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First wall/blanket/shield design and optimization system
First wall/blanket/shield design and optimization system (BSDOS) has been developed to provide a state-of-the-art design tool for fast accurate analysis. In addition, it has been designed to perform several other functions: (1) allowing comparison and evaluation studies for different concepts using the same data bases and ground rules, (2) permitting the use of any figure of merit in the evaluation studies, (3) optimizing the first wall/blanket/shield design parameters for any figure of merit under several design constraints, (4) permitting the use of different reactor parameters in the evaluation and optimization analyses, (5) allowing the use of improved eingineering data bases to study the impact on the design performance for planning future research and development, and (6) evaluating the effect of the data base uncertainties on the design performance. BSDOS is the first design and optimization system to couple the highly interacting neutronics, heat transfer, thermal hydraulics, stress analysis, radioactivity and decay-heat analyses, tritium balance, and capital cost. A brief description of the main features of BSDOS is given in this paper. Also, results from using BSDOS to perform design analysis for several reactor components are presented. 17 refs., 1 fig., 2 tabs.
Date:
February 1, 1988
Creator:
Gohar, Y.; Baker, C.; Attaya, H.; Cha, Y.; Majumdar, S. & Scandora, T.
Object Type:
Article
System:
The UNT Digital Library
Energy Program annual report
The national economy is particularly dependent on efficient electrical generation and transportation. Electrical demand continues to grow and will increasingly rely on coal and nuclear fuels. The nuclear power industry still has not found a solution to the problem of disposing of the waste produced by nuclear reactors. Although coal is in ample supply and the infrastructure is in place for its utilization, environmental problems and improved conversion processes remain technical challenges. In the case of transportation, the nation depends almost exclusively on liquid fuels with attendant reliance on imported oil. Economic alternates---synfuels from coal, natural gas, and oil shale, or fuel cells and batteries---have yet to be developed or perfected so as to impact the marketplace. Inefficiencies in energy conversion in almost all phases of resource utilization remain. These collective problems are the focus of the Energy Program.
Date:
February 1, 1988
Creator:
Borg, I.Y. (ed.)
Object Type:
Report
System:
The UNT Digital Library
Modeling studies on the precipitation of Kr after implantation into metals
A rate-theory approach is applied to interpreting observations on the precipitation of Kr injected into Ni at temperatures between 25 and 560/degree/C. At temperatures of 400/degree/C or higher, the implanted Kr precipitates evolve into a bi-modal size distribution containing small solid precipitates and an additional population of larger, faceted bubbles. The calculations explore the dependence of the observed bi-modal distribution on the maximum size of the solid Kr precipitates and the effect of this dependence on bubble mobility. The analysis suggests that during the irradiation, whereas the large bubbles move by surface diffusion, the solid Kr precipitates are immobile. The relevance of the Kr-Ni interaction on the solid Kr precipitates size cutoff is discussed. 18 refs., 8 figs., 2 tabs.
Date:
February 1, 1988
Creator:
Rest, J.
Object Type:
Article
System:
The UNT Digital Library
Fusion energy development: Breakeven and beyond: Keynote address
The scientific feasibility, technological inevitability, and economic necessity of fusion as an energy source are discussed.
Date:
February 1, 1988
Creator:
Furth, H.P.
Object Type:
Article
System:
The UNT Digital Library
Thermophysical properties of argon
The entire report consists of tables of thermodynamic properties (including sound velocity, thermal conductivity and diffusivity, Prandtl number, density) of argon at 86 to 400/degree/K, in the form of isobars over 0.9 to 100 bars. (DLC)
Date:
February 1, 1988
Creator:
Jaques, A.
Object Type:
Report
System:
The UNT Digital Library
The safety record at the tritium systems test assembly
This work addresses an important objective of the TSTA-demonstrating that the large tritium inventories required for fusion reactors can be routinely handled, without radiation exposure to operating personnel and without significant environemtnal releases. The techniques by which TSTA has achieved low releases and personnel exposures include high-integrity primary piping systems that exclude contact between tritium and organic materials, a secondary containment system that encloses all primary tritium piping in a controlled environment, an efficient, all-purpose tritium waste-treatment plant with 100% availability, and ultrasensitive, real-time diagnostics for anticipating and preventing releases, and for detection and location of tritium leaks in a low-risk mode. 5 refs., 11 figs., 2 tabs.
