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Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

Description: This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - … more
Date: September 1, 1985
Creator: Owen, P. T.; Michelson, D. C. & Knox, N. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fueling of tandem mirror reactors

Description: This paper summarizes the fueling requirements for experimental and demonstration tandem mirror reactors (TMRs), reviews the status of conventional pellet injectors, and identifies some candidate accelerators that may be needed for fueling tandem mirror reactors. Characteristics and limitations of three types of accelerators are described; neutral beam injectors, electromagnetic rail guns, and laser beam drivers. Based on these characteristics and limitations, a computer module was developed fo… more
Date: January 1, 1985
Creator: Gorker, G. E. & Logan, B. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Source-jerk analysis using a semi-explicit inverse kinetic technique

Description: A method is proposed for measuring the effective reproduction factor, k, in subcritical systems. The method uses the transient response of a subcritical system to the sudden removal of an extraneous neutron source (i.e., a source jerk). The response is analyzed using an inverse kinetic technique that least-squares fits the exact analytical solution corresponding to a source-jerk transient as derived from the point-reactor model. It has been found that the technique can provide an accurate means… more
Date: January 1, 1985
Creator: Spriggs, G.D. & Pederson, R.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Acceleration of beam ions during major radius compression in TFTR

Description: Tangentially co-injected deuterium beam ions were accelerated from 82 keV up to 150 keV during a major radius compression experiment in TFTR. The ion energy spectra and the variation in fusion yield were in good agreement with Fokker-Planck code simulations. In addition, the plasma rotation velocity was observed to rise during compression.
Date: September 1, 1985
Creator: Wong, K. L.; Bitter, M.; Hammett, G. W.; Heidbrink, W.; Hendel, H.; Kaita, R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Emission in the 50-80 A region from highly ionized silver in PLT tokamak plasmas

Description: The spectrum of silver emitted by Princeton Large Torus (PLT) tokamak plasmas has been recorded in the 25 to 150 A region by a multichannel time-resolving grazing-incidence spectrometer. Silver atoms have been introduced in the tokamak plasma using the laser blow-off technique. For the first time, lines emitted within the 3p-3d transitions of Ag XXIX, Ag XXX, and Ag XXXI ions, between 50 and 80 A, have been identified.
Date: September 1, 1985
Creator: Schwob, J.L.; Wouters, A.; Suckewer, S.; Cohen, S.A. & Finkenthal, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advancement of flash hydrogasification. Quarterly technical progress report, October-December 1984

Description: The design of test hardware and process development unit (PDU) modifications had been completed previously. Task VII involves the fabrication of test hardware and the modification of an existing 1-ton/h hydroliquefaction PDU at Rockwell's facilities for use as a hydrogasifier test facility. Test hardware fabrication has been completed. Modifications to the PDU were completed in July 1984. The modified facility can accommodate both 10- and 20-ft-long hydrogasifier reactors so that residence time… more
Date: September 1, 1985
Creator: Falk, A. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermonuclear inverse magnetic pumping power cycle for stellarator reactors

Description: A novel power cycle for direct conversion of alpha-particle energy into electricity is proposed for an ignited plasma in a stellarator reactor. The plasma column is alternately compressed and expanded in minor radius by periodic variation of the toroidal magnetic field strength. As a result of the way a stellarator is expected to work, the plasma pressure during expansion is greater than the corresponding pressure during compression. Therefore, negative work is done on the plasma during a compl… more
Date: September 1, 1985
Creator: Ho, D.D.M. & Kulsrud, R.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Three novel tokamak plasma regimes in TFTR

Description: Aside from extending ''standard'' ohmic and neutral beam heating studies to advanced plasma parameters, TFTR has encountered a number of special plasma regimes that have the potential to shed new light on the physics of tokamak confinement and the optimal design of future D-T facilities: (1) High-powered, neutral beam heating at low plasma densities can maintain a highly reactive hot-ion population (with quasi-steady-state beam fueling and current drive) in a tokamak configuration of modest bul… more
Date: October 1, 1985
Creator: Furth, H.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Convective equilibrium and mixing-length theory for stellarator reactors

