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Pressurized fluidized-bed combustion technology exchange workshop

Description: The pressurized fluidized-bed combustion technology exchange workshop was held June 5 and 6, 1979, at The Meadowlands Hilton Hotel, Secaucus, New Jersey. Eleven papers have been entered individually into EDB and ERA. The papers include reviews of the US DOE and EPRI programs in this area and papers by Swedish, West German, British and American organizations. The British papers concern the joint program of the USA, UK and FRG at Leatherhead. The key factor in several papers is the use of fluidized bed combustors, gas turbines, and steam turbines in combined-cycle power plants. One paper examines several combined-cycle alternatives. (LTN)
Date: April 1, 1980
Creator: ,
Partner: UNT Libraries Government Documents Department

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

Description: Each testing and analytical facility performing waste characterization activities for the Waste Isolation Pilot Plant (WIPP) participates in the Performance Demonstration Program (PDP) to comply with the Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC) (DOE/WIPP-02-3122) and the Quality Assurance Program Document (QAPD) (CBFO-94-1012). The PDP serves as a quality control check for data generated in the characterization of waste destined for WIPP. Single blind audit samples are prepared and distributed to each of the facilities participating in the PDP. The PDP evaluates analyses of simulated headspace gases, constituents of the Resource Conservation and Recovery Act (RCRA), and transuranic (TRU) radionuclides using nondestructive assay (NDA) techniques.
Date: April 1, 2009
Creator: /A, N
Partner: UNT Libraries Government Documents Department

Addendum to the Corrective Action Investigation Plan for Corrective Action Unit 447, Project Shoal Area, Nevada Subsurface Site, Revision 1, April 1999

Description: The report is an addendum to Chapter 6.0, ''Field Investigation,'' of the Corrective Action Investigation Plan for Corrective Action Unit 447: Project Shoal Area, Nevada Subsurface Site, DOE/NV--513. Sections 6.0 and 6.1 in DOE/NV--513 continue to stand, with the sections below following after them. These new sections represent information that was not available at the time DOE/NV--513 was issued.
Date: April 13, 1999
Creator: /NV, DOE
Partner: UNT Libraries Government Documents Department

Corrective Action Investigation Plan for Corrective Action Unit 405: Area 3 Septic Systems, Tonopah Test Range, Nevada(April 2001, Rev. 0) with Record of Technical Change No. 1

Description: This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's (DOE/NV's) approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 405, Area 3 Septic Systems, Tonopah Test Range (TTR), under the Federal Facility Agreement and Consent Order. Corrective Action Unit 405 consists of Corrective Action Sites 03-05-002-SW03, 03-05-002-SW04, and 03-05-002-SW07 (also collectively known as: Septic Waste Systems [SWSs] 3, 4, and 7). Located in Area 3 in the northwest section of the TTR, approximately 140 miles northwest of Las Vegas, this location was historically (between 1960 and 1990) used as a research facility with the mission to perform defense-related projects, and whose operations generated sanitary and industrial wastewaters potentially contaminated with COPCs and disposed of in septic tanks and leachfields. Though Septic Waste Systems 3, 4, and 7 were origin ally constructed to receive sanitary sewage, they may have inadvertently received effluent containing potentially hazardous and radiological constituents containing acetone, benzene, ethylbenzene, 4-methyl-2-pentanone, toluene, xylenes, volatile organic compound constituents, phenols, arsenic, barium, lead, mercury, hydrocarbons of oil and grease, and uranium-234, -235, and -238. The Area 3 septic systems were documented in a DOE/NV 1996 report as being included in the septic tank abandonment program conducted by Sandia National Laboratories in 1993; however, this program was not completed and the possibility exists that some of the Area 3 septic tanks may not have been abandoned. Even though all of the SWSs addressed in this CAIP are inactive, geophysical surveys conducted in 1993 were generally inconclusive and did not provide useful data for the purposes of this investigation. The scope of this current investigation, therefore, will be to determine the existence of the identified CO PCs and excavation will be the primary investigation method employed for ...
Date: April 26, 2001
Creator: /NV, DOE
Partner: UNT Libraries Government Documents Department

