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180 MW demonstration of advanced tangentially-fired combustion techniques for the reduction of nitrogen oxide (NO{sub x}) emissions from coal-fired boilers. Final report (open access)

180 MW demonstration of advanced tangentially-fired combustion techniques for the reduction of nitrogen oxide (NO{sub x}) emissions from coal-fired boilers. Final report

This report provides the key findings of the Innovative Clean Coal Technology (ICCT) demonstration project at Gulf Power`s Lansing Smith Unit No. 2 and the implications for other tangentially-fired boilers. L. Smith Unit No. 2 is a 180 MW tangentially-fired boiler burning Eastern Bituminous coal, which was retrofitted with Asea Brown Boveri/Combustion Engineering Services` (ABB/CE) LNCFS I, II, and III technologies. An extensive test program was carried-out with US Department of Energy, Southern Company and Electric Power Research Institute (EPRI) funding. The LNCFS I, II, and III achieved 37 percent, 37 percent, and 45 percent average long-term NO{sub x} emission reduction at full load, respectively (see following table). Similar NO{sub x} reduction was achieved within the control range (100--200 MW). However, below the control point (100 MW), NO{sub x} emissions with the LNCFS technologies increased significantly, reaching pre-retrofit levels at 70 MW. Short-term testing proved that low load NO{sub x} emissions could be reduced further by using lower excess O{sub 2} and burner tilt, but with adversed impacts on unit performance, such as lower steam outlet temperatures and, potentially, higher CO emissions and LOI.
Date: February 1, 1994
Creator: Tavoulareas, E. S.; Hardman, R.; Eskinazi, D. & Smith, L.
Object Type: Report
System: The UNT Digital Library
216-U-10 Pond and 216-Z-19 Ditch characterization studies (open access)

216-U-10 Pond and 216-Z-19 Ditch characterization studies

The chemical, reprocessing of spent nuclear fuels at the US Department of Energy`s Hanford Site has generated large volumes of radioactive liquid effluents. The majority of these effluents have been used strictly for cooling or other supportive functions and have been discharged to ditches and ponds. The 216-U-10 Pond and 216-Z-19 Ditch are two such disposal facilities. These facilities are components of an integrated system of ditches, ponds, and overflow facilities collectively referred to as the U-Pond disposal system. The U-Pond system has been used since 1943 and has received a large variety of radioisotopes from several sources. This study covered tho major aspects of the environment, including wind resuspension, biological uptake and transport, geologic distribution in surface and subsurface sediments, and ground-water impacts. The long-term use of U-Pond and the Z-19 Ditch has resulted in the localized accumulation of transuranic and fission product inventories as a result of sorption and filtration of particulates onto the uppermost sediments.
Date: February 1, 1994
Creator: Last, G. V.; Duncan, D. W.; Graham, M. J.; Hall, M. D.; Hall, V. W.; Landeen, D. S. et al.
Object Type: Report
System: The UNT Digital Library
The 1992 FRDM mass model and unstable nuclei (open access)

The 1992 FRDM mass model and unstable nuclei

We discuss the reliability of a recent global nuclear-structure calculation in regions far from {beta} stability. We focus on the results for nuclear masses, but also mention other results obtained in the nuclear-structure calculation, for example ground-state spins. We discuss what should be some minimal requirements of a nuclear mass model and study how the macroscopic-microscopic method and other nuclear mass models fullfil such basic requirements. We study in particular the reliability of nuclear mass models in regions of nuclei that were not considered in the determination of the model parameters.
Date: February 1, 1994
Creator: Moeller, P. & Nix, R. J.
Object Type: Article
System: The UNT Digital Library
1993 annual report of hazardous waste activities for the Oak Ridge K-25 site (open access)

1993 annual report of hazardous waste activities for the Oak Ridge K-25 site

This report is a detailed listing of all of the Hazardous Waste activities occurring at Martin Marietta`s K-25 site. Contained herein are hazardous waste notification forms, waste stream reports, generator fee forms and various TSDR reports.
Date: February 1, 1994
Creator: unknown
Object Type: Report
System: The UNT Digital Library
1993 baseline solid waste management system description (open access)

