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Analysis of Devonian Black Shales in Kentucky for Potential Carbon Dioxide Sequestration and Enhanced Natural Gas Production Quarterly Report
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Safety assessment document for the Dynamic Test Complex B854
A safety assessment was performed to determine if potential accidents at the 854 Complex at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The credible accidents that might have an effect on these facilities or have off-site consequences were considered. These were earthquake, extreme wind (including missiles), lightning, flood, criticality, high explosive (HE) detonation that disperses uranium and beryllium, spontaneous oxidation of plutonium, explosions due to finely divided particles, and a fire. Seismic and extreme wind (including missiles) analyses indicate that the buildings are basically sound. The lightning protection system is in the process of being upgraded to meet AMCR 385-100. These buildings are located high above the dry creek bed so that a flood is improbable. The probability of high explosive detonation involving plutonium is very remote since the radioactive materials are encased and plutonium and HE are not permitted concurrently in the same area at Site 300. (The exception to this policy is that explosive actuating devices are sometimes located in assemblies containing fissile materials. However, an accidental actuation will not affect the safe containment of the plutonium within the assembly.) There is a …
Date:
December 11, 1981
Creator:
Odell, B.N. & Pfeifer, H.E.
Object Type:
Report
System:
The UNT Digital Library
HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 1
Four runs were conducted in the Zirflex-Sulfex headend hot cell equipment. Prototype PWR blanket rods, Zircaloy2 clad UO/sub 2/, irradiated from 159 to 356 Mwd/t and decayed 2 years, were declad in boiling 6 M NH/sub 4/F-l M NH/sub 4/NO/sub 3/, terminating with a F/Zr mol ratio of 7 in the spent decladding solution. Average decladding time was 1.5 hr, leaving end cap residues of about 5 g per pin. At the end of the decladding, maximum loss of uranium and plutonium to the decladding solution was 0.04 and 0.37%, respectively. The core pellets were largely shattered with less than 0.5 wt% smaller than 10 mesh. Core dissolution was complete in 5 M HNO/sub 3/ in about 40 minutes, yielding a solvent extraction feed containing 4 M HNO/sub 3/ and 100 g U/l. Solid residue from the decladding and core dissolution was less than 0.001% of the initial weight and consisted of traces of Ca, Fe, Cr, and Sn; uranium and plutonium were not detected. (auth)
Date:
January 11, 1962
Creator:
Goode, J.H. & Baillie, M.G.
Object Type:
Report
System:
The UNT Digital Library
Surge-damping vacuum valve
A valve for damping out flow surges in a vacuum system is described. The surge-damping mechanism consists of a slotted, spring-loaded disk adjacent to the valve's vacuum port (the flow passage to the vacuum roughing pump). Under flow surge conditions, the differential pressure forces the disk into a sealing engagement with the vacuum port, thereby restricting the gas flow path to narrow slots in the disk's periphery. The increased flow damps out the flow surge. When pressure is equalized on both sides of the valve, the spring load moves the disk away from the port to restore full flow conductance through the valve.
Date:
October 11, 1977
Creator:
Bullock, J.C. & Kelley, B.E.
Object Type:
Report
System:
The UNT Digital Library
Laser-damage thresholds of thin-film optical coatings at 248 nm
We have measured the laser-induced damage thresholds for 248 nm wavelength light of over 100 optical coatings from commercial vendors and research institutions. All samples were irradiated once per damage site with temporally multi-lobed, 20-ns pulses generated by a KrF laser. The survey included high, partial, and dichroic reflectors, anti-reflective coatings, and single layer films. The samples were supplied by ten vendors. The majority of samples tested were high reflectors and antireflective coatings. The highest damage thresholds were 8.5 to 9.4 J/cm/sup 2/, respectively. Although these represent extremes of what has been tested so far, several vendors have produced coatings of both types with thresholds which consistently exceed 6 J/cm/sup 2/. Repeated irradiations of some sites were made on a few samples. These yielded no degradation in threshold, but in fact some improvement in damage resistance. These same samples also exhibited no change in threshold after being retested seven months later.
Date:
December 11, 1981
Creator:
Milam, D.; Rainer, F. & Lowdermilk, W.H.
Object Type:
Article
System:
The UNT Digital Library
Safety Analysis Report for Packaging (SARP) for USA/9506/BLF (DOE-AL)
The Safety Analysis Report for Packaging (SARP) satisfies the request of the U.S. Energy Research and Development Administration for a formal safety analysis of the insulated drum shipping container identified as USA/9506/BLF(DOE-A1). Included are discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. Complete physical and technical descriptions of the packages are presented.
