Publications

Results 2076–2100 of 2,290

Search results

Jump to search filters

MELCOR Computer Code Manuals Volume 1: Primer and Users' Guide

Humphries, Larry; Figueroa Faria, Victor G.; Young, Michael F.; Laros, James H.; Reynolds, John T.

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications.

More Details

MELCOR Computer Code Manuals

Humphries, Larry; Figueroa Faria, Victor G.; Young, Michael F.; Laros, James H.; Reynolds, John T.

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications.

More Details

Cultural Perspectives of the 2015 Nonlinear Mechanics and Dynamics Summer Research Institute

Arviso, Brittany A.; Croessmann, Charles L.; Fachko, Jonathan E.; Laros, James H.; Brake, Matthew R.; Rizzo, Davinia B.

This paper discusses the results of a study to determine the impact of culture on engineering. The study took place during the 2015 Nonlinear Mechanics and Dynamics Summer Research Institute, a six-week research program sponsored by Sandia National Laboratories and the University of New Mexico consisting of 24 graduate students participating in seven different projects. Twenty-two of the participants and two of the mentors were interviewed to study the effects of cultural background on engineering processes and interactions. The results of this study indicate that cultural differences drive engineering practices.

More Details

MELCOR Computer Code Manuals Volume 3: MELCOR Assessment Problems [Draft]

Humphries, Larry; Laros, James H.; Figueroa Faria, Victor G.; Young, Michael F.; Weber, Scott W.; Ross, Kyle R.; Phillips, Jesse P.

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light-water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories (SNL) for the U.S. Nuclear Regulatory Commission (NRC) as a second-generation plant risk assessment tool and the successor to the Source Term Code package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include thermal-hydraulic response in the reactor coolant system (RCS), reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; and fission product release and transport behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 2.0, released to users in September 2008. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR User's Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package. Volume 3, MELCOR Assessment Problems, presents a portfolio of test and sample problems consisting of both analyses of experiments and of full plant problems. These analyses will be repeated with future releases of MELCOR in order to provide a metric on code predictions as new versions are released.

More Details

High Performance Computing - Power Application Programming Interface Specification. Version 1.1 [DRAFT]

Laros, James H.; Kelly, Suzanne M.; Laros, James H.; Grant, Ryan E.; Olivier, Stephen L.; Levenhagen, Michael J.; DeBonis, David D.

Measuring and controlling the power and energy consumption of high performance computing systems by various components in the software stack is an active research area [13, 3, 5, 10, 4, 21, 19, 16, 7, 17, 20, 18, 11, 1, 6, 14, 12]. Implementations in lower level software layers are beginning to emerge in some production systems, which is very welcome. To be most effective, a portable interface to measurement and control features would significantly facilitate participation by all levels of the software stack. We present a proposal for a standard power Application Programming Interface (API) that endeavors to cover the entire software space, from generic hardware interfaces to the input from the computer facility manager.

More Details

Thermal transport in tantalum oxide films for memristive applications

Applied Physics Letters

Landon, Colin D.; Ihlefeld, Jon I.; Brumbach, Michael T.; Marinella, Matthew J.; Laros, James H.; Laros, James H.; Brennecka, Geoffrey L.

The thermal conductivity of amorphous TaOx memristive films having variable oxygen content is measured using time domain thermoreflectance. Thermal transport is described by a two-part model where the electrical contribution is quantified via the Wiedemann-Franz relation and the vibrational contribution by the minimum thermal conductivity limit for amorphous solids. The vibrational contribution remains constant near 0.9 W/mK regardless of oxygen concentration, while the electrical contribution varies from 0 to 3.3 W/mK. Thus, the dominant thermal carrier in TaOx switches between vibrations and charge carriers and is controllable either by oxygen content during deposition, or dynamically by field-induced charge state migration.

More Details

UVI Cyber-security Workshop Workshop Analysis

Kuykendall, Tommie G.; Allsop, Jacob L.; Anderson, Benjamin R.; Boumedine, Marc; Laros, James H.; Galvin, Seanmichael Y.; Gonzalez, Oscar; Lee, Wellington K.; Lin, Han W.; Morris, Tyler J.; Nauer, Kevin S.; Foehse, Beth A.; Ta, Kim T.; Trasti, Jennifer T.; White, David R.

The cybersecurity consortium, which was established by DOE/NNSA’s Minority Serving Institutions Partnerships Program (MSIPP), allows students from any of the partner schools (13 HBCUs, two national laboratories, and a public school district) to have all consortia options available to them, to create career paths and to open doors to DOE sites and facilities to student members of the consortium. As a part of this year consortium activities, Sandia National Laboratories and the University of Virgin Islands conducted a week long cyber workshop that consisted of three courses; Digital Forensics and Malware Analysis, Python Programming, and ThunderBird Cup. These courses are designed to enhance cyber defense skills and promote learning within STEM related fields.

More Details
Results 2076–2100 of 2,290
Results 2076–2100 of 2,290