1993 baseline solid waste management system description

Pacific Northwest Laboratory has prepared this report under the direction of Westinghouse Hanford Company. The report provides an integrated description of the system planned for managing Hanford`s solid low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. The primary purpose of this document is to illustrate a collective view of the key functions planned at the Hanford Site to handle existing waste inventories, as well as solid wastes that will be generated in the future. By viewing this system as a whole rather than as individual projects, key facility interactions and requirements are identified and a better understanding of the overall system may be gained. The system is described so as to form a basis for modeling the system at various levels of detail. Model results provide insight into issues such as facility capacity requirements, alternative system operating strategies, and impacts of system changes (ie., startup dates). This description of the planned Hanford solid waste processing system: defines a baseline system configuration; identifies the entering waste streams to be managed within the system; identifies basic system functions and waste flows; and highlights system constraints. This system description will evolve and be revised as issues are resolved, planning decisions …
Date: February 1, 1994
Creator: Armacost, L. L.; Fowler, R. A. & Konynenbelt, H. S.
Object Type: Report
System: The UNT Digital Library
1993 Pacific Northwest Loads and Resources Study, Pacific Northwest Economic and Electricity Use Forecast, Technical Appendix: Volume 1. (open access)

1993 Pacific Northwest Loads and Resources Study, Pacific Northwest Economic and Electricity Use Forecast, Technical Appendix: Volume 1.

This publication documents the load forecast scenarios and assumptions used to prepare BPA`s Whitebook. It is divided into: intoduction, summary of 1993 Whitebook electricity demand forecast, conservation in the load forecast, projection of medium case electricity sales and underlying drivers, residential sector forecast, commercial sector forecast, industrial sector forecast, non-DSI industrial forecast, direct service industry forecast, and irrigation forecast. Four appendices are included: long-term forecasts, LTOUT forecast, rates and fuel price forecasts, and forecast ranges-calculations.
Date: February 1, 1994
Creator: United States. Bonneville Power Administration.
Object Type: Report
System: The UNT Digital Library
4f heavy fermion photoelectron spectra do not exhibit the Kondo scale (open access)

4f heavy fermion photoelectron spectra do not exhibit the Kondo scale

It has been the authors contention for some time that the Single Impurity Anderson Model (SIAM), as extended by Gunnarsson and Schonhammer (GS), or the non-crossing approximation (NCA), does not correctly describe the 4f photoelectron spectra of heavy fermions. Recently, they have concentrated on Yb heavy fermions since in these materials the Kondo resonance (KR) is fully occupied and thus accessible via photoemission. In particular, they have repeatedly pointed out that the width, position, spectral weight, lineshape, and temperature dependence of the features assumed to be the KR and its sidebands, are nearly independent of the Kondo temperature, T{sub K}, while at the same time bearing a striking resemblance to the simple 4f core level spectra of pure Yb metal, or of Lu in isostructural Lu compounds. It is important to resolve these issues in view of the fundamental nature of the problem. Here, the authors chose to test the bulk vs. surface hypothesis by performing measurements on YbCu{sub 2}Si{sub 2} and YbAl{sub 3} single crystals at hv {approx} 120 eV (UPS) and hv {approx} 1,500 eV(XPS) to see if the n{sub f}, hole occupancy, values increase markedly at XPS energies as the electron escape depth increases by about a …
Date: February 1, 1994
Creator: Arko, A. J.; Joyce, J. J.; Andrews, A. B.; Blyth, R. I. R.; Bartlett, R. J.; Fisk, Z. et al.
Object Type: Report
System: The UNT Digital Library
An Accelerator Neutron Source for BNCT. Technical Progress Report, 1 June 1993--31 May 1994 (open access)

An Accelerator Neutron Source for BNCT. Technical Progress Report, 1 June 1993--31 May 1994

None
Date: February 1, 1994
Creator: Blue, T. E. & Vafai, K.
Object Type: Report
System: The UNT Digital Library
Access road from State Route 240 to the 200 West Area, Hanford Site, Richland, Washington: Environmental assessment (open access)

Access road from State Route 240 to the 200 West Area, Hanford Site, Richland, Washington: Environmental assessment

