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THE CALCINATION IN AIR OF BERYLLIUM OXALATE TRIHYDRATE TO BERYLLIUM OXIDE (open access)

THE CALCINATION IN AIR OF BERYLLIUM OXALATE TRIHYDRATE TO BERYLLIUM OXIDE

None
Date: October 19, 1961
Creator: Hamner, R.L. & Harris, L.A.
Object Type: Report
System: The UNT Digital Library
Measurement of Xenon Poisoning in the HRT (open access)

Measurement of Xenon Poisoning in the HRT

Measurements obtained during three periods of HRT operations indicated that the xenon poison fraction was approximately 0.010. The technique used was based on mass spectrographic analyses of the stable xenon isotopes in the reactor off-gas stream. Models proposed to explain the measurements show that xenon, which is formed primarily by decay of iodine adsorbed on the pipe walls, is held up on the walls, out of the circulating stream, for an average period of about eight hours. (auth)
Date: April 19, 1962
Creator: Burch, W.D.
Object Type: Report
System: The UNT Digital Library
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures (open access)

Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures

Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, offer important advantages as high-temperature fuel solutions for nuclear reactors and as media suitable for nuclear fuel processing. Both applications have stimulated experimental and theoretical studies of the corrosion processes by which molten salt mixtures attack potential reactor materials. Corrosion experiments with fluoride salts which were conducted in support of the Molten-Salt Reactor E xperiment and analytical methods employed to interpret corrosion and masstransfer behavior in this reactor system are discussed. The products of corrosion of metals by fluoride melts are soluble in the molten salt; accordingly passivation is precluded and corrosion depends directly on the thermodynamic driving force of the corrosion reactions. Compatibility of the container metal and molten salt, therefore, demands the selection of salt constituents which are not appreciably reduced by useful structural alloys and the development of container materials whose components are in near thermodynamic equilibrium with the salt medium. Utilizing information gained in corrosion testing of commercial alloys and in fundamental interpretations of the corrosion process, an alloy development program was conducted to provide a high temperature container material that combined corrosion resistance with useful mechanical properties. The program …
Date: September 19, 1962
Creator: DeVan, J. H. & Evans, R. B., III
Object Type: Report
System: The UNT Digital Library
Mirror hybrid reactor studies (open access)

Mirror hybrid reactor studies

The hybrid reactor studies are reviewed. The optimization of the point design and work on a reference design are described. The status of the nuclear analysis of fast spectrum blankets, systems studies for fissile fuel producing hybrid reactor, and the mechanical design of the machine are reviewed. (MHR)
Date: January 19, 1978
Creator: Bender, D.J.
Object Type: Article
System: The UNT Digital Library
Marketing of coal mining equipment. Evaluation of present techniques: suggestions to aid commercialization. Final report (open access)

Marketing of coal mining equipment. Evaluation of present techniques: suggestions to aid commercialization. Final report

This report is an examination of the equipment preferences and decision-making methodology of the coal industry. The prime purpose is to indicate directions in which equipment research might proceed and also to indicate methods by which investment in new, more productive mining equipment could be encouraged. In addition to this, an investigation of the research and development decisions of major mining equipment manufacturers was conducted. The findings can best be condensed into three categories: needs for equipment in underground mining, needs for equipment in surface mining, and the purchase decision by coal mine operators.
Date: September 19, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Useful characteristics of the Savannah River (open access)

Useful characteristics of the Savannah River

The following information about the Savannah River is tabulated: significant activities and discharges along the Savannah River, river water temperature data near Jackson st Savannah River Plant, flow informatiom, and reservoir parameters for Clarks Hill, Richard B. Russell and Hartwell reservoirs.
Date: May 19, 1982
Creator: Watts, J. R.
Object Type: Report
System: The UNT Digital Library
Equilibrium water vapor pressure over adhesives and epoxies (open access)

Equilibrium water vapor pressure over adhesives and epoxies

None
Date: May 19, 1975
Creator: Colmenares, C. & McDavid, L.
Object Type: Article
System: The UNT Digital Library
Analytical theory of ion-temperature-gradient instability (open access)

Analytical theory of ion-temperature-gradient instability

The relationship between the threshold values of ion-temperature-gradient instabilities and the temperature parameters of plasmas is investigated analytically in slab and toroidal geometries separately. It is found that the threshold values increase rapidly when the ion temperature becomes much higher than the electron temperature. The change of the threshold vaues with respect to the ion temperature is quite similar for both geometric models. This finding is consistent with PLT observations. Furthermore, the analytical results also agree with those of the numerical calculations.
Date: January 19, 1982
Creator: Guo, S.; Shen, J.; Chen, L. & Tsai, S.T.
Object Type: Report
System: The UNT Digital Library
Spectrophotometric studies of solutions at elevated temperatures and pressures: status and program for FY1961 and part of FY 1962 (open access)

Spectrophotometric studies of solutions at elevated temperatures and pressures: status and program for FY1961 and part of FY 1962

