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Evaluation of the Emission, Transport, and Deposition of Mercury, Fine Particulate Matter, and Arsenic From Coal-Based Power Plants in the Ohio River Valley Region Progress Report
4
Fiscal Year 2000
4
ARM Facilities Newsletter
2
Fiscal Year 2002
2
Fiscal Year 2003
2
Fiscal Year 2004
2
Fiscal Year 2005
2
Winter Fuels Report
2
Carbon Sequestration on Surface Mine Lands Quarterly Report
1
Development fo Novel Boron-based Multilayer Thin-Film Progress Report
1
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Time-resolved fast-neutron pinhole camera for studying thermonuclear plasmas
A fast-neutron pinhole camera with high detection efficiency and nanosecond time-resolution has been developed and applied to the investigation of the spatial and temporal distributions of DD- and DT-neutrons produced by thermonuclear plasmas. The pinhole consists of a specially designed 1.15 m long copper collimator with an effective aperture of 1 mm diameter. Several different types of spatial resolution detectors have been used at the image plane: (1) a multi-element, scintillation-photomultiplier system used for time-resolved measurements consisting of sixty-one individual detectors, (2) a scintillation-fiber-chamber coupled to a gated image-intensifier tube used for direct photographing of the neutron image, and (3) a propane bubble chamber used for time-integrated recording with a capability to distinguish DD- from DT-neutrons. Pulsed neutron sources with typical dimensions of 1 cm emitting of the order of 10/sup 12/ neutrons over a time period of 10-100 nsec have been investigated. A spatial resolution of 1 mm and a time resolution of approximately 10 nsec was achieved in the investigations of dense plasma compression phenomena.
Date:
February 2, 1976
Creator:
Bauer, R. W. & Weingart, R. C.
Object Type:
Article
System:
The UNT Digital Library
Power threshold for neutral beam current drive
For fully noninductive current drive in tokamaks using neutral beams, there is a power and density threshold condition, setting a minimum value for P{sup 3/2}/n{sup 2}. If this condition is not met, stationary state cannot occur, and a tokamak discharge will collapse. This is a consequence of the coupling between current and electron temperature, or between current drive efficiency and energy confinement time. 4 figs.
Date:
October 2, 1989
Creator:
Politzer, P. A. & Porter, G. D.
Object Type:
Report
System:
The UNT Digital Library
Electron energy and space charge calculations in reflex diodes
Previously reported Monte Carlo code calculations of the electron energy distributions and the consequent reflex triode characteristics will be presented for two different anode designs. In addition, a generalized formulation of Poisson's equation will be used to examine the virtual cathode side of a reflex diode. The familiar ''resonance'' solution for the reflex triode is again found, but with a different physical interpretation. In the former case the current diverges, but in the virtual cathode space the linear dimension diverges as one approaches the ''resonance.''
Date:
May 2, 1977
Creator:
Shearer, J. W.
Object Type:
Article
System:
The UNT Digital Library
Elementary rate constants for hydrogen atoms. Final report, 1974--1975
Personnel, facilities, manuscripts submitted for publication, and manuscripts in preparation are given. No data are provided. (LK)
Date:
January 2, 1977
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Report of the Census Task Force on beamline control system requirements
A special task force was appointed to study the experience with the present beamline control system at Fermilab and to make recommendations in this area. The charge of the committee and the list of its members are appended. In order to carry out its assignment, the committee conducted a series of meetings in which it discussed the controls situation in general and the best way to approach the user community. The various groups of users were identified, and a letter was written to representatives of these groups asking questions concerning the present system and future needs. The committee met with each group to discuss the response to these questions. Written summaries of the discussions are appended. Conclusions are drawn regarding current problems, systematic upgrades and specific recommendations. (LEW)
Date:
October 2, 1986
Creator:
Barsotti, E. J.; Bartlett, J. F.; Bogert, V. D.; Borcherding, F. O.; Butler, J.; Czarapata, P. C. et al.
Object Type:
Report
System:
The UNT Digital Library
Capillary liquid evaporation from wick covered plates: theory
Differential equations and associated parameters are derived for heat transfer to a thin liquid-saturated wick, as in the evaporator section of a ''heat pipe.'' Prescribed are a numerical method of solution and a procedure for experimental measurements of heat transfer in the flat plate model. This effort is a part of the Project CLEER program which is currently sponsored by the Mechanical Engineering Department research account.