The US Department of Energy (DOE) proposes to construct an access road on the Hanford Site, from State Route (SR) 240 to Beloit Avenue in the 200 West Area. Traffic volume during shift changes creates an extremely serious congestion and safety problem on Route 4S from the Wye barricade to the 200 Areas. A Risk Evaluation (Trost 1992) indicated that there is a probability of 1.53 fatal accidents on Route 4S within 2 years. To help alleviate this danger, a new 3.5-kilometer (2.2-mile)-long access road would be constructed from Beloit Avenue in the 200 West Area to SR 240. In addition, administrative controls such as redirecting traffic onto alternate routes would be used to further reduce traffic volume. The proposed access road would provide an alternative travel-to-work route for many outer area personnel, particularly those with destinations in the 200 West Area. This proposal is the most reasonable alternative to reduce the problem. While traffic safety would be greatly improved, a small portion of the shrub-steppe habitat would be disturbed. The DOE would offset any habitat damage by re-vegetation or other appropriate habitat enhancement activities elsewhere on the Hanford Site. This Environmental Assessment (EA) provides information about the environmental impacts …
Date: February 1, 1994
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Accident Analysis for High-Level Waste Management Alternatives in the US Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement (open access)

Accident Analysis for High-Level Waste Management Alternatives in the US Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement

A comparative generic accident analysis was performed for the programmatic alternatives for high-level waste (HLW) management in the US Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement (EM PEIS). The key facilities and operations of the five major HLW management phases were considered: current storage, retrieval, pretreatment, treatment, and interim canister storage. A spectrum of accidents covering the risk-dominant accidents was analyzed. Preliminary results are presented for HLW management at the Hanford site. A comparison of these results with those previously advanced shows fair agreement.
Date: February 1, 1994
Creator: Folga, S.; Mueller, C. & Roglans-Ribas, J.
Object Type: Article
System: The UNT Digital Library
Accidental beam loss in superconducting accelerators: Simulations, consequences of accidents and protective measures (open access)

Accidental beam loss in superconducting accelerators: Simulations, consequences of accidents and protective measures

The consequences of an accidental beam loss in superconducting accelerators and colliders of the next generation range from the mundane to rather dramatic, i.e., from superconducting magnet quench, to overheating of critical components, to a total destruction of some units via explosion. Specific measures are required to minimize and eliminate such events as much as practical. In this paper we study such accidents taking the Superconducting Supercollider complex as an example. Particle tracking, beam loss and energy deposition calculations were done using the realistic machine simulation with the Monte-Carlo codes MARS 12 and STRUCT. Protective measures for minimizing the damaging effects of prefire and misfire of injection and extraction kicker magnets are proposed here.
Date: February 1, 1994
Creator: Drozhdin, A.; Mokhov, N. & Parker, B.
Object Type: Report
System: The UNT Digital Library
Accountability for network backup failures (open access)

Accountability for network backup failures

Regular hard disk backups for workstations are widely recommended. The necessity of backups -- akin to one`s own mortality -- is something most people would rather not think about. This attitude has two consequences. When people do subscribe to automated network backups, they expect the system to perform at a high level of reliability and that their files will be there for them when they need them. Second, they usually fail to appreciate that reliability is a shared responsibility. Although ostensibly their only responsibility is to keep the computer powered on overnight, there are actually many more opportunities for failure within the user`s jurisdiction than in other parts of the infrastructure. High reliability is almost a sine qua non for backups. We describe a strategy for enhancing reliability based on the principle of accountability. This strategy involves monitoring the system, gathering statistics, detecting problems, anticipating problems, troubleshooting, and finally determining where failure occurred within the infrastructure and who should be accountable. We describe a specific backup system in a specific network environment to illustrate the value of accountability. This system, macdumps, backs up Macintosh disks over an AppleTalk network. The original software was written by Dan Tappan of BBN in …
Date: February 1, 1994
Creator: Benson, W. H.
Object Type: Article
System: The UNT Digital Library
Adsorption and Desorption of Contaminants (open access)