Final Addendum to the Corrective Action Investigation Plan for Corrective Action Unit 447, Project Shoal area, Nevada, Subsurface Site, Revision 1, April 1999

Description: Chapter 6.0 in the Shoal Subsurface Corrective Action Investigation Plan (CAIP) provided a framework for a data decision analysis (DDA) that would be used to determine investigation methods and data collection methods to minimize uncertainty in groundwater flow and transport predictions. Uncertain parameters were identified and possible field activities that could provide information on those uncertain parameters were briefly described. The DDA has now been completed (Pohll and Forsgren, 1999) and prompts this addendum to describe the outcome of the DDA, how it was used to determine the next phase of data collection for the Shoal Subsurface activities, and to provide details of the planned investigations sufficient to allow understanding of the scope and completion of the tasks involved.
Date: April 1, 1999
Creator: /NV, DOE
Partner: UNT Libraries Government Documents Department

Housekeeping Closure Report for Corrective Action Unit 36: Areas 8, 10, 16, 18, and 26, Housekeeping Waste Sites, Nevada Test Site, Nevada

Description: The Federal Facility Agreement and Consent Order was entered into by the State of Nevada, U.S. Department of Energy, and U.S. Department of Defense to identify sites of potential historical contamination and implement corrective actions based on public health and environmental considerations. The facilities subject to this agreement include the Nevada Test Site (NTS), parts of the Tonopah Test Range, parts to the Nellis Air Force Range, the Central Nevada Test Area, and the Project Shoal Area. Corrective Action Sites (CASs) are areas potentially requiring corrective actions and may include solid waste management units, individual disposal, or release sites. Based on geography, technical similarity, agency responsibility, or other appropriate reasons, CASs are grouped together into Corrective Action Units (CAUs) for the purposes of determining corrective actions. This report contains the Closure Verification Forms for cleanup activities performed at the 12 CASs within CAU 36 on the NTS. The Housekeeping Closure Verification Form for each CAS provides the location, directions to the site, general description, and photographs of the site before and after cleanup activities. Housekeeping activities at these sites included removal of batteries, buckets, cans, drums, gas cylinders, and smoke pots. Based on these activities, no further action is required at these CASs.
Date: April 26, 2000
Creator: /NV, DOE
Partner: UNT Libraries Government Documents Department

Project Execution Plan, Waste Management Division, Nevada Operations Office, U.S. Department of Energy, April 2000

Description: This plan addresses project activities encompassed by the U.S. Department of Energy/Nevada Operations Office Waste Management Division and conforms to the requirements contained in the ''Life Cycle Asset Management,'' U.S. Department of Energy Order O430.1A; the Joint Program Office Policy on Project Management in Support of DOE Order O430.1, and the Project Execution and Engineering Management Planning Guide. The plan also reflects the milestone philosophies of the Federal Facility Agreement and Consent Order, as agreed to by the state of Nevada; and traditional project management philosophies such as the development of life cycle costs, schedules, and work scope; identification of roles and responsibilities; and baseline management and controls.
Date: April 1, 2000
Creator: /NV, DOE
Partner: UNT Libraries Government Documents Department