Date:
February 1, 1988
Creator:
Coffin, D.O.
Object Type:
Article
System:
The UNT Digital Library
Blanket technology experiments at Argonne National Laboratory
Argonne National Laboratory has the largest US program for the development of blanket technology. The goals of the program are to resolve critical issues for different blanket concepts, to develop the understanding and predictive capability of blanket behavior, and to develop the technology needed to build and operate advanced fusion blankets. The projects within the program are liquid metal MHD, breeder neutronics, tritium oxidation, transient electromagnetics, FLIBE chemistry, and insulator coatings. The present status and recent results of the projects are described.
Date:
February 1, 1988
Creator:
Mattas, R. F.; Reed, C. B.; Picologlou, B.; Finn, P.; Clemmer, R.; Porges, K. et al.
Object Type:
Article
System:
The UNT Digital Library
Middle Fork and Upper Salmon River Habitat Improvement Implementation Plan, FY 1988-1992.
This document presents an implementation plan for completing the phase II portion of the Middle Fork and Upper Salmon River Habitat Improvement Agreement. Underseeding of spawning adult salmon and steelhead, high instream sediment levels, a lack of habitat diversity in the form of overhanging riparian vegetation and edge, and barriers to both adult and juvenile anadromous fish migration were identified as the principal factors limiting anadromous fish production in the project area. Underseeding is being addressed in other projects sponsored and funded by the Bonneville Power Administration while this implementation plan lays out a schedule for resolving the other identified limiting factors. The primary goal of this program is to increase the quality and quantity of anadromous fish habitat (spring chinook and summer steelhead) with an emphasis on the survival of the wild stocks. This goal will be achieved by reducing the impact of sediment loading, improving riparian vegetation, eliminating passage barriers, and increasing habitat diversity. Meeting the above goal will provide off-site mitigation under the manadate of the pacific northwest electric power planning and conservation act of 1980. Project implementation will follow measures in the Northwest Power Council's Columbia River Fish and Wildlife Program. 9 refs., 3 figs., 5 …
Date:
February 1, 1988
Creator:
Andrews, John & Everson, Larry B.
Object Type:
Report
System:
The UNT Digital Library
Gamma rays from Cygnus X-1: Modeling and nonthermal pair production
The gamma-ray bump observed between 0.5 and 2 MeV in the spectrum of Cygnus X-1 can be interpreted as the thermal emissions from a hot (kT)approximately)400 keV) pair-dominated cloud. We argue that the X-rays and gamma rays are produced in separate emission regions, and calculate the photon-photon pair production rate from X-ray and gamma-ray interactions in the vicinity of Cyg X-1 by employing a simplified geometry for the two emitting regions.
Date:
February 1, 1988
Creator:
Dermer, C. D. & Liang, E. P.
Object Type:
Article
System:
The UNT Digital Library
Nonlinear gyrokinetic theory for finite-BETA plasmas
A self-consistent and energy-conserving set of nonlinear gyrokinetic equations, consisting of the averaged Vlasov and Maxwell's equations for finite-..beta.. plasmas, is derived. The method utilized in the present investigation is based on the Hamiltonian formalism and Lie transformation. The resulting formation is valid for arbitrary values of k/perpendicular//rho//sub i/ and, therefore, is most suitable for studying linear and nonlinear evolution of microinstabilities in tokamak plasmas as well as other areas of plasma physics where the finite Larmor radius effects are important. Because the underlying Hamiltonian structure is preserved in the present formalism, these equations are directly applicable to numerical studies based on the existing gyrokinetic particle simulation techniques. 31 refs.
Date:
February 1, 1988
Creator:
Hahm, T. S.; Lee, W. W. & Brizard, A.