Adsorption and Desorption of Contaminants

The microbial remediation of sites Contaminated with organics is well documented, however, there are some significant problems that remain to be solved in the areas of contaminants sorbed to soils and non-aqueous phase liquid (NAPL) contamination. Methods of in situ bioremediation techniques employ either the stimulation of indigenous populations by nutrient addition, or the addition of prepared bacterial cultures to the subsurface environment. Problems of contaminant sorption and NAPL`s are related in that both encompass reduced contaminant bioavailability. Non-aqueous phase liquids have been identified as a priority area for research in the In situ Program due to their presence at DOE sites and the lack of adequate technology to effectively treat this contamination. Bioremediation technologies developed as a result of this project are easily transferred to industry.
Date: February 1, 1994
Creator: Palumbo, A. V.; Strong-Gunderson, J. M.; DeFlaun, M. & Ensley, B.
Object Type: Article
System: The UNT Digital Library
Advanced coal-fueled industrial cogeneration gas turbine system: Hot End Simulation Rig (open access)

Advanced coal-fueled industrial cogeneration gas turbine system: Hot End Simulation Rig

This Hot End Simulation Rig (HESR) was an integral part of the overall Solar/METC program chartered to prove the technical, economic, an environmental feasibility of a coal-fueled gas turbine, for cogeneration applications. The program was to culminate in a test of a Solar Centaur Type H engine system operated on coal slurry fuel throughput the engine design operating range. This particular activity was designed to verify the performance of the Centaur Type H engine hot section materials in a coal-fired environment varying the amounts of alkali, ash, and sulfur in the coal to assess the material corrosion. Success in the program was dependent upon the satisfactory resolution of several key issues. Included was the control of hot end corrosion and erosion, necessary to ensure adequate operating life. The Hot End Simulation Rig addressed this important issue by exposing currently used hot section turbine alloys, alternate alloys, and commercially available advanced protective coating systems to a representative coal-fueled environment at turbine inlet temperatures typical of Solar`s Centaur Type H. Turbine hot end components which would experience material degradation include the transition duct from the combustor outlet to the turbine inlet, the shroud, nozzles, and blades. A ceramic candle filter vessel was …
Date: February 1, 1994
Creator: Galica, M. A.
Object Type: Report
System: The UNT Digital Library
Advanced direct liquefaction concepts for PETC generic units. Quarterly technical progress report, October 1993--December 1993 (open access)

Advanced direct liquefaction concepts for PETC generic units. Quarterly technical progress report, October 1993--December 1993

Several promising leads that have developed during the course of this program are being evaluated in this phase of the study. These have been selected from those that can be economically evaluated within the time constraints of the program schedule. A detailed plan for evaluating these approaches was formulated. The individual steps that will be evaluated are: (1) Dewaxing of the distillate recycle solvent stream treating either 25% or 100% of the stream. (2) Hydrotreating the dewaxed distillate streams in a downflow fixed bed reactor. (3) Agglomerating the coal using both the 25% and 100% dewaxed-hydrotreated distillate streams. (4) Liquefying the as-received coal and the agglomerated coals using two different Mo-promoted hematite particulate catalysts. (5) Liquefying two different Mo-Fe impregnated coals. (6) Liquefying the two off-agglomerated, Mo-Fe impregnated coals. The effect of the presence of molybdenum in the 1050{degrees}F{sup +} will be determined by making comparisons in both Mo-containing and Mo-free full range V-131B process solvent. The solvents that will be used in this study are the full-range reconstituted Mo-containing V-131B from Run 262E and a Mo-free V-131B made up of 1050{degrees}F{sup +} bottoms from Run 258K V-131B and V-1074 distillate from Run 262E. The series of experiments are described …
Date: February 1, 1994
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced neutron source reactor thermal-hydraulic test loop facility description (open access)