Date:
November 11, 1977
Creator:
Watkins, R. A.; Bertram, R. E.; Blauvelt, R. K.; Griffin, J. F.; Peterson, J. B. & Prosser, D. L.
Object Type:
Report
System:
The UNT Digital Library
Low-exposure tritium radiotoxicity in mammals
Studies of tritium radiotoxicity involving chronic /sup 3/H0H exposures in mammals demonstrate in both mice and monkeys that biological effects can be measured following remarkably low levels of exposure - levels in the range of serious practical interest to radiation protection. These studies demonstrate also that deleterious effects of /sup 3/H beta radiation do not differ significantly from those of gamma radiation at high exposures. In contrast, however, at low exposures tritium is significantly more effective than gamma rays, rad for rad, by a factor approaching 3. This is important for hazard evaluation and radiation protection because knowledge concerning biological effects of chronic low-level radiation exposure has come mainly from gamma-ray data; and predictions based on gamma-ray data will underestimate tritium effects - especially at low exposures - unless the RBE is fully taken into account.
Date:
February 11, 1982
Creator:
Dobson, R.L.
Object Type:
Article
System:
The UNT Digital Library
Defect states in plasma-deposited a-Si:H. Technical progress report, August-October 1979
Raman and ESR measurements were used to study the atomic bonding and defect concentrations. Features are identified in the Raman spectra which can be attributed to configurations containing Si-Si, Si-As and As-As bonds. Features due to all three of these configurations were found to simultaneously exist, thus excluding a chemically ordered model of the bonding. However, the composition dependences of the features do not follow exactly a random bonding model either. The H bonding configurations were reflected in features at approx.2000 cm/sup -1/ in the Raman spectra. It was found that the H bonding changed dramatically in the As doping to 5% As alloying region. The ESR measurements indicated a low level of singly occupied defect states in all the samples studied.
Date:
December 11, 1979
Creator:
Knights, J C
Object Type:
Report
System:
The UNT Digital Library
Effects of oxide layers on optical properties and x-ray hardness of Al-Be mirrors
Oxide layers form on the surfaces of many metallic mirrors. The oxidation may occur during fabrication or after the mirror is finished and installed. Some oxide layers may be intentionally added to protect the mirror or to change its optical properties. Computer calculations predict the effect of oxide layers on optical and ultraviolet reflectance as well as the x-ray absorption and concomitant thermal damage to the mirrors. 6 refs., 6 figs., 1 tab.
Date:
June 11, 1991
Creator:
White, R.H. & Wirtenson, G.R.
Object Type:
Report
System:
The UNT Digital Library
Systematics of neutron-induced fission cross sections over the energy range 0. 1 through 15 MeV, and at 0. 0253 eV
Recent studies have shown straightforward systematic behavior as a function of constant proton and neutron number for neutron-induced fission cross sections of the actinide elements in the incident-neutron energy range 3 to 5 MeV. In this report, the second in a series, fission cross-section values are studied over the MeV incident-neutron energy range, and at 0.0253 eV. Fission-barrier heights and neutron-binding energies are correlated by constant proton and neutron number; however, these systematic behaviors alone do not explain the trends observed in the fission cross-section values.
Date:
November 11, 1977
Creator:
Behrens, J.W.
Object Type:
Report
System:
The UNT Digital Library
Study of corrosion in multimetallic systems. Task 2 of solar collector studies for solar heating and cooling applications. Final technical progress report
Corrosion measurements were made on candidate alloys of construction for non-concentrating solar collectors under simulated conditions of collector operation. Materials evaluated were aluminum alloys 1100, 3003, and 6061, copper alloy 122, Type 444 stainless steel, and 1018 plain carbon steel. The solutions used were equivolume mixtures of ethylene glycol and water, and propylene glycol and water. They were used without corrosion inhibitors but with addition of chloride, sulfate, and bicarbonate ions. The influences of dissolved oxygen, solution flow velocity, and heat transfer were evaluated. Corrosion morphologies investigated were general attack, pitting, crevice corrosion, and galvanic corrosion. Experimental results indicated that aluminum alloys can experience severe pitting and crevice corrosion at chloride concentrations approaching 50 ppM. The corrosion rate of copper exceeded about 100 ..mu..m/yr in ethylene glycol solutions and about 80 ..mu..m/yr in propylene glycol solutions. Crevice corrosion was not observed for copper, but severe galvanic corrosion occurred when it was coupled to T444 stainless steel. T444 steel corroded at rates of less than 1 ..mu..m/yr under all exposure conditions. During circulation at 100 C in the presence of air, ethylene glycol solutions acidified because of degradation of the glycol. The initial pH of propylene glycol solutions was already low, …
Date:
April 11, 1980
Creator:
Diegle, R B
Object Type:
Report
System:
The UNT Digital Library
Dipole aperture and superconductor requirements
The cost of an accelerator is not proportional to the aperture. A change in aperture by a certain percentage results in an overall accelerator cost change by only a fraction of that percentage; the fraction may be between 0.1 and 0.5 and is almost independent of the bending field. This estimate is obtained by analyzing the superconductor requirements as a function of aperture and by making rough estimates of the largest cost items of the accelerator such as magnets and ring tunnel.
