to their hydroperoxides, and heating. Since these oils are relatively inexpensive and easily applied, this project could lead to a cost effective method for removing organic sulfur from coals. During the first quarter the selection of base fro pretreatment and extraction was completed. NaOH is better than NH{sub 4}OH for the pretreatment and Na{sub 2}CO{sub 3} is better than NaOH for the oil extraction. During the second quarter the effectiveness of linseed oil and NaOH for sulfur removal from IBC-108 coal was further tested by pretreating the coal with two base concentrations at four different times followed by treatment with linseed oil at 125{degrees}C for three different times and finally washing with 5% Na{sub 2}CO{sub 3} and methanol. During this third quarter more experimental parameters were systematically varied in order to study the effectiveness of linseed oil and NaOH for sulfur removal from IBC- 108 coal.

  5. Role of char during reburning of nitrogen oxides. Eighth quarterly report, July 1, 1995--September 30, 1995

    SciTech Connect (OSTI)

    Chen, Wei-Yin; Lu, Te-Chang; Fan, L.T.; Yashima, Mutsuo

    1995-11-05

    The investigation of this quarter focuses on the rates of NO reactions with chars in various gaseous environments. The results have revealed significant insights into the NO reduction mechanisms on char surface, particularly when the oxidants, O{sub 2} and CO{sub 2}, are introduced into the feed. Indeed, evidences suggest that the formation of stable oxygen complexes is the major cause of differences in NO reactivity on chars of different origins. The oxidants retard the reactivity of char derived fro the bituminous coal more seriously than they affect the char derived from lignite. Furthermore, additions of these oxidants into the reacting stream produce additional yields of CO and CO{sub 2} during NO reaction with lignite char, suggesting gasification of carbon from lignite char. No excess CO and CO{sub 2} were observed when the bituminous coal char was used. These yields of CO and CO{sub 2} also imply that desorption of stable surface oxygen complex is a rate-limiting step which may be catalyzed by the mineral matters during reactions involving lignite char. Surface area evaluated by CO{sub 2} and Dubinin-Radushkevich (D-R) equation is not a normalization factor of char reactivity during reburning. In the absence of oxidants, the bituminous coal char shows drastic increase in activation energy at about 950 {degrees}C indicating transition of desorption to adsorption controlled mechanisms. When CO{sub 2} is introduced, the transition temperature increases. When oxygen is also added, no such transition is observed up to 1100 {degrees}C. Lignite char reactivity increases smoothly over the temperature range 800 to 1100 {degrees}C. It is also observed that char reactivity decreases with increasing pyrolysis temperature which may be caused by closure of pores due to graphitization. The rate of NO reduction on the Pittsburgh {number_sign}8 coal char is then in good accord with that of a West Virginia coal char reported by De Soete (1980).

  6. Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations

    SciTech Connect (OSTI)

    Ivanov, Kostadin N.; Todorova, Nadejda K.; Sartori, Enrico

    2003-05-15

    exercises 2 and 3 performed by the benchmark team using the coupled code TRAC-PF1/NEM. The purpose of these supporting studies was to aid participants in developing their models.

  7. SU-E-J-189: Credentialing of IGRT Equipment and Processes for Clinical Trials

    SciTech Connect (OSTI)

    Court, L; Aristophanous, M; Followill, D; Kirsner, S; Kisling, K; Pidikiti, R; Wong, P; Balter, P; Bellezza, D; Massingill, B; Papanikolaou, N; Parker, B; Zhen, H

    2014-06-01

    Purpose: Current dosimetry phantoms used for clinical trial credentialing do not directly assess IGRT processes. This work evaluates a custom-built IGRT phantom for credentialing of multiple IGRT modalities and processes. Methods: An IGRT phantom was built out of a low-density body with two inserts. Insert A is used for the CT simulation. Insert B is used for the actual treatment. The inserts contain identical targets in different locations. Relative positions are unknown to the user. The user simulates the phantom (with insert A) as they would a patient, including marking the phantom. A treatment plan is created and sent to the treatment unit. The phantom (with insert B) is then positioned using local IGRT practice. Shifts (planned isocenter, if applicable, and final isocenter) are marked on the phantom using room lasers. The mechanical reproducibility of re-inserting the inserts within the phantom body was tested using repeat high-resolution CT scans. The phantom was tested at 7 centers, selected to include a wide variety of imaging equipment. Results: Mechanical reproducibility was measured as 0.5-0.9mm, depending on the direction. Approaches tested to mark (and transfer) simulation isocenter included lasers, fiducials and reflective markers. IGRT approaches included kV imaging (Varian Trilogy, Brainlab ExacTrac), kV CT (CT-on-rails), kV CBCT (Varian Trilogy, Varian Truebeam, Elekta Agility) and MV CT (Tomotherapy). Users were able to successfully use this phantom for all combinations of equipment and processes. IGRT-based shifts agreed with the truth within 0.8mm, 0.8mm and 1.9mm in the LR, AP, and SI directions, respectively. Conclusion: Based on these preliminary results, the IGRT phantom can be used for credentialing of clinical trials with an action level of 1mm in AP and LR directions, and 2mm in the SI direction, consistent with TG142. We are currently testing with additional institutions with different equipment and processes, including Cyberknife. This

  8. Milestones for Selection Characterization and Analysis of the Performance of a Repository for Spent Nuclear Fuel and HIh-Level Radioactive Waste at Yucca Mountain.