A program was initiated on the spectrophotometric study of aqueous solution chemistry. The goal is operation at temperatures up to at least 330 deg C and at pressures up to 200 atm, and to near the critical point if this appears to be feasible. A spectrometer capable of operation under these extreme conditions is being designed. (W.L.H.)
Date: July 19, 1960
Creator: Biggers, R. E. & Chilton, J. M.
Object Type: Report
System: The UNT Digital Library
MOLTEN-SALT REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM MARCH 1 TO AUGUST 31, 1961 (open access)

MOLTEN-SALT REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM MARCH 1 TO AUGUST 31, 1961

The Molten Salt Reactor Experiment design, component development, and engineering analysis is discussed. Materials studies for the Molten-Salt Reactor Program including metallurgy, in-pile tests, chemistry, engineering research, and fuel processing are described. (M.C.G.)
Date: January 19, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Discussions of Medical Device Issues: A Selected Bibliography (open access)

Discussions of Medical Device Issues: A Selected Bibliography

This report provides a bibliography of resources related to the safety and regulation of medical devices.
Date: June 19, 1970
Creator: Cavalier, Kay
Object Type: Report
System: The UNT Digital Library
Deployment of the Anti-Ballistic Missile (ABM): The Pros and Cons (open access)

Deployment of the Anti-Ballistic Missile (ABM): The Pros and Cons

This report is about the pros an cons of deploying an anti-ballistic missile system (ABM) for defense against missile attack.
Date: April 19, 1967
Creator: Bussey, Donald S.
Object Type: Report
System: The UNT Digital Library
The Negative Income Tax and other Welfare Proposals to Guarantee an Annual Income. (open access)

The Negative Income Tax and other Welfare Proposals to Guarantee an Annual Income.

This report describes the Negative Income Tax and other Welfare Proposals to Guarantee an Annual Income.
Date: June 19, 1967
Creator: Peel, Evelyn
Object Type: Report
System: The UNT Digital Library
Military Justice: A Summary of its Legislative and Judicial Development (open access)

Military Justice: A Summary of its Legislative and Judicial Development

This report discusses the military justice system and legislation and judicial decisions regarding it.
Date: September 19, 1969
Creator: Ujevich, Robert M.
Object Type: Report
System: The UNT Digital Library
Election of the President by the house of Representatives (open access)

Election of the President by the house of Representatives

This report discusses the historical statistics of presidential election, the declaration of the results and other reports.
Date: August 19, 1968
Creator: Government and General Research Division
Object Type: Report
System: The UNT Digital Library
EXTRACTION OF NEPTUNIUM FROM ACIDIC SOLUTIONS BY ORGANIC NITROGEN AND PHOSPHORUS COMPOUNDS (open access)

EXTRACTION OF NEPTUNIUM FROM ACIDIC SOLUTIONS BY ORGANIC NITROGEN AND PHOSPHORUS COMPOUNDS

Neptunium distribution coefficients from acid nitrate, chloride, and sulfate solutions by several organic nitiogen and phosphorus compounds were measured as functions of several extraction variables, including neptunium valence, acid and salt concentration, and reagent concentration. Extractability by all the reagents varied in the order Np(IV)> Np(VI)>> Np(V). Except for primary amines, all reagents extracted Np(IV) much more strongly from nitrate than sulfate solutions. Among organonitrogen compounds the order of extractability of Np(IV) was: quaternary> tertiary> primary and secondary from nitrate solutions but primary>> secondary> tertiary from sulfate solutions. Neptunium(IV) nitrate extractions with the different extractants passed through maxima at widely different acid concentrations. In most cases, extraction increased when nitric acid was replaced by nitrate salt. Extraction was usually approximately proportional to the square of the reagent concentration. (auth)
Date: October 19, 1961
Creator: Weaver, B.
Object Type: Report
System: The UNT Digital Library
RADIOLOGICAL HAZARDS FROM RUPTURE OF THE SECONDARY COOLANT SYSTEM OF THE 10 Mw ESCR (open access)

RADIOLOGICAL HAZARDS FROM RUPTURE OF THE SECONDARY COOLANT SYSTEM OF THE 10 Mw ESCR

The hazards study was made to determine the radiation level from the secondary sodium lines of the l0-Mw ESCR, and to evaluate the corresponding radioactive concentration in the secondary loop and the maximum permissible effective activation flux in the intermediate heat exchanger. The results are presented graphicallyn the radiation level from the coolant lines during normal operation as a function of line diameter and Na/sup 4/ concentration; the effective thermal neutron activation flux level in the intermediate heat exchanger as a function of the Na/sup 4/ concentration in the secondary loop and the ratio of the time spent in the flux field to the time spent in making one cycle; average Na concentration in the reactor room atmosphere for operative and inoperative ventilation systems, assuming that all the sodium in the secondary system is released to the room and burns; and the downwind concentration of Na/ sup 24/ resulting from the release of all the secondary sodium on an open pad area exterior to the reactor building. An analysis of the results shows that in the event of an accident the toxicological hazards are more severe than the radiological hazards. Recommendations are given for minimizing the toxological hazards. (B.O.G.)
Date: January 19, 1960
Creator: Piccot, A.R.
Object Type: Report
System: The UNT Digital Library
Notes on Luminosity Variation at ISABELLE (open access)