Date:
December 11, 1983
Creator:
Wipf, S.L.
Object Type:
Article
System:
The UNT Digital Library
Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report. Appendix C: preliminary design data package. Volume II. Appendices
This appendix to the final report on the Hybrid Passenger Vehicle Development Program contans data on Na-S batteries, Ni-Zn batteries; vehicle body design; tire characteristics; and results of computer simulations of vehicle yaw, pitch, and roll under various driving and aerodynamic conditions. (LCL)
Date:
September 11, 1979
Creator:
Piccolo, R.
Object Type:
Report
System:
The UNT Digital Library
International energy R and D: a picture compiled from open sources
None
Date:
February 11, 1975
Creator:
Green, E.A.
Object Type:
Report
System:
The UNT Digital Library
Writing Parallel, Discrete-Event Simulations in Modsim: Insight and Experience
The Time Warp Operating System (TWOS) has been the focus of much research in parallel simulation. A new language, called ModSim, has been developed for use in conjunction with TWOS. The coupling of ModSim and TWOS provides a tool to construct large, complex simulation models that will run on several parallel and distributed computer systems. As part of the Griffin Project'' underway here at Los Alamos National Laboratory, there is strong interest in assessing the coupling of ModSim and TWOS from an application-oriented perspective. To this end, a key component of the Eagle combat simulation has been implemented in ModSim for execution on TWOS. In this paper brief overviews of ModSim and TWOS will be presented. Finally, the compatibility of the computational models presented by the language and the operating system will be examined in light of experience gained to date. 18 refs., 4 figs.
Date:
September 11, 1989
Creator:
Rich, D.O. & Michelsen, R.E.
Object Type:
Article
System:
The UNT Digital Library
Nitrogen fixation method and apparatus. [DOE patent application]
A method and apparatus for achieving nitrogen fixation includes a volumetric electric discharge chamber. The volumetric discharge chamber provides an even distribution of an electron beam, and enables the chamber to be maintained at a controlled energy to pressure (E/p) ratio. An E/p ratio of from 5 to 15 kV/atm of O/sub 2//cm promotes the formation of vibrationally excited N/sub 2/. Atomic oxygen interacts with vibrationally excited N/sub 2/ at a much quicker rate than unexcited N/sub 2/, greatly improving the rate at which NO is formed.
Date:
August 11, 1981
Creator:
Chen, H. L.
Object Type:
Patent
System:
The UNT Digital Library
REACTOR CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1962
Separate abstracts were prepared for thirty-one of the thirty-three sections. Of the sections not abstracted, the one entitled Fission Product Transport'' contained no information, the other, Transport of Noble Gases in Graphite'' is available in a more complete form as ORNLTM-I35 (NSA 16: 9209) (J.R.D.)
Date:
May 11, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Laboratory Development of the Acid Thorex Process for Recovery of Consolidated Edison Thorium Reactor Fuel
The id Thorex process, in which nitric acid is the salting'' agent in the solvent extraction of Th and U from an acid eficient feed with TBP in Amsco, was demonstrated in laboratory equipment for the recovery of synthetic Co solidated Edison Thorium Reactor fuel containing trace fission products. The acid was removed from solution of the declad fuel pellets to produce an acid deficient feed by steam stripping, and the adjusted feed was treated with bisulfite to decrease the extractability of fission products. The Th and U were extracted with 30% TBP in Amsco, and pregnant organic was scrubbed with dilute nitric acid to improve decontamination. Additional acid was added to the extraction section to increase the distribution oefficient of the Th, The Th and U could then be stripped ther simultaneously or separately. No difficulties were ound with either excessive reflux of acid or <0.3%. The co centrated aqueous waste was about 0.2 liter per kilog am of Th processed, about 1/10 of that from the aluminum n trate-salted process. Engineering studies showed that the stage height in the extraction column with the acid Thorex process was 2.1 ft compared with 4 ft with the aluminum-salted Thorex process. …
Date:
May 11, 1962
Creator:
Rainey, R. H. & Moore, J. G.