    SciTech Connect (OSTI)

    Rechard, Robert P.

    2015-02-01

    This report presents a concise history in tabular form of events leading up to site identification in 1978, site selection in 1987, subsequent characterization, and ongoing analysis throu gh 2009 of the performance of a repository for spent nuclear fuel and high - level radi oactive waste at Yucca Mou ntain in southern Nevada. The tabulated events generally occurred in five periods: (1) commitment to mined geologic disposal and identification of sites; (2) site selection and analysis, based on regional geologic characterization through literature and an alogous data; (3) feasibility analysis demonstrating calculation procedures and importance of system components, based on rough measures of performance using surface exploration, waste process knowledge, and general laboratory experiments; (4) suitability analysis demonstrating viability of disposal system, based on environment - specific laboratory experiments, in - situ experiments, and underground disposal system characterization; and (5) compliance analysis, based on completed site - specific characterization . The current sixth period beyond 2010 represents a new effort to set waste management policy in the United States. Because the relationship is important to understanding the evolution of the Yucca Mountain Project , the tabulation also shows the interaction between the policy realm and technical realm using four broad categories of events : (a ) R egulatory requirements and related federal policy in laws and court decisions, (c ) Presidential and agency directives, (c) technical milestones of implemen ting institutions, and (d ) critiques of the Yucca Mountai n P roject and pertinent national and world events related to nuclear energy and radioactive waste. Preface The historical progression of technical milestones for the Yucca Mountain Project was originally developed for 10 journal articles in a special issue of Reliability Engineering System Safe ty on the performance assessment for the Yucca Mountain

  9. SU-E-T-132: Dosimetric Impact of Positioning Errors in Hypo-Fractionated Cranial Radiation Therapy Using Frameless Stereotactic BrainLAB System

    SciTech Connect (OSTI)

    Keeling, V; Jin, H; Ali, I; Ahmad, S

    2014-06-01

    Purpose: To determine dosimetric impact of positioning errors in the stereotactic hypo-fractionated treatment of intracranial lesions using 3Dtransaltional and 3D-rotational corrections (6D) frameless BrainLAB ExacTrac X-Ray system. Methods: 20 cranial lesions, treated in 3 or 5 fractions, were selected. An infrared (IR) optical positioning system was employed for initial patient setup followed by stereoscopic kV X-ray radiographs for position verification. 6D-translational and rotational shifts were determined to correct patient position. If these shifts were above tolerance (0.7 mm translational and 1° rotational), corrections were applied and another set of X-rays was taken to verify patient position. Dosimetric impact (D95, Dmin, Dmax, and Dmean of planning target volume (PTV) compared to original plans) of positioning errors for initial IR setup (XC: Xray Correction) and post-correction (XV: X-ray Verification) was determined in a treatment planning system using a method proposed by Yue et al. (Med. Phys. 33, 21-31 (2006)) with 3D-translational errors only and 6D-translational and rotational errors. Results: Absolute mean translational errors (±standard deviation) for total 92 fractions (XC/XV) were 0.79±0.88/0.19±0.15 mm (lateral), 1.66±1.71/0.18 ±0.16 mm (longitudinal), 1.95±1.18/0.15±0.14 mm (vertical) and rotational errors were 0.61±0.47/0.17±0.15° (pitch), 0.55±0.49/0.16±0.24° (roll), and 0.68±0.73/0.16±0.15° (yaw). The average changes (loss of coverage) in D95, Dmin, Dmax, and Dmean were 4.5±7.3/0.1±0.2%, 17.8±22.5/1.1±2.5%, 0.4±1.4/0.1±0.3%, and 0.9±1.7/0.0±0.1% using 6Dshifts and 3.1±5.5/0.0±0.1%, 14.2±20.3/0.8±1.7%, 0.0±1.2/0.1±0.3%, and 0.7±1.4/0.0±0.1% using 3D-translational shifts only. The setup corrections (XC-XV) improved the PTV coverage by 4.4±7.3% (D95) and 16.7±23.5% (Dmin) using 6D adjustment. Strong correlations were observed between translation errors and deviations in dose coverage for XC. Conclusion