Notes on Luminosity Variation at ISABELLE

In the present ISABELLE design, the luminosity at each insertion will be the same, unless special efforts are taken to get a low-..beta.. insertion or reduced crossing angle. These can only change the luminosity by factors of 2 to 4 from insertion to insertion. An estimation of the range of desired luminosities is given.
Date: October 19, 1977
Creator: Herrera, J. C.; Marx, M.; Roe, B. & Rosenberg, E. I.
Object Type: Article
System: The UNT Digital Library
Civilian Power Reactor Program. Part II. Economic Potential and Development Program. Heavy Water-Moderated Power Reactor (open access)

Civilian Power Reactor Program. Part II. Economic Potential and Development Program. Heavy Water-Moderated Power Reactor

The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel development program, and improvements which would result from the successful completion of the development program as presented. One plant size was used in the evaluation of plant potential, with a 300 Mw/sub e/ nominal rating. The boiling D/sub 2/O-cooled, pressure tube direct cycle plant design was used. The current development program is outlined; this work includes several items leading to the long-range development of the concept. (auth)
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Object Type: Report
System: The UNT Digital Library
INSTRUMENTATION AND CONTROLS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JULY 1, 1961 (open access)

INSTRUMENTATION AND CONTROLS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JULY 1, 1961

The report comprises seven sections. A separate abstract was prepared for each section. (J.R.D.)
Date: February 19, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Civilian Power Reactor Program. Part III. Status Report on Large (100 and 300 MWe) Heavy Water-Moderated Power Reactors--as of 1960 (open access)

Civilian Power Reactor Program. Part III. Status Report on Large (100 and 300 MWe) Heavy Water-Moderated Power Reactors--as of 1960

An evaluation of 300- and 100-Mwe power plants was conducted using ground rules prescribed by the USAEC for this study. Costs corresponding to two average discharged fuel burnups are: 8.6 mills/kwh (8500 Mwd/ metric ton) and 8.8 mills/kwh (7500 Mwd/metric ton) for the 300-Mw plant. Costs for the 100 Mw plant are 14.7 mills/kwh for an average discharged fuel burnup of 6010 Mwd/metric ton. Estimates of future potential indicate that the 300 Mw/sub 3/ (8500 Mwd/metric ton) plant could produce power for 7.3 mills/kwh in a second generation, full scale plant of the same type. A further reduction to 6.4 mills/kwh should be possible as the result of the recommended ten-year development program. The current development program is adequate for providing the data needed to design and construct a prototype reactor. However, there is no natural U-fueled prototype and no prototype of the chosen reference design scheduled in the U.S. Current technology is sufficiently developed to initiate the design and construction of a pressure tube, boiling D/sub 2/Ocooled, natural UO/sub 2/- fueled reactor prototype plant in the immediate future. This plant would demonstrate the main features of a full scale plant and, in addition. would provide design data which could …
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Object Type: Report
System: The UNT Digital Library
Low Temperature Thermoluminescence of Gamma Irradiated Potassium Dihydrogen Phosphate (open access)

Low Temperature Thermoluminescence of Gamma Irradiated Potassium Dihydrogen Phosphate

Thermoluminescence in potassium dihydrogen phosphate (KDP) induced by Co/ sup 60/ gamma irradiation at liquid nitrogen temperature (-198 deg C) was investigated. Glow curves in the temperature range --196 to 0 deg C were measured for a series of gamma exposure dosages ranging from 10/sup 4/ roentgen to 5 x 10/sup 6/ roentgen. The heating rate used for glow curve measurements was 12 deg C per minute. Twice recrystallized Mallinckrodt reagent grade potassium dihydrogen phosphate, with a grain size between 100 and 170 mesh, was used for most samples. In the case of the powder samples, the glow curve for an exposure dose of 10/sup 4/ roentgen exhibited two peaks in this temperature range, one at approximately --78 deg C and the other at approximately -146 deg C. The -78 deg C peak split into two distinct peaks with increasing dosage. At still higher doses an additional peak at about -9 deg C became evident. This peak may, however, be due to aluminum oxide. Calculation of the trap depth, E, and the frequency factor, s, associated with the --78 deg C peak, by the approximate method of Grossweiner yielded values of 0.485 ev and 9.97 x 10/sup 10/ sec/sup -1/ …
Date: October 19, 1962
Creator: Sims, T. M.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Establishment and maintenance of a coal sample bank and data base (open access)

Establishment and maintenance of a coal sample bank and data base

During the current reporting period a total of 139 samples (46 DOE Sample Bank samples and 93 other Penn State samples) of various sizes were distributed. Sixty-three of the samples were distributed to DOE or its contractors; 76 were distributed to other agencies. A total of 88 data printouts were distributed. In addition, seven special data requests were fulfilled by either search/sort and printout or creation of a data disk. Several preliminary requests for Sample Bank and Data Base information have also been handled.
Date: April 19, 1989
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Determination of chloride contamination on detonator components by SAM and ESCA (open access)

Determination of chloride contamination on detonator components by SAM and ESCA

None
Date: May 19, 1975
Creator: Colmenares, C.
Object Type: Article
System: The UNT Digital Library