Date:
June 2, 1969
Creator:
Van Sant, J. H.
Object Type:
Report
System:
The UNT Digital Library
Tritium-related materials problems in fusion reactors
Pressing materials problems that must be solved before tritium can be used to produce energy economically in fusion reactors are discussed. The following topics are discussed: (1) breeding tritium, (2) recovering bred tritium, (3) containing tritium, (4) fuel recycling, and (5) laser-fusion fueling. (MOW)
Date:
April 2, 1976
Creator:
Hickman, R. G.
Object Type:
Report
System:
The UNT Digital Library
Transaction oriented minicomputer allows flexible design of the controlled materials information system
The design of business data processing applications utilizing minicomputers requires special considerations throughout the development of the systems project. Minicomputer features, capabilities, and limitations must be closely examined prior to the implementation of the design phase. The design requirements of an inventory control minicomputer system currently being installed by the Data Processing Services Department of Lawrence Livermore Laboratory are presented.
Date:
April 2, 1976
Creator:
Jessen, T. D.
Object Type:
Article
System:
The UNT Digital Library
Development of high-creep-strength molybdenum and tungsten alloys by the internal nitriding process
Substantial increases in the high-temperature creep strength of Mo-Hf alloys can be obtained by internal nitriding. The creep resistance of internally nitrided Mo-1.86 wt % Hf is more than 100 times greater than that of other commercially available molybdenum-base alloys. The HfN precipitates appear to be stable over long times at temperatures near 1600 K. Internally nitrided Mo-Hf alloys appear to be good candidates for fabrication of components of space power systems where the ratio of high-temperature strength to weight is important. They are particularly good candidates for components that can be fabricated from the lower-strength unnitrided alloy and subsequently nitrided to provide high-temperature strength.
Date:
October 2, 1986
Creator:
Mitchell, J. B.
Object Type:
Article
System:
The UNT Digital Library
A computational model for coal transport and combustion
In the period of March 1, 1992 to May 30, 1992 considerable progress has been made in the development of the stress transport model for rapid granular flows in a rotating frame of reference. The derivation of thermodynamically consistent constitutive equations were complete. It was shown that the model contains the existing kinetics theories as special limiting cases. The model predictions for the special case of rapid simple shear flows were evaluated and the results are compared with the simulation data. Progress also has been made in formulation of the thermodynamically consistent rate dependent model for turbulent two-phase flows. The thermodynamically admissible constitutive equations were derived, and the case of a simple shear flow was also studied. The kinetic model for rapid flows of granular materials, which includes frictional losses, was used and the special case of gravity flows down an inclined chute was studied. The computational modeling for rapid granular flows in complex geometries was further developed. The design for the experimental simple shear flow device was further improved, and the construction of the device has started.
Date:
June 2, 1992
Creator:
Ahmadi, G.
Object Type:
Report
System:
The UNT Digital Library
Survey of supression of sodium fires in liquid metal fast breeder reactors
A survey was made of protection and suppression technologies relative to liquid sodium fires at selected sites. These technologies will find application in the Liquid Metal Fast Breeder Reactor (LMFBR) program. Based on this survey, a series of conclusions and recommendations are given. Dry type powder agents will only be of use of relatively small sodium fires. Large fires will be extinguished by inerting the chamber or collecting pans where the sodium leak occurs. Liquid sodium fire suppression methods must be incorporated into the initial design of an LMFBR. There exists a need for close coordination of liquid sodium fire technology and guidelines for fire fighting personnel. Suggestions are made for a number of technical development programs. An extensive search for new suppression agents is not recommended although carbon microspheres should be submitted for approval.
Date:
June 2, 1976
Creator:
Hemstreet, R. A.