Advanced neutron source reactor thermal-hydraulic test loop facility description

The Thermal-Hydraulic Test Loop (THTL) is a facility for experiments constructed to support the development of the Advanced Neutron Source Reactor (ANSR) at Oak Ridge National Laboratory. The ANSR is both cooled and moderated by heavy water and uses uranium silicide fuel. The core is composed of two coaxial fuel-element annuli, each of different diameter. There are 684 parallel aluminum-clad fuel plates (252 in the inner-lower core and 432 in the outer-upper core) arranged in an involute geometry that effectively creates an array of thin rectangular flow channels. Both the fuel plates and the coolant channels are 1.27 mm thick, with a span of 87 mm (lower core), 70 mm (upper core), and 507-mm heated length. The coolant flows vertically upwards at a mass flux of 27 Mg/m{sup 2}s (inlet velocity of 25 m/s) with an inlet temperature of 45{degrees}C and inlet pressure of 3.2 MPa. The average and peak heat fluxes are approximately 6 and 12 MW/m{sup 2}, respectively. The availability of experimental data for both flow excursion (FE) and true critical heat flux (CHF) at the conditions applicable to the ANSR is very limited. The THTL was designed and built to simulate a full-length coolant subchannel of the …
Date: February 1, 1994
Creator: Felde, D. K.; Farquharson, G.; Hardy, J. H.; King, J. F.; McFee, M. T.; Montgomery, B. H. et al.
Object Type: Report
System: The UNT Digital Library
Advanced separation technology for flue gas cleanup. Quarterly technical report No. 7, [October--December 1993] (open access)

Advanced separation technology for flue gas cleanup. Quarterly technical report No. 7, [October--December 1993]

During the third quarter of 1993, we continued work on Tasks 2, 3, 4, 5, and 6. In Task 2, we tested the NO{sub x} sorption capacity of Fe(II)-EDTA and five new SRI-synthesized compounds. We also made a comparison of all the tests so far and have selected two compounds as the leading candidates. In Task 3, we electrochemically converted FE(III) phthalocyanine to its Fe(II) analog and synthesized several metal phthalocyanine compounds. In Task 4, we evaluated 200-fiber HFC modules for SO{sub 2} removal with water and solutions of Na{sub 2}SO{sub 3}. We also connected this HFC unit to the liquor regenerating HFC unit described in Task 6. We continue to observe 95--100% SO{sub 2} removal. In Task 5, we calculated the overall mass transfer coefficients of earlier Fe(II)-EDTA runs for scrubbing NO{sub x}. We also obtained a new module from Hoechst-Celanese and began its characterization. In Task 6, we demonstrated that the spent liquor from Task 4 can be regenerated using a second HFC. The spent liquor was regenerating using DMA with initial recovery of SO{sub 2} up to 52%.
Date: February 1994
Creator: Bhown, Abhoyjit S.; Alvarado, Dean; Stearns, Paul; Ventura, Susanna; Sirkar, Kamalesh K.; Majumdar, Sudipto et al.
Object Type: Report
System: The UNT Digital Library
Advanced Turbine Systems Program conceptual design and product development. Quarterly report, [August 3, 1993--October 31, 1993] (open access)

Advanced Turbine Systems Program conceptual design and product development. Quarterly report, [August 3, 1993--October 31, 1993]

This Quarterly Technical Progress Report covers the period August 3 through October 31, 1993, for Phase II of the Advanced Turbine Systems (ATS) Program by Solar Turbines Incorporated under DOE Contract No. DE-AC21-93MC30246. The objective of this program is to provide the conceptual design and product development plan for an industrial gas turbine system to operate at a thermal efficiency of 50 percent and developable to 60 percent. Solar`s ATS Engine Design Team reviewed the intercooled and recuperated (ICR) gas turbine concept defined in the Program proposal, validated certain assumptions associated therewith, and began the process of actualizing this concept in terms of achievable turbomachinery components. Given the probable use of a free power turbine arrangement, both 1-spool and 2-spool compressor arrangements were examined with both fixed and variable turbine geometry. Off-design performance, both part-load and full-load over a range of inlet air temperatures, was examined. During this period certain simplifying assumptions were made regarding the amount of cycle air extracted for use in turbine cooling and the distribution of its return to the cycle. The exact influence of turbine cooling air extraction on cycle performance (thermal efficiency) will be highly dependent upon turbine airfoil material selection, its life/temperature capabilities, …
Date: February 1, 1994
Creator: Karstensen, K. W.
Object Type: Report
System: The UNT Digital Library
Advances in and uses of gamma-ray field instrumentation at Los Alamos (open access)

