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Comparison of ICEPEL predictions with single elbow flexible piping system experiment
The ICEPEL Code for coupled hydrodynamic-structural response analysis of piping systems is used to analyze an experiment on the response of flexible piping systems to internal pressure pulses. The piping system consisted of two flexible Nickel-200 pipes connected in series through a 90/sup 0/ thick-walled stainless steel elbow. A tailored pressure pulse generated by a calibrated pulse gun is stabilized in a long thick-walled stainless steel pipe leading to the flexible piping system which ended with a heavy blind flange. The analytical results of pressure and circumferential strain histories are discussed and compared against the experimental data obtained by Stanford Research Institute.
Date:
January 1, 1978
Creator:
A-Moneim, M.T. & Chang, Y.W.
Object Type:
Article
System:
The UNT Digital Library
Computer simulation of LMFBR piping systems. [Accident conditions]
Integrity of piping systems is one of the main concerns of the safety issues of Liquid Metal Fast Breeder Reactors (LMFBR). Hypothetical core disruptive accidents (HCDA) and water-sodium interaction are two examples of sources of high pressure pulses that endanger the integrity of the heat transport piping systems of LMFBRs. Although plastic wall deformation attenuates pressure peaks so that only pressures slightly higher than the pipe yield pressure propagate along the system, the interaction of these pulses with the different components of the system, such as elbows, valves, heat exchangers, etc.; and with one another produce a complex system of pressure pulses that cause more plastic deformation and perhaps damage to components. A generalized piping component and a tee branching model are described. An optional tube bundle and interior rigid wall simulation model makes such a generalized component model suited for modelling of valves, reducers, expansions, and heat exchangers. The generalized component and the tee branching junction models are combined with the pipe-elbow loop model so that a more general piping system can be analyzed both hydrodynamically and structurally under the effect of simultaneous pressure pulses.
Date:
January 1, 1977
Creator:
A-Moneim, M.T.; Chang, Y.W. & Fistedis, S.H.
Object Type:
Article
System:
The UNT Digital Library
[Photograph 2012.201.B0136.0086]
Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Tulsa -- Country-western singer Roy Clark will lead a group of entertainers on an 18-concert tour of the Soviet Union."
Date:
October 1, 1975
Creator:
ABC DOT
Object Type:
Photograph
System:
The Gateway to Oklahoma History
Uranium hydrogeochemical and stream sediment reconnaissance in Lincoln and Flathead Counties, northwest Montana
Between mid-May and late June 1976, 3409 water and water-transported sediment samples were collected from 1781 locations spread over an approximate 17000-km/sup 2/ area of northwestern Montana. All of the samples were analyzed for total uranium at the LASL, using standardized procedures and rigorous quality controls, the waters by fluorometry and the sediment (and those waters with greater than 10 ppb uranium) by delayed-neutron counting methods. All of the field collection, treatment, and packaging of the samples was performed following strict LASL specifications. The uranium concentrations measured in the waters range from undetectable (less than 0.2) ppb to 173.6 ppb, but average only 0.66 ppb. The low uranium concentrations in the waters of this area are thought to be due primarily to a general lack of readily soluble uranium and dilution with spring runoff. Those locations which did have abnormally high uranium were examined more closely, and follow-up field examinations are recommended in the vicinity of some of these sites. The uranium content of the sediment samples range from 0.5 ppM to 52.2 ppM and average 4.56 ppM. Sample locations with high and/or anomalous uranium values were examined with respect to the local geology, water chemistry, and other relevant factors. …
Date:
May 1, 1977
Creator:
Aamodt, P. L.