Object Type:
Report
System:
The UNT Digital Library
An estimation of tritium inventory limits for the E-Area vaults
At the request of Waste Management, Interim Waste Technology has conducted a modeling study to estimate the tritium inventory limits for the E-Area vaults. These inventory limits are based on the groundwater impact of the planned waste disposal. The tritium inventory limit for an Intermediate Level Tritium Vault (ILTV) is estimated to be 400,000 Curies with a 100 year storage period. During this period, it is assumed that the ILTV will be vented, any leachate will be extracted, and its performance will be carefully monitored. The tritium inventory limits for a Low Activity Waste Vault (LAWV) and an Intermediate Level Non-Tritium Vault (ILNTV) are estimated to be 15,000 and 11,000 Curies, respectively. Venting and leachate extraction were not assumed necessary. These operational alternatives would further enhance the performance of these vaults. These limits are significantly higher than the forecasted maximum tritium inventories for the vaults. Details of the modeling study are described in the attached report.
Date:
December 2, 1991
Creator:
Yu, A. D. & Cook, J. R.
Object Type:
Report
System:
The UNT Digital Library
Monte Carlo model for a thick target T(D,n)/sup 4/ He neutron source
A brief description is given of a calculational model developed to simulate a T(D,n)/sup 4/ He neutron source which is anisotropic in energy and intensity. The model also provides a means for including the time dependency of the neutron source. Although the model has been applied specifically to the Lawrence Livermore Laboratory ICT accelerator, the technique is general and can be applied to any similar neutron source.
Date:
August 2, 1976
Creator:
Webster, W. M.
Object Type:
Report
System:
The UNT Digital Library
Floating substrate process. First quarterly progress report, January 6, 1976--March 28, 1976
Laboratory apparatus has been designed, built, and put into operation to study the supercooling of Sn--Si melts and the uptake of silicon from silanes. Values of supercooling of Sn--Si melts as high as 78/sup 0/C at 1100/sup 0/C and 39/sup 0/C at 1200/sup 0/C have been observed. Results to date have been limited by nucleation caused by foreign material floating on the surface of the melt. Spontaneously nucleated planar platelet growth has been observed at the Sn--Si supercooled surface having growth rates of approximately 0.5 cm/min. Homogeneous nucleation of silane decomposition has been studied at 1015/sup 0/C and 1135/sup 0/C. The flow rates of HCl required to suppress gas phase decomposition have been determined for silane flow rates up to 4.5 x 10/sup -3/ mole/min. Initial silicon uptake experiments have shown that at least 20 percent of the incoming silicon contained in a flowing silane gas stream can be incorporated into liquid tin at 1040/sup 0/C.
Date:
April 2, 1976
Creator:
Garfinkel, M. & Hall, R. N.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of the solar building, Albuquerque, NM. Annual progress report, March 31, 1976--April 30, 1977
Data validation procedures and correlations are detailed as well as system performance results. The latter includes solar collection, heat pump performance, tank temperature stratification, building infiltration and system heating output/building energy requirements. The procedure to computer model the Solar Building and correlate the model with field collected data is described.
Date:
May 2, 1977
Creator:
Gilman, S. F.
Object Type:
Report
System:
The UNT Digital Library
Mica fission detectors
The present development status of the mica fission detectors is summarized. It is concluded that the techniques have been refined and developed to a state such that the mica fission counters are a reliable and reproducible detector for fission events.
Date:
June 2, 1977
Creator:
Wong, C.; Anderson, J. D.; Hansen, L.; Lehn, A. V. & Williamson, M. A.
Object Type:
Report
System:
The UNT Digital Library
Permian Basin as a radioactive waste repository
The Permian Basin comprises portions of many structural basins in which halite was deposited close together aerially during the Permian Period of time. It contains at least five areas where salt beds within a formation cumulatively total greater than 200 feet, and are overlain by between 1,000 and 5,000 feet of strata: the Colorado-Kansas, Kansas, Oklahoma-Texas, Clovis and Carlsbad areas. A few other areas within the Permian Basin may contain salt beds collectively greater than 200 feet thick. The Carlsbad area contains a great thickness of salt and covers a very large area. For the Clovis and Oklahoma-Texas areas there is little data available for the Texas portions. The Kansas area has the only halite mines with rooms comparable to those of the proposed waste repository facility. There is little data available for the Colorado-Kansas area, especially for the Colorado portion. The Permian Basin major tectonic elements were formed before deposition of Permian salt beds, and only minor igneous activity and possible fault movement is along the periphery. The greatest seismic activity is associated with the Nemaha Ridge along the northeast side of the Permian Basin, and there is no proven movement, only a suggestion of movement in the form …
Date:
November 2, 1975
Creator:
Smith, J. W.
