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Wildfire ignition resistant home design(WIRHD) program: Full-scale testing and demonstration final report.

Description: The primary goal of the Wildfire ignition resistant home design(WIRHD) program was to develop a home evaluation tool that could assess the ignition potential of a structure subjected to wildfire exposures. This report describes the tests that were conducted, summarizes the results, and discusses the implications of these results with regard to the vulnerabilities to homes and buildings.
Date: December 13, 2011
Creator: Quarles, Stephen, L. & Sindelar, Melissa
Partner: UNT Libraries Government Documents Department

Preliminary Investigation of the Thermal Decomposition of Ablefoam and EF-AR20 Foam (Ablefoam Replacement)

Description: Preliminary thermal decomposition experiments with Ablefoam and EF-AR20 foam (Ablefoam replacement) were done to determine the important chemical and associated physical phenomena that should be investigated to develop the foam decomposition chemistry sub-models that are required in numerical simulations of the fire-induced response of foam-filled engineered systems for nuclear safety applications. Although the two epoxy foams are physically and chemically similar, the thermal decomposition of each foam involves different chemical mechanisms, and the associated physical behavior of the foams, particularly ''foaming'' and ''liquefaction,'' have significant implications for modeling. A simplified decomposition chemistry sub-model is suggested that, subject to certain caveats, may be appropriate for ''scoping-type'' calculations.
Date: January 1, 2002
Creator: ULIBARRI, TAMARA A.; DERZON, DORA K.; ERICKSON, KENNETH L.; CASTANEDA, JAIME N.; BOREK III, THEODORE T.; RENLUND, ANITA M. et al.
Partner: UNT Libraries Government Documents Department

Methodology for developing and implementing alternative temperature-time curves for testing the fire resistance of barriers for nuclear power plant applications

Description: Advances in fire science over the past 40 years have offered the potential for developing technically sound alternative temperature-time curves for use in evaluating fire barriers for areas where fire exposures can be expected to be significantly different than the ASTM E-119 standard temperature-time exposure. This report summarizes the development of the ASTM E-119, standard temperature-time curve, and the efforts by the federal government and the petrochemical industry to develop alternative fire endurance curves for specific applications. The report also provides a framework for the development of alternative curves for application at nuclear power plants. The staff has concluded that in view of the effort necessary for the development of nuclear power plant specific temperature-time curves, such curves are not a viable approach for resolving the issues concerning Thermo-Lag fire barriers. However, the approach may be useful to licensees in the development of performance-based fire protection methods in the future.
Date: August 1, 1996
Creator: Cooper, L. Y. & Steckler, K. D.
Partner: UNT Libraries Government Documents Department

Testing in support of on-site storage of residues in the Pipe Overpack Container

Description: The disposition of the large back-log of plutonium residues at the Rocky Flats Environmental Technology Site (Rocky Flats) will require interim storage and subsequent shipment to a waste repository. Current plans call for disposal at the Waste Isolation Pilot Plant (WIPP) and the transportation to WIPP in the TRUPACT-II. The transportation phase will require the residues to be packaged in a container that is more robust than a standard 55-gallon waste drum. Rocky Flats has designed the Pipe Overpack Container to meet this need. It is desirable to use this same waste packaging for interim on-site storage in non-hardened buildings. To meet the safety concerns for this storage the Pipe Overpack Container has been subjected to a series of tests at Sandia National Laboratories in Albuquerque, New Mexico. In addition to the tests required to qualify the Pipe Overpack Container as a waste container for shipment in the TRUPACT-II several tests were performed solely for the purpose of qualifying the container for interim storage. This report will describe these tests and the packages response to the tests. 12 figs., 3 tabs.
Date: February 1, 1997
Creator: Ammerman, D.J.; Bobbe, J.G. & Arviso, M.
Partner: UNT Libraries Government Documents Department

Development of flame retardant PV module encapsulants: Volume 1. Final report

Description: This Phase 1 final report covers the work performed by Springborn Testing and Research, Inc., for the period October 1, 1997 to June 30, 1998 under the Department of Energy Cooperative Agreement Number DE-FC36-97GO10255, entitled Development of Flame Retardant PV Module Encapsulants. While use of roof-mounted arrays has always been an attractive means of deploying PV, only within recent years have such building integrated concepts (BIPV) found renewed interest among module makers and end-users. Prior to building integrated and rooftop applications, flammability requirements for modules have not been a great industry concern. However, with growing interest in BIPV and the requirement for building code requirements for commercial and industrial structures, flammability issues have become a barrier to entry for many module constructions into this potentially huge domestic market for PV. The overall goal of the 3 phase PV BONUS two project is to develop and commercialize a line of fire retardant encapsulation materials to serve the emerging building integrated and building mounted PV market. The objectives of the Phase 1 effort are limited to concept development and business planning activities.
Date: June 1, 1998
Creator: Galica, J.P.
Partner: UNT Libraries Government Documents Department