Object Type:
Report
System:
The UNT Digital Library
Hydrogeochemical and stream sediment reconnaissance of the National Uranium Resource Evaluation Program primarily for the Rocky Mountain states of New Mexico, Colorado, Wyoming, and Montana, and the State of Alaska. Semiannual progress report, October 1978-March 1979
During this six-month period, Hydrogeochemical and Stream Sediment Reconnaissance samples were collected by the Los Alamos Scientific Laboratory (LASL) from 623 locations in Colorado for a special study. Additional special studies are planned for nine other areas in the Rocky Mountain states in fiscal year 1979, plus some cleanup reconnaissance sampling in parts of four quadrangles that overlap state borders. Preparations for reconnaissance sampling of the entire North Slope region of Alaska have been made but sampling is contingent upon receiving supplemental funds. Water samples from 6725 locations were analyzed for uranium by fluorometry or delayed-neutron counting (DNC). Water samples from 9390 locations were analyzed by emission spectroscopy for 12 other elements. Sediment samples from 14,414 locations were analyzed for uranium and 31 other elements by combined DNC and neutron activation analysis. Sediment samples from 9876 locations were analyzed for two additional elements by x-ray fluorescence. Nine LASL reconnaissance reports, one pilot study data release, one supplemental multielement data release, a multielement data release for three areas in western Alaska, and one quarterly report were open filed by the Department of Energy, Grand Junction Office during the six-month period. Numerous other reports are in various stages of completion and several …
Date:
July 1, 1979
Creator:
Aamodt, P. L.; Bunker, M. E.; Waterbury, G. R. & Waller, R. A.
Object Type:
Report
System:
The UNT Digital Library
Uranium hydrogeochemical and stream sediment reconnaissance data from the area of the Noatak and portions of the Baird Mountains and Ambler River Quadrangles, Alaska
During August 1976, a total of 876 natural waters and 861 bottom sediments were collected at a nominal density of one location each 23 km/sup 2/ from streams and small lakes throughout the Noatak NTMS quadrangle, the southern two-thirds of the Baird Mountains NTMS quadrangle, and in the southwest corner of the Ambler River NTMS quadrangle. These samples were collected as part of the National Uranium Resource Evaluation program in Alaska being conducted by the Los Alamos Scientific Laboratory (LASL). The field collection and treatment of the samples were performed following strict LASL specifications. Total uranium was measured in the waters by fluorometry and in the sediments by delayed-neutron counting, using stringent quality assurance controls at the LASL. The uranium contents of the waters ranged from below the detection limit of 0.02 parts per billion (ppB) to a high of 8.38 ppB, and the uranium contents of the sediments ranged from a low of 0.3 parts per million (ppM) to a high of 34.0 ppM. In general, the locations of waters containing relatively high uranium contents were found to occur in clusters, and particularly in the headwaters of streams draining the southern slopes of the Baird Mountains. Few sediments contained …
Date:
May 1, 1978
Creator:
Aamodt, Paul L.; Hill, Dwight E. & Sharp, Robert R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Effects of Nonadiabatic Transitions on Invariants of the Motion.
None
Date:
January 1, 1972
Creator:
Aamodt, R. E. & Jaeger, E. F.
Object Type:
Report
System:
The UNT Digital Library
Hydraulic fracture experiments in GT-1 and GT-2
Hydraulic fracturing experiments were conducted in granite rock, at temperatures near 100 and 150/sup 0/C, in two wells 0.785 km (2575 ft) and 1.98 km (6500 ft) deep near Los Alamos, New Mexico. No unusual difficulty was observed in fracturing crystalline rock hydraulically. The apparent surface energy (energy required to create new fracture surface by breaking the rock) was measured as 100 J/m/sup 2/. Orientation of the deeper fracture was measured as N35/sup 0/E (+-5/sup 0/). The fraction of fluid injected into the rock that could be recovered at hydrostatic surface pressure was measured. The efficiency of recovery was as high as 92 percent after the fracture impedance was lowered by ''propping'' the fracture with sand. Permeability of the rock over the face of the fracture was compatible with laboratory measurements (10/sup -7/ to 10/sup -8/ darcys). Downhole pressures required to extend the fractures were about 150 and 340 bars (2175 and 4900 psi), respectively.
Date:
February 1, 1977
Creator:
Aamodt, R. L.