Object Type:
Report
System:
The UNT Digital Library
User's guide to the LLL basic interpretere
Scientists are finding increased applications for microprocessors as process controllers in their experiments. However, while microprocessors are small and inexpensive, they are difficult to program in machine or assembly language. A high-level language is needed to enable scientists to develop their own microprocessor programs for their experiments on location. Recognizing this need, LLL contracted to have such a language developed. This report describes the result -- the LLL BASIC interpreter. 1 figure, 4 tables.
Date:
April 2, 1976
Creator:
Eckard, R. & Barber, J.
Object Type:
Report
System:
The UNT Digital Library
Annotated bibliography of safety-related occurrences in boiling-water nuclear power plants as reported in 1976
This bibliography contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at boiling-water reactor nuclear power plants in 1976. The report includes 1,253 abstracts that describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. They are arranged alphabetically by reactor name and then chronologically for each reactor. Key-word and permuted-title indexes are provided to facilitate location of the subjects of interest, and tables that summarize the information contained in the bibliography are provided. The information listed in the tables includes instrument failures, equipment failures, system failures, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction). Three of the unique events that occurred during the year are reviewed in detail.
Date:
August 2, 1977
Creator:
Scott, R. L. & Gallaher, R. B.
Object Type:
Report
System:
The UNT Digital Library
Estimation of the solubility of 1,3,5-triamino-2,4,6-trinitrobenzene (TATB) in various solvents
A simple method for estimating the solubility of TATB in various solvents is presented. It is considered unlikely that a solvent will be found in which TATB is more soluble than 0.1 percent (w/v). Exceptions are the so-called superacids in which the solubility of TATB exceeds 20 percent (w/v).
Date:
March 2, 1977
Creator:
Selig, Walter
Object Type:
Report
System:
The UNT Digital Library
Proposed safety standards for ERDA trailers and other portable structures
Topics discussed include body and frame design and construction requirements, planning cnsiderations, thermal protection, heating and cooling systems, plumbing, electrical systems, fire safety, industrial safety and hygiene, identification of portable structures, and testing. (TFD)
Date:
May 2, 1977
Creator:
Lipska, A. E. & Welton, L. G.
Object Type:
Report
System:
The UNT Digital Library
Resonance self-shielding calculations using the probability table method
Resonance self-shielding calculations are presented for fissile material (U-235) and iron using the Probability-Table-Method in a Monte Carlo code.
Date:
August 2, 1976
Creator:
Plechaty, E. F. & Cullen, D. E.
Object Type:
Report
System:
The UNT Digital Library
Alternate fuel cycle technologies, nitrate-to-oxide conversion project. Progress report, January--June 1977
Work is being done at the Rocky Flats Plant (RFP) under contract from the Savannah River Operations Office (SROO) of the U.S. Energy Research and Development Administration (ERDA) to critically analyze and evaluate existing technology for converting plutonium nitrate to plutonium oxide, and to recommend flow sheets and equipment for this process. Seven such processes were compared using an expanded process-comparison scheme. The results of the comparison differed somewhat from the initial comparison made in September, 1976. The direct calcination methods, headed by the screw calciner process, received the highest ratings when operating experience was considered with a small weighting factor. These methods are much simpler than the others. The oxalate precipitation methods, headed by the plutonium(IV) oxalate precipitation and calcination process, received highest ratings when operating experience was strongly considered. Thus, in the long term, the screw calciner or other direct-conversion methods should be developed. For a plant to be built in the short term, however, an oxalate precipitation method should be used since a larger amount of experience exists with these processes. The block flow diagrams, material balances, and equipment flow sheets for each of the seven processes compared are included in this report. A process-design criterion is …
Date:
September 2, 1977
Creator:
Lehmkuhl, G. D.
Object Type:
Report
System:
The UNT Digital Library
LPTR irradiation of LLL metglas samples
Irradiation of MetGlas samples in position E-1 of the reactor core is described. Data are tabulated on neutron energy and flux, and irradiation time. Data are also included on a specimen of 304 stainless steel cut from the irradiation assembly liner to be used for dosimetry. (JRD)
Date:
June 2, 1976
Creator:
MacLean, S. C. & Rowe, C. L.
Object Type:
Report
System:
The UNT Digital Library