Description: In high ..beta.. stellarator and tokamak reactors, the plasma pressure gradient in some regions of the plasma may exceed the critical pressure gradient set by ballooning instabilities. In these regions, convective cells break out to enhance the transport. As a result, the pressure gradient can rise only slightly above the critical gradient and the plasma is in another state of equilibrium - ''convective equilibrium'' - in these regions. Although the convective transport cannot be calculated pre… more
Date: September 1, 1985
Creator: Ho, D.D.M. & Kulsrud, R.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium compatibility of HT-9 and Fe-9Cr-1Mo steels

Description: Ferritic steels have been receiving significant attention for possible use as steam generator tubing, and as alternate structural materials for liquid-metal heat-transport systems in commercial fast reactors, fusion reactors, etc. The materials are chosen on the basis of their high thermal conductivity, resistance to stress-corrosion-cracking in aqueous and steam environments, favorable fabricability and fairly low cost. These steels are available in several classes based on the microstructure … more
Date: November 1, 1985
Creator: Anantatmula, R. P. & Brehm, W. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Feynmann variance-to-mean method

Description: The Feynmann and other fluctuation techniques have been shown to be useful for determining the multiplication of subcritical systems. The moments of the counting distribution from neutron detectors is analyzed to yield the multiplication value. We present the methodology and some selected applications and results and comparisons with Monte Carlo calculations.
Date: January 1, 1985
Creator: Dowdy, E. J.; Hansen, G. E. & Robba, A. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Natural convective behavior of EBR-II following a loss of flow from decay heat levels

Description: Eight loss-of-flow transients were conducted at initial decay heat levels of 0.75 to 1.6% of the rated EBR-II power. The data indicate that the natural convective flow was adequate to remove the decay heat without overheating the reactor core. Good agreement with NATDEMO and HOTCHAN predictions was obtained. (DLC)
Date: January 1, 1985
Creator: Chang, L.K.; Mohr, D.; Feldman, E.E.; Betten, P.R. & Planchon, H.P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Financial and ratepayer impacts of nuclear power plant regulatory reform

Description: Three reports - ''The Future Market for Electric Generating Capacity,'' ''Quantitative Analysis of Nuclear Power Plant Licensing Reform,'' and ''Nuclear Rate Increase Study'' are recent studies performed by the Los Alamos National Laboratory that deal with nuclear power. This presents a short summary of these three studies. More detail is given in the reports.
Date: January 1, 1985
Creator: Turpin, A. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Comparison of predicted and measured fission product behavior in the Fort St. Vrain HTGR during the first three cycles of operation

Description: Fission product release from the reactor core has been predicted by the reference design methods and compared with reactor surveillance measurements and with the results of postirradiation examination (PIE) of spent FSV fuel elements. Overall, the predictive methods have been shown to be conservative: the predicted fission gas release at the end of Cycle 3 is about five times higher than observed. The dominant source of fission gas release is as-manufactured, heavy-metal contamination; in-servi… more
Date: October 1, 1985
Creator: Hanson, D. L.; Jovanovic, V. & Burnette, R. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Advancement of flash hydrogasification. Quarterly technical progress report, July-September 1984

Description: The design of test hardware and process development unit (PDU) modifications had been completed previously. Task VII involves the fabrication of test hardware and the modification of an existing 1-ton/h hydroliquefaction PDU at Rockwell's facilities for use as a hydrogasifier test facility. Modifications to the PDU have been completed. The modified facility is designed to accommodate both 10- and 20-ft-long hydrogasifier reactors so that residence times will be in the range of 2 to 6 s when coa… more
Date: September 1, 1985
Creator: Falk, A. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MAPPS (Maintenance Personnel Performance Simulation): a computer simulation model for human reliability analysis

Description: A computer model has been developed, sensitivity tested, and evaluated capable of generating reliable estimates of human performance measures in the nuclear power plant (NPP) maintenance context. The model, entitled MAPPS (Maintenance Personnel Performance Simulation), is of the simulation type and is task-oriented. It addresses a number of person-machine, person-environment, and person-person variables and is capable of providing the user with a rich spectrum of important performance measures … more
Date: January 1, 1985
Creator: Knee, H.E. & Haas, P.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Operation of the repeating pneumatic injector on TFTR and design of an 8-shot deuterium pellet injector

