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Reviews of ASME Section 11 pump and valve relief requests: Post Generic Letter 89-04

Description: This paper presents a discussion of ASME Section 11 Pump and Valve Inservice Testing relief request reviews by the NRC and their contractors. Topics that will be discussed include the scope of USNRC reviews in Technical Evaluation Reports (TERs) (and Safety Evaluation, SEs); including the basis for granting relief requests, the status of relief requests in IST Program updates, and the Generic Letter 89-04 approval process; and the level of technical detail required in submitted programs. This p… more
Date: January 1, 1992
Creator: DiBiasio, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fuel performance annual report for 1989

Description: This annual report, the twelfth in a series, provides a brief description of fuel performance during 1989 in commercial nuclear power plants and an indication of trends. Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance are provided. References to more detailed information and related US Nuclear Regulatory Commission evaluations are included.
Date: June 1, 1992
Creator: Bailey, W.J.; Berting, F.M. (Pacific Northwest Lab., Richland, WA (United States)) & Wu, S. (Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety rod latch inspection

Description: During an attempt to raise control rods from the 100 K reactor in December, one rod could not be withdrawn. Subsequent investigation revealed that a small button'' in the latch mechanism had broken off of the lock plunger'' and was wedged in a position that prevented rod withdrawal. Concern that this failure may have resulted from corrosion or some other metallurgical problem resulted in a request that SRL examine six typical latch mechanisms from the 100 L reactor by use of radiography and met… more
Date: February 1, 1992
Creator: Leader, D.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High temperature ceramic membrane reactors for coal liquid upgrading

Description: In this project we will study a novel process concept, i.e., the use of ceramic membrane reactors in upgrading of coal model compounds and coal derived liquids. In general terms, the USC research team is responsible for constructing and operating the membrane reactor apparatus and for testing various inorganic membranes for the upgrading of coal derived asphaltenes and coal model compounds. The USC effort will involve the principal investigator of this project and two graduate research assistan… more
Date: January 1, 1992
Creator: Tsotsis, T.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Rapid quenching of molten lithium-aluminum jets in water under loss-of-control-rod-cooling conditions

Description: A series of fifteen tests were performed to investigate the thermal interactions between molten LiAl control rod material and water under conditions prototypic of the loss-of-control-rod-cooling (LCRC) accident scenario. The experimental parameters such as melt mass, stream diameter, melt temperature and flowrate, water depth and water temperature were controlled or varied to agree with analytically determined conditions, thus insuring prototypicality of the experiments and applicability of the… more
Date: January 1, 1992
Creator: Greene, G. A.; Finfrock, C. C.; Schwarz, C. E.; Allison, D. K. & Hyder, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Antiproton driven microfission-fusion on closer inspection

Description: A closer look at the energetics of antiproton annihilation in real systems, coupled to hydrodynamics, materials strength, particle transport, equations of state, and related interactions is necessary to assess ultimate viability. The systematics of antiproton microfission-fusion are the subject of this analysis, as well as technology constraints.
Date: January 1, 1992
Creator: Wienke, B.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Mechanical strength and stability of lithium aluminate

Description: Pacific Northwest Laboratory (PNL) investigated the strength and resistance to thermal shock of lithium aluminate annular pellets. The room temperature, axial compressive fracture strength of pellets made at Westinghouse Advanced Energy Systems (WAES) varied from 80 to 133 ksi. The strength at 430{degrees}C (806{degrees}F) was to 30 to 40% lower. The strength at 900{degrees}C (1652{degrees}F) showed a wide variation with one measurement near 90 ksi. These strength values are consistent with oth… more
Date: June 1, 1992
Creator: Brimhall, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Current nuclear industry practices with regard to the integration of surveillances

Description: Commercial nuclear industry practices regarding the integration of technical specification (TS) surveillance and maintenance activities are identified in this report. A questionnaire was developed and used to obtain current industry practices from NRC Regional personnel and INEL engineers with utility experience. Some of these practices indicate that the scheduling of TS surveillance and maintenance items could be more effectively coordinated. Also, must utilities do not formally consider risk … more
Date: April 1, 1992
Creator: Stewart, M. & Smith, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radioactive waste management in the former USSR