Object Type:
Report
System:
The UNT Digital Library
Anomalous fracture-extension pressure in granitic rocks
Fracture-extension pressures appreciably higher than the least principal earth-stress were observed in hydraulic fractures formed in a pair of 3 km (9600 ft) deep boreholes drilled near the Valles Caldera in northern New Mexico. Pressurization of open wellbores in rock containing preexisting fractures may open these fractures, instead of creating new fractures at right angles to the least principal stress. The pressure necessary to flow into these fractures may be appreciably higher than the least principal stress. Upon sand-propping one such pre-existing fracture, a lower fracture extension pressure was observed. A second fracture in a parallel well-bore 92 m (300 ft) away, at the same depth of 2 km (6500 ft) exhibited the lower fracture extension pressure without propping, but with about 90/sup 0/ difference in fracture direction. Fractures created through perforations at a depth of 3 km (9600 ft) not only exhibited breakdown pressures upon initial pressurization, but sometimes even higher ''breakdown'' pressures upon repressurization. These phenomena may be of interest in the interpretation of earth stress measurements made by hydraulic fracturing.
Date:
January 1, 1978
Creator:
Aamodt, R. L. & Potter, R. M.
Object Type:
Article
System:
The UNT Digital Library
Induction and Growth of Fractures in Hot Rock: Artifical Geothermal Reservoirs.
None
Date:
January 1, 1972
Creator:
Aamodt, R. L. & Smith, M. C.
Object Type:
Report
System:
The UNT Digital Library
Development of cermets for high level radioactive waste fixation
A method for the solidification and fixation of commercial and defense high-level radioactive wastes, namely a cermet process, is currently under development. Chemical and physical processing techniques, as developed up to this time, and the subsequent properties of the resulting cermet bodies are described; unique and advantageous features of the cermet waste form and the conversion process are discussed.
Date:
January 1, 1979
Creator:
Aaron, W S; Quinby, T C & Kobisk, E H
Object Type:
Article
System:
The UNT Digital Library
Cermets for high level waste containment
Cermet materials are currently under investigation as an alternate for the primary containment of high level wastes. The cermet in this study is an iron--nickel base metal matrix containing uniformly dispersed, micron-size fission product oxides, aluminosilicates, and titanates. Cermets possess high thermal conductivity, and typical waste loading of 70 wt % with volume reduction factors of 2 to 200 and low processing volatility losses have been realized. Preliminary leach studies indicate a leach resistance comparable to other candidate waste forms; however, more quantitative data are required. Actual waste studies have begun on NFS Acid Thorex, SRP dried sludge and fresh, unneutralized SRP process wastes.
Date:
January 1, 1978
Creator:
Aaron, W. S.; Quinby, T. C. & Kobisk, E. H.
Object Type:
Article
System:
The UNT Digital Library
Development and characterization of cermet forms for radioactive waste
Cermets designed to isolate high-level wastes in a solid form are a composite consisting of various ceramic phase particles uniformly dispersed in and microencapsulated by an iron-nickel base alloy matrix. The metal matrix provides this waste form with many advantageous features including excellent thermal conductivity and mechanical strength. These cermets are formed by first dissolving the waste in molten urea, precipitating and calcining all the constituents, compacting the calcine, and sintering and reduction to form the final product. The exact formulation of cermets through additions to the waste is designed to fix most of the fission products in stable, leach resistant ceramic phases which are subsequently microencapsulated by an alloy matrix. The alloy matrix, which is derived primarily from the waste itself and includes the reducible fission and activation products from the waste, can be compositionally adjusted through additions to optimize its corrosion resistance under conditions existing in various disposal environments. The processes by which cermets are formed include several new and unique materials preparation options that are being developed to permit engineering scale-up and to be compatible with remote operations. Cermets formed by alternate processing methods are being characterized. Initially, cermet samples were prepared using a laboratory scale, batch …
Date:
January 1, 1979
Creator:
Aaron, W. S.; Quinby, T. C. & Kobisk, E. H.
Object Type:
Article
System:
The UNT Digital Library
Prototype gauge for measuring contour and wall thicknesses of hemispherical parts. [Interferometer]
A prototype gauge (gage) was designed and fabricated using air bearings in a new configuration to provide less error and distortion during inspection of hemispherical parts. No wear occurs on the moving parts during operations and accuracy of alignment is maintained. The gauge will check outside radial distance, inside radial, and outside radial and wall, and inner radial and wall thicknesses of parts. The gauge contains only four moving parts, which increases the measuring accuracy. A horizontal table rotates. A table mounted on the horizontal table at 45/sup 0/ rotates through two transducers. All moving parts are mounted on hydrostatic gas bearings. Laser interferometric, air-bearing gauge heads are used to obtain the required data. Investigation of a hemispherical part is in any desired spiral path from equator to pole. Measurement information is obtained from two laser interferometric transducers using linear air bearings. The transducers use a Spectra Physics Model-120 helium and neon laser. Working range of each transducer is 1.5 inches. The fringe voltage signals are amplified and converted to inches to be displayed on a digital readout. A punched paper tape contains the nominal inside diameter (ID) and outside diameter (OD) information in Binary Coded Decimal form. The tape …
Date:
March 1, 1976
Creator:
Aarts, H. J. & Robertson, J. H.