  10. One-Dimensional Analysis of Thermal Stratification in AHTR and SFR Coolant Pools

    SciTech Connect (OSTI)

    Haihua Zhao; Per F. Peterson

    2007-10-01

    Thermal stratification phenomena are very common in pool type reactor systems, such as the liquid-salt cooled Advanced High Temperature Reactor (AHTR) and liquid-metal cooled fast reactor systems such as the Sodium Fast Reactor (SFR). It is important to accurately predict the temperature and density distributions both for design optimation and accident analysis. Current major reactor system analysis codes such as RELAP5 (for LWRs, and recently extended to analyze high temperature reactors), TRAC (for LWRs), and SASSYS (for liquid metal fast reactors) only provide lumped-volume based models which can only give very approximate results and can only handle simple cases with one mixing source. While 2-D or 3-D CFD methods can be used to analyze simple configurations, these methods require very fine grid resolution to resolve thin substructures such as jets and wall boundaries, yet such fine grid resolution is difficult or impossible to provide for studying the reactor response to transients due to computational expense. Therefore, new methods are needed to support design optimization and safety analysis of Generation IV pool type reactor systems. Previous scaling has shown that stratified mixing processes in large stably stratified enclosures can be described using one-dimensional differential equations, with the vertical transport by free and wall jets modeled using standard integral techniques. This allows very large reductions in computational effort compared to three-dimensional numerical modeling of turbulent mixing in large enclosures. The BMIX++ (Berkeley mechanistic MIXing code in C++) code was originally developed at UC Berkeley to implement such ideas. This code solves mixing and heat transfer problems in stably stratified enclosures. The code uses a Lagrangian approach to solve 1-D transient governing equations for the ambient fluid and uses analytical or 1-D integral models to compute substructures. By including liquid salt properties, BMIX++ code is

  11. Development of a High Fidelity System Analysis Code for Generation IV Reactors

    SciTech Connect (OSTI)

    Hongbin Zhang; Vincent Mousseau; Haihua Zhao

    2008-06-01

    Traditional nuclear reactor system analysis codes such as RELAP and TRAC employ an operator split methodology. In this approach, each of the physics (fluid flow, heat conduction and neutron diffusion) is solved separately and the coupling terms are done explicitly. This approach limits accuracy (first order in time at best) and makes the codes slow in running since the explicit coupling imposes stability restrictions on the time step size. These codes have been extensively tested and validated for the existing LWRs. However, for GEN IV nuclear reactor designs which tend to have long lasting transients resulting from passive safety systems, the performance is questionable and modern high fidelity simulation tools will be required. The requirement for accurate predictability is the motivation for a large scale overhaul of all of the models and assumptions in transient nuclear reactor safety simulation software. At INL we have launched an effort with the long term goal of developing a high fidelity system analysis code that employs modern physical models, numerical methods, and computer science for transient safety analysis of GEN IV nuclear reactors. Modern parallel solution algorithms will be employed through utilizing the nonlinear solution software package PETSc developed by Argonne National Laboratory. The physical models to be developed will have physically realistic length scales and time scales. The solution algorithm will be based on the physics-based preconditioned Jacobian-free Newton-Krylov solution methods. In this approach all of the physical models are solved implicitly and simultaneously in a single nonlinear system. This includes the coolant flow, nonlinear heat conduction, neutron kinetics, and thermal radiation, etc. Including modern physical models and accurate space and time discretizations will allow the simulation capability to be second order accurate in space and in time. This paper presents the current status of the development efforts as

  12. Application of Bomb Radiocarbon Chronologies to Shortfin Mako (Isurus oxyrinchus)

    SciTech Connect (OSTI)

    Ardizzone, D; Cailliet, G M; Natanson, L J; Andrews, A H; Kerr, L A; Brown, T A

    2007-07-16

    otoliths, bivalves and corals. In the same study by Campana et al. (2002), a single vertebra fro

  13. Discovery of Novel Complex Metal Hydrides for Hydrogen Storage through Molecular Modeling and Combinatorial Methods

    SciTech Connect (OSTI)

    Lesch, David A; Adriaan Sachtler, J.W. J.; Low, John J; Jensen, Craig M; Ozolins, Vidvuds; Siegel, Don

    2011-02-14

    of study also focused on activating boron-based materials in order to exploit the tremendous gravimetric capacity of LiBH4. A number of LiNH2 – LiBH4 – transition metal (TM) systems were investigated for the following reasons. No additional leads were discovered in this system. Another major project activity was the assembly of a high throughput synthesis system. The automated synthesizer was set up in a glovebox and was capable of handling liquids and powders and carrying out sealed block syntheses up to 250 °C. Unfortunately, the synthesizer could not handle the delivery of the fine powders required fro hydrogen storage applications. Although the powder delivery system was overhauled and redesigned several times, this problem was never remedied.