Description: Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems … more
Date: June 1, 1992
Creator: Bradley, D.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Validation issues in aging risk evaluations

Description: Validation issues in aging risk evaluations are examined by considering how variabilities and uncertainties due to sparse component aging data, modeling assumptions, and risk quantification approaches may affect aging risk evaluation results and inferences. Sensitivity studies using a NUREG-1150 PWR evaluated the effect of component aging data uncertainties and variations in test and maintenance frequencies on aging prioritizations. Preliminary results indicate that while individual component r… more
Date: January 1, 1992
Creator: Hassan, M.; Samanta, P. (Brookhaven National Lab., Upton, NY (United States)) & Vesely, W. (Science Applications International Corp., San Diego, CA (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reviewing the impact of advanced control room technology

Description: Progress to date on assessing the nature of the expected changes in human performance and risk associated with the introduction of digital control, instrumentation, and display systems is presented. Expected changes include the shift toward more supervisory tasks, development of intervention strategies, and reallocation of function between human and machine. Results are reported in terms of the scope of new technology, human performance issues, and crews experience with digital control systems … more
Date: January 1, 1992
Creator: Wilhelmsen, C. A.; Gertman, D. I.; Ostrom, L. T.; Nelson, W. R.; Galyean, W. J. & Byers, J. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Particulate behavior in a controlled-profile pulverized coal-fired reactor: A study of coupled turbulent particle dispersion and thermal radiation transport

Description: This report describes recent progress in a fundamental, three-year investigation of the coupled problem of turbulent particle dispersion and thermal radiation transport. The project's objective is to make measurements of particle size, velocity, number density, temperature and wall radiant heat flux in a parametrically-controlled reactor presently existent at Brigham Young University (BYU). Although the study proposed here is primarily designed to provide experimental data not currently availab… more
Date: January 1, 1992
Creator: Queiroz, M. & Webb, B.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculation of Savannah River K Reactor Mark-22 assembly LOCA/ECS power limits

Description: This paper summarizes the results of TRAC-PF1/MOD3 calculations of Mark-22 fuel assembly of loss-of-coolant accident/emergency cooling system (LOCA/ECS) power limits for the Savannah River Site (SRS) K Reactor. This effort was part of a larger effort undertaken by the Los Alamos National Laboratory for the US Department of Energy to perform confirmatory power limits calculations for the SRS K Reactor. A method using a detailed three-dimensional (3D) TRAC model of the Mark-22 fuel assembly was d… more
Date: January 1, 1992
Creator: Fischer, S. R.; Farman, R. F. & Birdsell, S. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The development of an integrated multistage fluid bed retorting process. [KENTORT II process--50-lb/hr]

Description: This report summarizes the progress made on the development of an integrated multistage fluidized bed retorting process (KENTORT II). The KENTORT II process includes integral fluidized bed zone for pyrolysis, gasification, and combustion of the oil shale. The purpose of this program is to design and test the KENTORT II process at the 50-lb/hr scale. The work performed during this year involved projects that will contribute physical and chemical data for the final design of the 50-lb/hr retort. … more
Date: January 1, 1992
Creator: Carter, S.; Vego, A.; Taulbee, D. & Stehn, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Flow instability in a vertical annulus under steady state and transient conditions

Description: Experimental data have been obtained for the occurrence of flow instability in a vertical annulus under steady state and transient down-flow conditions. The results show that the primary factor affecting the onset of flow instability is the Q{sub ratio} parameter (a measure of the void production in a channel). In addition, it is shown that for steady state conditions good agreement exists between the single annulus data and single tube data based upon the same L/D ratio. The results also indic… more
Date: January 1, 1992
Creator: Fighetti, C.; Kokolis, S.; Maciuca, C.; Reddy, D.G.; Yang, B.; Carrano, V. (Columbia Univ., New York, NY (United States)) et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Natural convection heat transfer analysis of ATR fuel elements