Object Type:
Report
System:
The UNT Digital Library
TCT hybrid preconceptual blanket design studies
The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal divertor. The blanket concept selected by PPPL consists of a neutron multiplying converter region, containing natural Uranium Molybdenum (U-Mo) slugs followed by a fuel burning blanket region of molten salt containing PuF/sub 3/. PNL analyzed this concept to determine its structural, thermal and hydraulic performance characteristics. An adequate first wall cooling method was determined, utilizing low pressure water in a double wall design. A conceptual layout of the converter region tubes was performed, providing adequate helium cooling and the desired movement of U-Mo slugs. A thermal hydraulic analysis of the power-producing blanket regions indicated that either more helium coolant tubes are needed or the salt must be circulated to obtain adequate heat removal capability.
Date:
January 1, 1978
Creator:
Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al.
Object Type:
Report
System:
The UNT Digital Library
Using field theory in hadron physics
Topics are covered on the connection of field theory and hadron physics. The renormalization group and infrared and ultraviolet limits of field theory, in particular quantum chromodynamics, spontaneous mass generation, color confinement, instantons, and the vacuum state in quantum chromodynamics are treated. 21 references. (JFP)
Date:
March 1, 1978
Creator:
Abarbanel, H.D.I.
Object Type:
Article
System:
The UNT Digital Library
Federal Environmental activities
This report presents the Environmental activities of all units of the federal government except the supreme court and the committees of congress.
Date:
June 1, 1972
Creator:
Abbasi, Susan R.
Object Type:
Report
System:
The UNT Digital Library
Water use alternatives for Navajo energy production
The Navajo have substantial resources of coal and uranium, and water use is certain to accompany development of these resources. A variety of supplies, however, are available--water in storage in Navajo Reservoir, water in existing uses which may be transferred, and groundwater. Furthermore, the quantity of water use varies over a wide range depending on the use of water conservation technologies such as dry coolers and wastewater treatment units. Joint management of energy and water resources requires a basic understanding of the water supply and demand alternatives available to the energy industry. Thus, the uses of water for key energy activities--coal and uranium mining, coal transportation (slurry pipelines), and coal conversion (electricity and synthetic gas production) are reviewed. For those activities for which water conservation is feasible, the technologies and estimate costs ($/af saved) are described. The range of water requirements are then compared to energy and water resource estimates. Finally, alternative (not necessarily exclusive) criteria for energy and water resource management are discussed: a) promote energy activities with the lowest minimum water requirements; b) require industry to use low-quality water resources and the most effective water conservation technology; and c) maximize the economic return on Navajo water resources ($/af …
Date:
January 1, 1979
Creator:
Abbey, D.
Object Type:
Article
System:
The UNT Digital Library
BNL Archive and Dissemination System. [For accessing data files constructed at separate places and times]
The Brookhaven National Laboratory Archive and Dissemination System (BNLADS) is designed to deal with the record keeping associated with archiving and disseminating sequential files through a computer network. This data base management system (DBMS) is implemented in a host language that is a subset of PL/I. The stored sequential files that can be dealt with by the BNLADS must be in character mode (ASCII, BCD, EBCDIC). The accessing of fields is specified by a format description which allows for forward processing of fields only. The structure of a case type statement allows for a data field determining a format sequence from a set of format sequences. A data description language (DDL) was devised to describe the accessing sequence of stored sequential files. A data model definition gives the user a view of the content of each stored sequential file. The DDL requires all field type references to contain the field name, so that the BNLADS can access all stored sequential files by logical field name and can write stored sequential files by stating the logical field name without the necessity of referring to formats. The BNLADS is architected in a stratified form in which the application programs are built on …
Date:
February 1, 1977
Creator:
Abbey, S; Fuchel, K; Heller, J; Lin, K S & Osterer, L
Object Type:
Article
System:
The UNT Digital Library
Rankine cycle energy conversion system design considerations for low and intermediate temperature sensible heat sources. Geothermal, waste heat, and solar thermal conversion
Design considerations are described for energy conversion systems for low and intermediate temperature sensible heat sources such as found in geothermal, waste heat, and solar-thermal applications. It is concluded that the most cost effective designs for the applications studied did not require the most efficient thermodynamic cycle, but that the efficiency of the energy conversion hardware can be a key factor.