Object Type:
Report
System:
The UNT Digital Library
Insertion device and beam line plans for the Advanced Photon Source: A report and recommendations by the Insertion Device and Beam Line Planning Committee
In the 7-GeV Advanced Photon Source (APS) Conceptual Design Report (CDR), fifteen complete experimental beam lines were specified in order to establish a representative technical and cost base for the components involved. In order to optimize the composition of the insertion devices and the beam line, these funds are considered a ''Trust Fund.'' The present report evaluates the optimization for the distribution of these funds so that the short- and long-term research programs will be most productive, making the facility more attractive from the user's point of view. It is recommended that part of the ''Trust Fund'' be used for the construction of the insertion devices, the front-end components, and the first-optics, minimizing the cost to potential users of completing a beam line. In addition, the possibility of cost savings resulting from replication and standardization of high multiplicity components (such as IDs, front ends, and first-optics instrumentation) is addressed. 2 refs., 5 tabs.
Date:
February 1, 1988
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Waste acid detoxification and reclamation: Phase 1, Project planning and concept development
The objectives of this project are to develop processes for reducing the volume, quantity, and toxicity of metal-bearing waste acids. The primary incentives for implemeting these types of waste minimization processes are regulatory and economic in that they meet requirements in the Resource Conservation and Recovery Act and reduce the cost for treatment, storage, and disposal. Two precipitation processes and a distillation process are being developed to minimize waste from fuel fabrication operations, which comprise a series of metal-finishing operations. Waste process acids, such as HF/--/HNO/sub 3/ etch solutions contianing Zr as a major metal impurity and HNO/sub 3/ strip solutions containing Cu as a major metal impurity, are detoxified and reclaimed by concurrently precipitating heavy metals and regenerating acid for recycle. Acid from a third waste acid stream generated from chemical milling operations will be reclaimed using distillation. This stream comprises HNO/sub 3/ and H/sub 2/SO/sub 4/ which contains U as the major metal impurity. Distillation allows NO/sub 3//sup /minus// to be displaced by SO/sub 4//sup /minus/2/ in metal salts; free HNO/sub 3/ is then vaporized from the U-bearing sulfate stream. Uranium can be recovered from the sulfate stream in downstream precipitation step. These waste minimization processes were developed …
Date:
February 1, 1988
Creator:
Stewart, T. L. & Brouns, T. M.
Object Type:
Report
System:
The UNT Digital Library
The hole of a blanket tritium system on the fusion fuel cycle
The requirements of tritium technology are centered in three main areas, i.e., (1) fuel processing, (2) breeder tritium extraction, and (3) tritium containment. The gaseous tritium stream from the breeder tritium extraction system is significantly different from the plasma exhaust stream and, therefore, may have important impact on the operation of the fuel processing system. For some blankets, such as aqueous solution blanket, the blanket tritium stream may dominate the fuel processing system in terms of component size and power consumption. The importance of the blanket interface to a fuel processing experiment, such as TSTA, has been identified. The initial work to define the blanket processing system, which is proposed to be added as part of TSTA, will be discussed here.
Date:
February 1988
Creator:
Sze, D.K.; Finn, P.; Clemmer, R.; Anderson, J.; Bartlit, J.; Naruse, Y. et al.
Object Type:
Article
System:
The UNT Digital Library
Initial evaluation of photographic data of F- and H-Area seepage basin outcrops
Photographic data for the Savannah River Plant (SRP) were reviewed for 1961 through 1987 to determine the value of this photography in estimating the timing and extent of the F- and H-Area seepage basin outcrops along the upper Four Mile Creek floodplain. In excess of 15,000 frames of photography of the SRP were reviewed. The quality of the photography varied widely and included panchromatic (black and white), natural color, and false color infrared. Altitudes of the photography ranged from 2,000 feet above ground level (AGL) to 40,000 feet AGL. For each year the best photography at the lowest altitude was evaluated to determine the presence of vegetation damage downslope of the F- and H-Area seepage basins. Criteria of no visible evidence of vegetation (forest canopy) damage, initial evidence of vegetation or canopy damage, canopy thinning, tree mortality, and expansion of vegtation damage and/or tree mortality zones were applied to each of the photographs. In this initial evaluation, only the largest of the outcrops below the seepage basins were evaluated. (3 tabs.)
Date:
February 8, 1988
Creator:
Mackey, H. E., Jr.