Remedial Action Work Plan Amchitka Island Mud Pit Closures

Description: This remedial action work plan presents the project organization and construction procedures developed for the performance of the remedial actions at U.S. Department of Energy (DOE's) sites on Amchitka Island, Alaska. During the late1960s and early 1970s, the U.S. Department of Defense and the U.S. Atomic Energy Commission (the predecessor agency to DOE) used Amchitka Island as a site for underground nuclear tests. A total of nine sites on the Island were considered for nuclear testing; however, tests were only conducted at three sites (i.e., Long Shot in 1965, Milrow in 1969, and Cannikin in 1971). In addition to these three sites, large diameter emplacement holes were drilled in two other locations (Sites D and F) and an exploratory hole was in a third location (Site E). It was estimated that approximately 195 acres were disturbed by drilling or preparation for drilling in conjunction with these activities. The disturbed areas include access roads, spoil-disposal areas, mud pits which have impacted the environment, and an underground storage tank at the hot mix plant which was used to support asphalt-paving operations on the island. The remedial action objective for Amchitka Island is to eliminate human and ecological exposure to contaminants by capping drilling mud pits, removing the tank contents, and closing the tank in place. The remedial actions will meet State of Alaska regulations, U.S. Fish and Wildlife Service refuge management goals, address stakeholder concerns, and address the cultural beliefs and practices of the native people. The U.S. Department of Energy, Nevada Operations Office will conduct work on Amchitka Island under the authority of the Comprehensive Emergency Response, Compensation, and Liability Act. Field activities are scheduled to take place May through September 2001. The results of these activities will be presented in a subsequent Closure Report.
Date: April 5, 2001
Creator: /NV, DOE
Partner: UNT Libraries Government Documents Department

Scaled Experimental Modeling of VHTR Plenum Flows

Description: Abstract The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S. which has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. Various scaled heated gas and water flow facilities were investigated for modeling VHTR upper and lower plenum flows during the decay heat portion of a pressurized conduction-cooldown scenario and for modeling thermal mixing and stratification (“thermal striping”) in the lower plenum during normal operation. It was concluded, based on phenomena scaling and instrumentation and other practical considerations, that a heated water flow scale model facility is preferable to a heated gas flow facility and to unheated facilities which use fluids with ranges of density to simulate the density effect of heating. For a heated water flow lower plenum model, both the Richardson numbers and Reynolds numbers may be approximately matched for conduction-cooldown natural circulation conditions. Thermal mixing during normal operation may be simulated but at lower, but still fully turbulent, Reynolds numbers than in the prototype. Natural circulation flows in the upper plenum may also be simulated in a separate heated water flow facility that uses the same plumbing as the lower plenum model. However, Reynolds number scaling distortions will occur at matching Richardson numbers due primarily to the necessity of using a reduced number of channels connected to the plenum than in the prototype (which has approximately 11,000 core channels connected to the upper plenum) in an otherwise geometrically scaled model. Experiments conducted in either or both facilities will meet the objectives of providing benchmark data for the validation of codes proposed for NGNP designs and safety studies, as well as providing a better understanding of the complex flow phenomena in the plenums.
Date: April 1, 2007
Creator: 15, ICONE
Partner: UNT Libraries Government Documents Department

Development of Advanced Wear and Corrosion Resistant Systems Through Laser Surface Alloying and Materials Processing

Description: The stability of tungsten carbide particles in iron-rich and nickel-rich liquid during the laser surface alloying (LSA) process was investigated. Kinetic calculations indicate a rapid dissolution of tungsten carbide particles in iron-rich liquid, as compared with the dissolution rate in nickel-rich liquid. Optical microscopy indicated a heterogeneous microstructure around the tungsten particles that is in agreement with concentration gradients predicted by kinetic calculation. The work demonstrates the applicability of computational thermodynamics and kinetic models for the LSA process.
Date: April 1, 2002
Creator: A, Babu S S Martukanitz R P Parks K D David S
Partner: UNT Libraries Government Documents Department

Pressure-induced Breaking of Equilibrium Flux Surfaces in the W7AS Stellarator

Description: Calculations are presented for two shots in the W7AS stellarator which differ only in the magnitude of the current in the divertor control coil, but have very different values of experimentally attainable β (<β> ≈ 2.7% versus <β> ≈ 1.8%). Equilibrium calculations find that a region of chaotic magnetic field line trajectories fills approximately the outer 1/3 of the cross-section in each of these configurations. The field lines in the stochastic region are calculated to behave as if the flux surfaces are broken only locally near the outer midplane and are preserved elsewhere. The calculated magnetic field line diffusion coefficients in the stochastic regions for the two shots are consistent with the observed differences in the attainable β, and are also consistent with the differences in the reconstructed pressure profiles.
Date: April 24, 2007
Creator: A. Reiman, M.C. Zarnstorff, D. Monticello, A. Weller, J. Geiger, and the W7-AS Team
Partner: UNT Libraries Government Documents Department