Advances in and uses of gamma-ray field instrumentation at Los Alamos

We are developing a set of tools to be used by the Safeguards Assay Group to solve problems found in safeguards and the domestic nuclear industry. The tools are also applicable to problems dealing with the environment, defense, and other areas of national and international interest. We have used extensively the advances in hardware and software since our last multichannel analyzer (MCA) development activities over a decade ago. We are also using our experience with and feedback from users of our previous instruments. In analyzing the instrument needs of our constituents and the characteristics of our previous instruments, which we think have inhibited their broader use, we have concluded that uses for an MCA-type instrument are widely varied and fundamentally changing,and that any new instruments should include a versatile, widely used hardware interface, which is as independent as possible of hardware standards, and which is readily interfaced to the computers or controllers rapidly evolving in the commercial sector. In addition, software tools must be provided that allow Los Alamos, users, and third parties to quickly and conveniently develop software specific to the user or the measurement to control the basic instrument we develop. This paper deals mainly with a miniature …
Date: February 1, 1994
Creator: Halbig, J. K.; Klosterbuer, S. F.; Russo, P. A.; Sprinkle, J. K. Jr.; Smith, S. E. & Ianakiev, K.
Object Type: Article
System: The UNT Digital Library
Advances in passive neutron instruments for safeguards use (open access)

Advances in passive neutron instruments for safeguards use

Passive neutron and other nondestructive assay techniques have been used extensively by the International Atomic Energy Agency to verify plutonium metal, powder, mixed oxide, pellets, rods, assemblies, scrap, and liquids. Normally, the coincidence counting rate is used to measure the {sup 240}Pu-effective mass and gamma-ray spectrometry or mass spectrometry is used to verify the plutonium isotopic ratios. During the past few years, the passive neutron detectors have been installed in plants and operated in the unattended/continuous mode. These radiation data with time continuity have made it possible to use the totals counting rate to monitor the movement of nuclear material. Monte Carlo computer codes have been used to optimize the detector designs for specific applications. The inventory sample counter (INVS-III) has been designed to have a higher efficiency (43%) and a larger uniform counting volume than the original INVS. Data analyses techniques have been developed, including the ``known alpha`` and ``known multiplication`` methods that depend on the sample. For scrap and other impure or poorly characterized samples, we have developed multiplicity counting, initially implemented in the plutonium scrap multiplicity counter. For large waste containers such as 200-L drums, we have developed the add-a-source technique to give accurate corrections for the …
Date: February 1, 1994
Creator: Menlove, H. O.; Krick, M. S.; Langner, D. G.; Miller, M. C. & Stewart, J. E.
Object Type: Article
System: The UNT Digital Library
The Advent of Failure Analysis Software Technology (open access)

The Advent of Failure Analysis Software Technology

The increasing complexity of integrated circuits demands that software tools, in addition to hardware tools, be used for successful diagnosis of failure. A series of customizable software tools have been developed that organize failure analysis information and provide expert level help to failure analysts to increase their productivity and success.
Date: February 1, 1994
Creator: Henderson, C. L. & Barnard, R. D.
Object Type: Article
System: The UNT Digital Library
Adventures in maceral separation (open access)

Adventures in maceral separation

Progress has been made in recent years in the science of maceral separation. However, there are many areas that can be improved and new areas investigated. Power of density gradient centrifugation to physically resolve macerals and submaceral species coupled with other instrumental techniques is attractive for defining the limits of coal heterogeneity as well as investigating the ability of other separation methods.
Date: February 1, 1994
Creator: Dyrkacz, G. R.
Object Type: Article
System: The UNT Digital Library
The Age, Volume [15], Number 2, February 1994 (open access)

The Age, Volume [15], Number 2, February 1994

Monthly publication containing information related to Chambers County, Texas, including current events of the Chambers County Historical Commission, the Wallisville Heritage Park, and the Chambers County historical and genealogical societies; reprinted newspaper articles about county events and citizens; and historical news and records.
Date: February 1994
Creator: Wallisville Heritage Park (Organization)
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Aging Management Guideline for commercial nuclear power plants: Battery chargers, inverters and uninterruptible power supplies. Final report (open access)

Aging Management Guideline for commercial nuclear power plants: Battery chargers, inverters and uninterruptible power supplies. Final report

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant battery chargers, inverters and uninterruptible power supplies important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already, experienced) and aging management program activities to the more generic results and recommendations presented herein.
Date: February 1, 1994
Creator: Berg, R.; Stroinski, M. & Giachetti, R.
Object Type: Report
System: The UNT Digital Library