Date:
October 1, 1976
Creator:
Abbin, J. P. Jr.
Object Type:
Report
System:
The UNT Digital Library
Imagery from Infrared Scanning of the East and Southwest Rift Zones of Kilauea and the Lower Portion of the Southwest Rift Zone of Mauna Loa, Island of Hawaii
From July 31 through August 4, 1973 night time flights for obtaining infrared imagery along the east and southwest rift zones of Kilauea and the southwest rift zone of Mauna Loa were undertaken on the island of Hawaii. Flights were also made on Hualalai and Kohala volcanoes but because of inconclusive results, they are not included in this report. Ground control stations had been established during daylight hours several days prior to starting the flight program. Students stationed at the ground central points guided the aircraft on predetermined flight paths by the use of directional lights which were visible to the plane's navigator. Results of the infrared scanning program are considered to be very successful. Events leading up to the final imagery on 8 x 10 color prints are discussed. The sum of $23,900 was designated by the NSF to be expended on aerial photogeologic work on the Hawaii Geothermal Project. Infrared scanning was the only aerial technique employed in this phase.
Date:
January 1, 1974
Creator:
Abbott, A. T.
Object Type:
Article
System:
The UNT Digital Library
Fast reactor analytical shielding progress report for July and August 1973. 189a No. 10318, activity No. HN 04 01 01 1
Analytical shielding work performed for the fast reactor program during the months of July and August included calculations for both the FFTF and the Demo plant, computer code development, analyses of TSF experiments, and a cross- section sensitivity study of a TSF experiment. Most of the FFTF studies were aimed at determining the effect of various design changes on the dose rates at the maintenance deck during reactor operation, in particular, the effects of penetrations through the radial cavity shield and the effect of a new design for the head temperature control system shield. Gamma-ray dose rates due to the activated sodium coolant were also calculated for two locations in the system: around one of the branch-arm piping shields and near the entrances of the 28-in. and 16-in. coolant lines into the IHX cell. The main Demo plant study was for the lower axial shield region; another study has been initiated to calculate the Demo stored-fuel power and the ex-vessel detector response. The code development consisted in setting forth a set of specifications for the fourth version of the discrete ordinates code DOT. The TSF experiments that were analyzed were an experiment in which secondary gammaray production in iron-polyethylene configurations …
Date:
November 1, 1973
Creator:
Abbott, L. S.; Childs, R. L.; Engle, W. W. & Maerker, R. E.
Object Type:
Report
System:
The UNT Digital Library
Topics in the QCD phenomenology of deep-inelastic scattering. [Review]
The status of QCD with respect to recent results from deep-inelastic neutrino scattering is described emphasizing the theoretical uncertainties coming from effects of nonleading order in 1/Q/sup 2/ and in ..cap alpha../sub s/. 31 references.
Date:
March 1, 1979
Creator:
Abbott, L.F.
Object Type:
Article
System:
The UNT Digital Library
Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics
A fuel cycle that employs /sup 233/U denatured with /sup 238/U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured /sup 233/U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed. The scope of the R, D and D programs to commercialize these reactors and their associated fuel cycles is also summarized and the resource requirements and economics of denatured /sup 233/U cycles are compared to those of the conventional Pu/U cycle. In addition, several nuclear power systems that employ denatured /sup 233/U fuel and are based on the energy center concept are evaluated.
Date:
December 1, 1979
Creator:
Abbott, L.S.; Bartine, D.E. & Burns, T.J. (eds.)
Object Type:
Report
System:
The UNT Digital Library