Description: The repeating pneumatic hydrogen pellet injector, which was developed at the Oak Ridge National Laboratory (ORNL), has been installed and operated on the Tokamak Fusion Test Reactor (TFTR). The injector combines high-speed extruder and pneumatic acceleration technologies to propel frozen hydrogen isotope pellets repetitively at high speeds. The pellets are transported to the plasma in an injection line that also serves to minimize the gas loading on the torus; the injection line incorporates a … more
Date: January 1, 1985
Creator: Combs, S. K.; Milora, S. L.; Foust, C. R.; Baylor, L. R.; Burris, R. D.; Fisher, P. W. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Methodology for estimating sodium aerosol concentrations during breeder reactor fires

Description: We have devised and applied a methodology for estimating the concentration of aerosols released at building surfaces and monitored at other building surface points. We have used this methodology to make calculations that suggest, for one air-cooled breeder reactor design, cooling will not be compromised by severe liquid-metal fires.
Date: January 1, 1985
Creator: Fields, D. E. & Miller, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Measured residual stresses in overlay pipe weldments removed from service

Description: Surface and throughwall residual stresses were measured on an elbow-to-pipe weldment that had been removed from the Hatch-2 reactor about a year after the application of a weld overlay. The results were compared with experimental measurements on three mock-up weldments and with finite-element calculations. The comparison shows that there are significant differences in the form and magnitude of the residual stress distributions. However, even after more than a year of service, the residual stres… more
Date: February 1, 1985
Creator: Shack, W.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Safety characteristics of the integral fast reactor concept

Description: The Integral Fast Reactor (IFR) concept is an innovative approach to liquid metal reactor design which is being studied by Argonne National Laboratory. Two of the key features of the IFR design are a metal fuel core design, based on the fuel technology developed at EBR-II, and an integral fuel cycle with a colocated fuel cycle facility based on the compact and simplified process steps made possible by the use of metal fuel. The paper presents the safety characteristics of the IFR concept which … more
Date: January 1, 1985
Creator: Marchaterre, J.F.; Cahalan, J.E.; Sevy, R.H. & Wright, A.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Survey of physical property data for several alloys. [Nitronic 33; copper C10400; copper C17510]

Description: This report summarizes an examination of physical property data available in the literature for six alloys of potential interest to the Toroidal Fusion Core Experiment in the Fusion Energy Program. The properties of thermal expansion, density, specific heat, electrical resistivity, and thermal conductivity were compiled for six alloys: Nitronic 33, a low-nickel, high manganese stainless steel; nickel-base Inconnel Alloys 625, 718, and X-750; and copper alloys C10400 and C17510. The temperatures… more
Date: August 1, 1985
Creator: Pawel, R. E. & Williams, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production of high density plasma by pellet injection in TFTR

Description: High plasma densities have been produced in ohmic and neutral beam heated discharges on TFTR using a repeating pneumatic pellet injector developed at Oak Ridge National Laboratory (ORNL). Line average plasma densities as high as 1 x 10/sup 14/ cm/sup -3/ have been attained by injection of five 2.7 mm deuterium pellets ..delta..n/sub e/ = 2 x 10/sup 14/ cm/sup -3/ over a one-second interval into a stetched neutral beam pulse. Injection of a single large (4 mm) pellet in ohmic discharge has produ… more
Date: January 1, 1985
Creator: Milora, S. L.; Schmidt, G. L.; Combs, S. K.; Bush, C. E.; Goldston, R. J.; Grek, B. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TRAC-PF1/MOD-1 analysis of Loss-Of-Flow Test L9-4

Description: Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC) to provide advanced best-estimate predictions of postulated accidents in pressurized water reactors (PWRs) and for many thermal-hydraulic experimental facilities. As part of our independent assessment of code version TRAC-PF1/MOD1, we analyzed Loss-of-Fluid Test (LOFT) L9-4 and compared the test data to the calculated results. This was an anticipated-transient-without-scram test in which the pumps were tripp… more
Date: January 1, 1985
Creator: Meier, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Engineering data bases for refractory alloys

Description: Refractory alloys based on niobium, molybdenum, tantalum, and tungsten are required for the multi-100kW(e) space nuclear reactor power concepts that have been assessed in the SP-100 Program because of the extremely high temperatures involved. A review is presented of the technology efforts on the candidate refractory alloys in the areas of availability/fabricability, mechanical properties, irradiation effects, and compatibility. Of the niobium-base alloys, only Nb-1Zr has a data base that is su… more
Date: January 1, 1985
Creator: Cooper, R.H. Jr. & Harms, W.O.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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