Measurements of the effects of smoke on active circuits

Description: Smoke has long been recognized as the most common source of fire damage to electrical equipment; however, most failures have been analyzed after the fire was out and the smoke vented. The effects caused while the smoke is still in the air have not been explored. Such effects have implications for new digital equipment being installed in nuclear reactors. The US Nuclear Regulatory Commission is sponsoring work to determine the impact of smoke on digital instrumentation and control. As part of this program, Sandia National Laboratories has tested simple active circuits to determine how smoke affects them. These tests included the study of three possible failure modes on a functional board: (1) circuit bridging, (2) corrosion (metal loss), and (3) induction of stray capacitance. The performance of nine different circuits was measured continuously on bare and conformally coated boards during smoke exposures lasting 1 hour each and continued for 24 hours after the exposure started. The circuit that was most affected by smoke (100% change in measured values) was the one most sensitive to circuit bridging. Its high impedance (50 Mohm) was shorted during the exposure, but in some cases recovered after the smoke was vented. The other two failure modes, corrosion and induced stray capacitance, caused little change in the function of the circuits. The smoke permanently increased resistance of the circuit tested for corrosion, implying that the contacts were corroded. However, the change was very small (< 2%). The stray capacitance test circuit showed very little change after a smoke exposure in either the short or long term. The results of the tests suggest that conformal coatings and type of circuit are major considerations when designing digital circuitry to be used in critical control systems.
Date: January 1, 1998
Creator: Tanaka, T. J.
Partner: UNT Libraries Government Documents Department

The Federal manufactured home construction and safety standards -- implications for foam panel construction

Description: This report reviews the U.S. Department of Housing and Urban Development construction code for (HUD-code) manufactured homes, Part 3280: Manufactured Home Construction and Safety Standards (the HUD Code), to identify sections that might be relevant in determining if insulated foam core panels (or structural insulated panels, SIPs) meet the requirements of Part 3280 for use in manufactured home construction. The U.S. Department of Energy and other parties are interested in the use of SIPs in residential construction, including HUD-Code manufactured homes, because the foam panels can have a higher effective insulation value than standard stud-framed construction and use less dimensional lumber. Although SIPs have not been used in manufactured housing, they may be well suited to the factory production process used to manufacture HUD-Code homes and the fact that they require less virgin timber may reduce the effect of volatile and increasing timber prices. Part 3280 requirements for fire resistance, wind resistance, structural load strength, ventilation, transportation shock, and thermal protection are reviewed. A brief comparison is made between the HUD Code requirements and data collected from foam panel manufacturers. 8 refs.
Date: March 1, 1997
Creator: Lee, A.D.; Schrock, D.W. & Flintoft, S.A.
Partner: UNT Libraries Government Documents Department

Hypothetical accident condition thermal analysis and testing of a Type B drum package

Description: A thermophysical property model developed to analytically determine the thermal response of cane fiberboard when exposed to temperatures and heat fluxes associated with the 10 CFR 71 hypothetical accident condition (HAC) has been benchmarked against two Type B drum package fire test results. The model 9973 package was fire tested after a 30 ft. top down drop and puncture, and an undamaged model 9975 package containing a heater (21W) was fire tested to determine content heat source effects. Analysis results using a refined version of a previously developed HAC fiberboard model compared well against the test data from both the 9973 and 9975 packages.
Date: July 1, 1995
Creator: Hensel, S.J.; Alstine, M.N. Van & Gromada, R.J.
Partner: UNT Libraries Government Documents Department

Concepts and processes for alternate solenoid coils. Final report. [Fire resistance]

Description: A solenoid coil concept with fire environment potential was proposed, fabricated, and evaluated with favorable results. A polyphenylmethylsiloxane polymer was used as a high temperature insulation coating for the bobbin coil assembly. Alternate concepts utilizing foil conductors and additional insulating materials were examined for follow-on development potential.
Date: February 1, 1979
Creator: Jordan, H.F.
Partner: UNT Libraries Government Documents Department

Development of flammable liquid storage wooden cabinets for chemical laboratories

Description: A fire hardened wooden cabinet was developed for the storage of flammable liquids for LLNL Bldg. 151 nuclear chemistry laboratories. The new cabinet requirements were to fit into existing cabinet spaces, match existing cabinets in appearance, and meet the National Fire Protection Association Flammable and Combustible Liquids Code. A standard test apparatus was developed to produce the required fire exposure necessary to evaluate existing cabinets and new designs. The final design was a cabinet insert that could be prefabricated and installed into the appropriate storage area of the existing cabinets.
Date: November 1, 1993
Creator: Staggs, K. J.; Hasegawa, H. K.; Doughty, S. M. & Barr, J. G.
Partner: UNT Libraries Government Documents Department

DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-02028

Description: Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-02028. For those attributes that were also measured during the field surveillance, no significant changes were observed. Four conditions were identified that do not meet inspection criteria. These conditions are subject to additional investigation and disposition by the Surveillance Program Authority. The conditions include: (1) The lead shield was covered with a white corrosion layer; (2) The lead shield height exceeds drawing requirements; (3) Mold was observed on the lower fiberboard subassembly; and (4) Fiberboard thermal conductivity in the axial direction exceeded the specified range. The Surveillance Program Authority was notified of these conditions and will document the disposition by surveillance report. All other observations and test results met identified criteria, or were collected for information and trending purposes. The Savannah River Site (SRS) stores packages containing plutonium (Pu) materials in the K-Area Complex (KAC). The Pu materials are packaged per the DOE 3013 Standard and stored within Model 9975 shipping packages in KAC. The KAC facility DSA (Document Safety Analysis) credits the Model 9975 package to perform several safety functions, including criticality prevention, impact resistance, containment, and fire resistance to ensure the plutonium materials remain in a safe configuration during normal and accident conditions. The Model 9975 package is expected to perform its safety function for at least 12 years from initial packaging. The DSA recognizes the degradation potential for the materials of package construction over time in the KAC storage environment and requires an assessment of materials performance to validate the assumptions of the analysis and ultimately predict service life. As part of the comprehensive Model 9975 package surveillance program, destructive examination of package 9975-02028 was performed following field surveillance in accordance with Reference. Field surveillance of the Model 9975 package in KAC included nondestructive ...
Date: December 30, 2009
Creator: Daugherty, W. & Stefek, T.
Partner: UNT Libraries Government Documents Department

DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-03431

Description: Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-03431. For those attributes that were also measured during the field surveillance, no significant changes were observed. All observations and test results met identified criteria, or were collected for information and trending purposes. Except for modest corrosion of the lead shield (which is typical of these packages following several years service), no evidence of a degraded condition was found in this package. The Savannah River Site (SRS) stores packages containing plutonium (Pu) materials in the KArea Complex (KAC). The Pu materials are packaged per the DOE 3013 Standard and stored within Model 9975 shipping packages in KAC. The KAC facility DSA (Document Safety Analysis) credits the Model 9975 package to perform several safety functions, including criticality prevention, impact resistance, containment, and fire resistance to ensure the plutonium materials remain in a safe configuration during normal and accident conditions. The Model 9975 package is expected to perform its safety function for at least 12 years from initial packaging. The DSA recognizes the degradation potential for the materials of package construction over time in the KAC storage environment and requires an assessment of materials performance to validate the assumptions of the analysis and ultimately predict service life. As part of the comprehensive Model 9975 package surveillance program, destructive examination of package 9975-03431 was performed following field surveillance in accordance with Reference. Field surveillance of the Model 9975 package in KAC included nondestructive examination of the drum, fiberboard, lead shield and containment vessels. Results of the field surveillance are provided in Attachment 1.
Date: May 30, 2012
Creator: Daugherty, W.
Partner: UNT Libraries Government Documents Department

Titanium-tantalum alloy development

Description: Research has been underway at Los Alamos National Laboratory for several years to develop an alloy capable of containing toxic materials in the event of a fire involving a nuclear weapon. Due to their high melting point, good oxidation resistance, and low solubility in molten plutonium, alloys based on the Ti-Ta binary system have been developed for this purpose. The course of the alloy development to-date, along with processing and property data, are presented in this overview.
Date: April 1, 1996
Creator: Cotton, J.D.; Bingert, J.F.; Dunn, P.S.; Butt, D.P. & Margevicius, R.W.
Partner: UNT Libraries Government Documents Department

A compilation of reports of the Advisory Committee on Reactor Safeguards. 1994 annual. Volume 16

Description: This compilation contains 30 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1994. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the U.S. Library of Congress. The reports are categorized by the most appropriate generic subject area and by chronological order within subject area.
Date: April 1, 1995
Partner: UNT Libraries Government Documents Department

Investigation of the fire performance of building insulation in full-scale and laboratory fire tests

Description: Twenty-two insulations are exposed to fire tests including the 25 ft Tunnel test, the Attic Floor Radiant Panel test and actual fire conditions of a simulated attic configuration. The insulations consisted of a number of cellulose fiber insulations, utilizing various chemical treatments, glass fiber and mineral fiber insulations. The fire performance characteristics of the insulations were measured in each of the three test scenarios and the report compares their results.
Date: April 1, 1984
Creator: Kleinfelder, W.A.
Partner: UNT Libraries Government Documents Department

Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2

Description: An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations. The package is designed to ship large quantities of fissile and radioactive materials as solids.
Date: April 1, 1978
Creator: Klima, B.B.; Shappert, L.B.; Seagren, R.D. & Box, W.D.
Partner: UNT Libraries Government Documents Department

Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Shipping Cask D-38

Description: An analytical evaluation of the Oak Ridge National Laboratory Shipping Cask D-38 (solids shipments) was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.
Date: April 1, 1978
Creator: Klima, B.B.; Shappert, L.B.; Seagren, R.D. & Box, W.D.
Partner: UNT Libraries Government Documents Department