Object Type:
Report
System:
The UNT Digital Library
The effective stiffness of nuclei near magic numbers
This paper trys to explain the rapid increase in the apparent size of the rubidium isotope nuclei around the magic number N = 50. Droplet and deformation models are used to evaluate the measured data. 6 refs., 4 figs.
Date:
February 1, 1988
Creator:
Meyers, W.D. & Rozmej, P.
Object Type:
Article
System:
The UNT Digital Library
An HVEM study of displacement cascade damage in Nb/sub 3/Sn at 13 K
TEM images of the martensite structure in Nb/sub 3/Sn were recorded at various temperatures between 12 and 30/degree/K. The transition to the superconducting state was observed by a slight deflection of the electron beam due to a perturbation of the magnetic field of the objective lens at the sample. The primary interest is in irradiation effects due to fast neutrons from a fusion reactor, and therefore ion irradiation conditions that are somewhat comparable to this were selected. These consisted of 50 keV Xe/sup /plus// irradiations to simulate neutron produced cascades in a near surface region and 1.5 Mev Kr/sup /plus// to produce cascade damage through a greater sample thickness. Defect images were obtained as a function of ion dose at 13/degree/K using both fundamental and superlattice dark-field reflections in two-beam conditions. For 50 keV Xe/sup /plus// irradiations at 13/degree/K the defect yields were quite low at low ion doses where individual defect cascades are well separated. At higher ion doses when significant cascade overlap is present, defect density and contrast became greater than expected. Annealing to room temperature produced a large increase in defect density. Irradiation by 1.5 MeV Kr/sup /plus// at 15/degree/K removed the martensite structure by an ion …
Date:
February 1, 1988
Creator:
Kirk, M. A.; Baker, M. C.; Kestel, B. J.; Weber, H. W. & Kampwirth, R. T.
Object Type:
Article
System:
The UNT Digital Library
Design analysis and optimization of self-cooled lithium blankets and shields
A study of self-cooled lithium blankets was carried out to define the performance of these blankets and to determine the potential to operate at the maximum possible values of the performance parameters. The main design parameters considered during the course of the study were the tritium breeding ratio, the blanket energy multiplication factor, the energy fraction lost to the shield, the total blanket thickness, the reflector material selection, and the compositions of the different blanket zones. Another study was carried out to determine materials, compositions, arrangements, and thickness of the shield zone for the reference blanket. Helium and water-cooled shields were optimized for the inboard and outboard sections of the reactor. Based on the above two studies, the reference blanket and shield configurations were developed for the ANL Tokamak Power Systems Study. The helium-cooled shield was selected for use with liquid metal blankets to reduce safety concerns related to lithium-water reactivity. This helium-cooled shield provides shielding characteristics similar to a conventional water-cooled shield. The analyses and results from these studies are the subject of this paper. 12 refs., 4 figs., 2 tabs.
Date:
February 1, 1988
Creator:
Gohar, Y.
Object Type:
Article
System:
The UNT Digital Library
Considerations for the use of synchrotron radiation sources to measure sub-keV x-ray photoabsorption cross sections in transmission
Sub-keV x-ray photoabsorption cross section measurements in transmission have been made using synchrotron radiation beam lines on the VUV storage ring at the National Synchrotron Light Source (NSLS) and on the SPEAR storage ring at Stanford. The experimental considerations associated with making absolute measurements are reviewed, along with techniques for resolving difficulties. Suggestions for future measurements are included.
Date:
February 1, 1988
Creator:
Tirsell, K.G. & Del Grande, N.K.
Object Type:
Article
System:
The UNT Digital Library
Beauty physics at the ultrahigh energies of the ELOISATRON (Euroasiatic Long Intersecting Superconducting Accelerator Synchrotron)
The potential for experimentally studying B physics at the proposed INFN 100 TeV ELOISATRON (Euroasiatic Long Intersecting Superconducting Accelerator Synchrotron) is compared with possibilities at 40 TeV at the Superconducting Super Collider. The effect of the increase in center of mass energy on the production and decay of B mesons has been investigated, particularly with respect to the accummulation of large samples of B hadron decays necessary for the detection of CP violating effects. 13 refs., 7 figs., 1 tab.