Object Type:
Report
System:
The UNT Digital Library
Underground muon observations in the Soudan 2 detector
The Soudan 2 nucleon decay detector has recorded data since Summer 1988 using a quarter (dimensions 4 m by 8 m by 5 m high) of the eventual detector. This iron-argon time projection chamber records extensive data on each event and has excellent angular and multi-track resolution. We describe the trigger, the event analysis procedure and the current status of the detector and the underground muon data sample. 1 ref.
Date:
September 11, 1989
Creator:
Allison, W. W. M.; Barr, G. D.; Brooks, C. B.; Cobb, J. H.; Kirby-Gallagher, L. M.; Giles, R. H. et al.
Object Type:
Article
System:
The UNT Digital Library
Environmental monitoring at the Lawrence Livermore National Laboratory. 1981 annual report
This report gives methods and results of the 1981 radiation monitoring program at LLL for both radioactive and non-radioactive contamination from gaseous and liquid effluents. Off-site monitoring includes various radionuclides but especially tritium in the ecosystems. (PSB)
Date:
March 11, 1982
Creator:
Auyong, M.; Griggs, K.S. & Buddemeier, R.W.
Object Type:
Report
System:
The UNT Digital Library
Mechanical model for ductility loss
A mechanical model was constructed to probe into the mechanism of ductility loss. Fracture criterion based on critical localized deformation was undertaken. Two microstructure variables were considered in the model. Namely, the strength ratio of grain boundary affected area to the matrix, ..cap omega.., and the linear fraction, x, of grain boundary affected area. A parametrical study was carried out. The study shows that the ductility is very sensitive to those microstructure parameters. The functional dependence of ductility to temperature as well as strain-rate, suggested by the model, is demonstrated to be consistent with the observation.
Date:
February 11, 1980
Creator:
Hu, W.L.
Object Type:
Article
System:
The UNT Digital Library
Advanced conversion: C-1-B advanced conversion
None
Date:
November 11, 1974
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
RADIATION EFFECTS IN GRAPHITE
A review of radiation effects on graphite is presented. Included are discussions of the general relations of these effects with original structural properties, and details of radioinduced changes. Other discussions are devoted to stored energy, annealing, and future problems in the use of nuclear graphite. Data and illustrations concerning structure and radioinduced changes are included. (J.R.D.)
Date:
May 11, 1962
Creator:
Nightingale, R.E.
Object Type:
Report
System:
The UNT Digital Library
DIRECTIONS FOR THE FABRICATION OF A PROBE FOR THE MEASUREMENT OF PLATE SPACING IN PLATE-TYPE FUEL ELEMENTS
A probe for measurement of the space between fuel plates in high-burnup MTR-type fuel elements by eddycurrent techniques is described/su The sensing section is supported near the end of a flattened stainless steel tube into which a rectangular hole was cut to receive it/su The sensing section consists essentially of two slightly bowed springs, the midsections of which protrude slightly above the upper and lower surfaces of the flattened tube. Each spring- carries a section of a ball bearing as the contact point/su It is these two slightly bowed springs that serve as expanding calipers sensing variations in the spacing between adjacent plates. Essentially the rest of the probe is a long handle to permit probing and a conduit for the electrical leads. A two-wire shielded cable is firmly attached to the unflattened end of the probe and then attached to a modified Wheatstone bridge, from which the output is fed into a chart recorder. (M.C.G.)
Date:
April 11, 1962
Creator:
Dismuke, S.E.
Object Type:
Report
System:
The UNT Digital Library
Dissolution of Zirconium Reactor Fuels in Titanium Equipment
Continuous dissolution of Zircaloy-2 in a titanium dissolver appears practical using as a dissolvent refluxing 3 M HNO/sub 2/-l.2 M HF--0.4 M HBF/sub 4/-0.6 M Cr(III)-0.4 M Cr(VI)--0.46 M Zr. Dissolution and corrosion rates were 10 mg/cm/sub 2/-min and 0.0 mil/mo in short term tests, respectively. A stable product solution containing 0.36 M Zr was obtained after addition of aluminum nitrate to complex fluoride ion. Another reagent investigated for use in continuous dissolution was 16 M HNO/sub 3/-2.6 M F-0.025 M HBF/sub 4/-1.4 M Zr with short term titanium corrosion rates of 0.0 mil/mo. However, Zircaloy-2 dissolution rates were only 3 mg/cm/sup 2/-min in the latter reagent. (auth)
Date:
October 11, 1961
Creator:
Gens, T.A.
Object Type:
Report
System:
The UNT Digital Library