Description: Natural convection air cooling of the Advanced Test Reactor (ATR) fuel assemblies is analyzed to determine the level of decay heat that can be removed without exceeding the melting temperature of the fuel. The study was conducted to assist in the level 2 PRA analysis of a hypothetical ATR water canal draining accident. The heat transfer process is characterized by a very low Rayleigh number (Ra {approx} 10{sup {minus}5}) and a high temperature ratio. Since neither data nor analytical models wer… more
Date: May 1, 1992
Creator: Langerman, M.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MHTGR thermal performance envelopes: Reliability by design

Description: This document discusses thermal performance envelopes which are used to specify steady-state design requirements for the systems of the Modular High Temperature Gas-Cooled Reactor to maximize plant performance reliability with optimized design. The thermal performance envelopes are constructed around the expected operating point accounting for uncertainties in actual plant as-built parameters and plant operation. The components are then designed to perform successfully at all points within the … more
Date: May 1, 1992
Creator: Etzel, K.T.; Howard, W.W. & Zgliczynski, J.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Broad-Application Test Reactor

Description: This report is about a new, safe, and operationally efficient DOE reactor of nuclear research and testing proposed for the early to mid- 21st Century. Dubbed the Broad-Application Test Reactor (BATR), the proposed facility incorporates a multiple-application, multiple-mission design to support DOE programs such as naval reactors and space power and propulsion, as well as research in medical, science, isotope, and electronics arenas. DOE research reactors are aging, and implementing major replac… more
Date: May 1, 1992
Creator: Motloch, C. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mode methods for strain-hardening structures

Description: An approximation method is being developed to predict the dynamic plastic response of rigid, strain-hardening structures. This method is analogous to the instantaneous mode techniques used to treat rigid, perfectly plastic structures in that a deflection shape involving a number of arbitrary functions of time is selected, based on static deformation profiles. Two stress fields are associated with the deflection shape: One satisfies the equations of motion with appropriate boundary and continuit… more
Date: April 1, 1992
Creator: Youngdahl, C.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Treatment of high-level wastes from the IFR fuel cycle

Description: The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in… more
Date: January 1, 1992
Creator: Johnson, T. R.; Lewis, M. A.; Newman, A. E. & Laidler, J. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The development of precipitated iron catalysts with improved stability

Description: The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal li… more
Date: May 6, 1992
Creator: Abrevaya, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fission gas bubble nucleated cavitational swelling of the alpha-uranium phase of irradiated U-Pu-Zr fuel

Description: Cavitational swelling has been identified as a potential swelling mechanism for the alpha uranium phase of irradiated U-Pu-Zr metal fuels for the Integral Fast Reactor being developed at Argonne National Laboratory. The trends of U-Pu-Zr swelling data prior to fuel cladding contact can be interpreted in terms of unrestrained cavitational driven swelling. It is theorized that the swelling mechanisms at work in the alpha uranium phase can be modeled by single vacancy and single interstitial kinet… more
Date: April 1, 1992
Creator: Rest, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fatigue and environmentally assisted cracking in light water reactors

Description: Fatigue and stress corrosion cracking (SCC) for low-alloy steel used in piping and in steam generator and reactor pressure vessels have been investigated. Fatigue data were obtained on medium-sulfur-content A533-Gr B and A106-Gr B steels in high-purity (HP) deoxygenated water, in simulated pressurized water reactor water, and in air. Analytical studies focused on the behavior of carbon steels in boiling water reactor (BWR) environments. Crack-growth rates of composite fracture-mechanics specime… more
Date: March 1, 1992
Creator: Kassner, T.F.; Ruther, W.E.; Chung, H.M.; Hicks, P.D.; Hins, A.G.; Park, J.Y. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

High temperature ceramic membrane reactors for coal liquid upgrading

Description: In this project we well evaluate the performance of Sel-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. In addition, the development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will be also investigated. (VC)
Date: June 19, 1992
Creator: Tsotsis, T.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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