Date:
February 1, 1988
Creator:
Cox, B.
Object Type:
Article
System:
The UNT Digital Library
Sulfur tolerant anode materials
The goal of this program is the development of a molten carbonate fuel cell (MCFC) anode which is more tolerant of sulfur contaminants in the fuel than the current state-of-the-art nickel-based anode structures. This program addresses two different but related aspects of the sulfur contamination problem. The primary aspect is concerned with the development of a sulfur tolerant electrocatalyst for the fuel oxidation reaction. A secondary issue is the development of a sulfur tolerant water-gas-shift reaction catalyst and an investigation of potential steam reforming catalysts which also have some sulfur tolerant capabilities. These two aspects are being addressed as two separate tasks.
Date:
February 1, 1988
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Relationship between fabrication parameters and structural characteristics of sintered lithium orthosilicate
Lithium orthosilicate (Li/sub 4/SiO/sub 4/) powder was synthesized by the solid-state reaction of lithium oxide with amorphous silica, and the effects of fabrication parameters on the structural characteristics of the product were investigated. Processing considerations such as milling media, drying technique, calcination time and temperature, pressing behavior, sintering time and temperatures, and impurity concentration were addressed. The initial powder particle size was observed to be important in achieving high sintered density, with densities as high as 98% TD achieved with a particle size of approximately 1 ..mu..m. 9 refs., 6 figs.
Date:
February 1, 1988
Creator:
Chu, C.Y.; Bar, K.; Singh, J.B.; Poeppel, R.B. & Billone, M.C.
Object Type:
Article
System:
The UNT Digital Library
Proposal to the Department of Energy for participation in the UA1 experiment
This proposal is to the Department of Energy for 501.6K dollars (349.6K operations and 152K equipment) for continued participation in the UA1 experiment on proton-antiproton collisions. The UA1 experiment is the study of high-energy proton-antiproton collisions in the Super-Proton-synchrotron (SPS) Collider at CERN. A major upgrade of the UA1 detector is in progress for operation with the upgraded antiproton source (ACOL). The US groups have played an increasingly prominent role in UA1 during the past few years. This paper discusses the data analysis that has been done by the group of the position detector and it's hardware.
Date:
February 1, 1988
Creator:
Rohlf, J.W.
Object Type:
Report
System:
The UNT Digital Library
Northwest Hazardous Waste Research, Development, and Demonstration Center: Program Plan. [Contains glossary]
The Northwest Hazardous Waste Research, Development, and Demonstration Center was created as part of an ongoing federal effort to provide technologies and methods that protect human health and welfare and environment from hazardous wastes. The Center was established by the Superfund Amendments and Reauthorization Act (SARA) to develop and adapt innovative technologies and methods for assessing the impacts of and remediating inactive hazardous and radioactive mixed-waste sites. The Superfund legislation authorized $10 million for Pacific Northwest Laboratory to establish and operate the Center over a 5-year period. Under this legislation, Congress authorized $10 million each to support research, development, and demonstration (RD and D) on hazardous and radioactive mixed-waste problems in Idaho, Montana, Oregon, and Washington, including the Hanford Site. In 1987, the Center initiated its RD and D activities and prepared this Program Plan that presents the framework within which the Center will carry out its mission. Section 1.0 describes the Center, its mission, objectives, organization, and relationship to other programs. Section 2.0 describes the Center's RD and D strategy and contains the RD and D objectives, priorities, and process to be used to select specific projects. Section 3.0 contains the Center's FY 1988 operating plan and describes the …
Date:
February 1, 1988
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A tritium-compatible piezoelectric valve for the tokamak fusion test reactor
This work describes modifications made to a commercial piezoelectric valve to make it sufficiently tritium compatible for the TFTR trritium injection scenario. The results of testing the valve for leakage and performance following a series of progressively more severe tritium exposures are also presented. Finally, a proposal for a totally radiation-compatible piezoelectric valve, suitable for tritium-burning fusion machines of the future, is decribed. 9 refs., 2 figs., 1 tab.
Date:
February 1, 1988
Creator:
Coffin, D.O.; Cole, S.P. & Wilhelm, R.C.
Object Type:
Article
System:
The UNT Digital Library