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Additions to generating capacity 1978--1987 for the contiguous United States: as projected by the Regional Electric Reliability Councils in their April 1, 1978 long-range coordinated planning reports to the Department of Energy
Comparison of the 1978 projections of the Reliability Councils with those made the previous year indicates three major changes in electric utility planning: (1) a reduction in total capacity additions for the 10-year planning period, (2) a significant decrease in nuclear additions, and (3) a shift from oil and gas to coal as a source of primary energy. Nuclear capacity continues to far overshadow fossil-fuel capacity in the unit-size range 1000 MW and up, with the reverse true for unit sizes less than 1000 MW. Although the total 10-year new-unit capacity drops from 326,624 MW (1977 to 1986) to 308,017 (1978 to 1987), new capacity planned that would use coal as a primary energy source increases from 136,763 MW to 146,206 MW. Nuclear capacity, in terms of total new units projected for the two 10-year periods, decreases from 130,532 MW to 116,177 MW, and capacity with oil as the primary source drops from 32,837 MW to 21,072 MW. For 1977 to 1986, no capacity was planned with oil as a primary source and coal as an alternate fuel but for 1978 to 1987, 1220 MW of such capacity is projected. Therefore, the total new capacity projected that could use coal …
Date:
September 15, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Final report on Process Test MR-105-2, Orifice selection during reactor operation
The test established that a practical orifice selecting device can be made and used to control the water flow rate to a process tube at either of two accurately calibrated rates with no loss of accuracy in flow measurement. With the selector tested, there was no flow restriction during the orifice transition. The pressure fluctuations during the change were small in magnitude, and caused no operational problem. The test demonstrated that orifice selection is feasible from operating other factors justify their use.
Date:
September 15, 1952
Creator:
Schilling, R. D.
Object Type:
Report
System:
The UNT Digital Library
Reliability and safety of the electrical power supply complex of the Hanford production reactors
Safety has been and must continue to be the inviolable modulus by which the operation of a nuclear reactor must be judged. A malfunction in any reactor may well result in a release of fission products which may dissipate over a wide geographical area. Such dissipation may place the health, happiness and even the lives of the people in the region in serious jeopardy. As a result, the property damage and liability cost may reach astronomical values in the order of magnitude of billions of dollars. Reliability of the electrical network is an indispensable factor in attaining a high order of safety assurance. Progress in the peaceful use of atomic energy may take the form of electrical power generation using the nuclear reactor as a source of thermal energy. In view of these factors it seems appropriate and profitable that a critical engineering study be made of the safety and reliability of the Hanford reactors without regard to cost economics. This individual and independent technical engineering analysis was made without regard to Hanford traditional engineering and administration assignments. The main objective has been to focus attention on areas which seem to merit further detailed study on conditions which seem to …
Date:
September 15, 1960
Creator:
Robbins, F. D.
Object Type:
Report
System:
The UNT Digital Library
LDUA engineering development plan
This document provides guidance to perform Light Duty Utility Arm (LDUA) development work and documentation required to validate the design of the LDUA System.The LDUA system will be used to deploy various types of sensors and devices to demonstrate the technology and qualify the integrated systems for operational use in the Hanford single shell tanks to characterize the waste inside and assess tank integrity.
Date:
September 15, 1994
Creator:
Engstrom, J. W.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories Operation monthly activities report, August 1960
This document details activities of the Hanford Laboratories Operation for the month of August 1960.
Date:
September 15, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Effects of crack geometry and material behavior on scattering by cracks for QNDE applications. Technical progress report, March 1, 1988--August 30, 1989
In work carried out on this project, the usual mathematical modeling of ultrasonic wave scattering by flaws is being extended to account for several typical characteristics of fatigue and stress-corrosion cracks, and the environment of such cracks. Work has been completed on scattering by macrocrack-microcrack configurations. We have also investigated reflection and transmission by a flaw plane consisting of an infinite array of randomly oriented cracks. In another investigation the propagation of mechanical disturbances in solids with periodically distributed cracks has been studied.
Date:
September 15, 1989
Creator:
Achenbach, J. D.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories monthly activities report, August 1964
The monthly report for the Hanford Laboratories Operation, August 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operations are discussed.
Date:
September 15, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A Purex process two cycle plant study
Major additions to separations facilities may be required because of increased reactor power levels, reduced exposures; changes in slug specifications, obsolescence of existing solvent extraction plants or development of new separations processes with lower operating costs. The magnitude of first costs for a separations plant is so large as to discourage production planning which would require an additional major separations facility. Experience in separations design has shown that certain process and equipment changes, if they could be developed, would significantly reduce the capital investment in a separations facility. Accordingly design development for a new separations facility is under way. The purposes of this document are to present the results of the first separation design study directed toward a new solvent extraction plant and to summarize process, plant, and equipment changes which should be developed to achieve significant capital and operating cost reduction.
Date:
September 15, 1955
Creator:
Fecht, J. B.; Jaske, R. T.; Lane, T. V. & Ludlow, J. O.
Object Type:
Report
System:
The UNT Digital Library
Manufacturing Section semiannual summary report, period ending June 30, 1967
In this fourth semiannual issue, the reactor and power data from the Hanford Production Reactors are shown for the six-month period January through June, 1967, together with data for the three preceding six-month periods. For comparison purposes, the two years of experience will continue to be shown by dropping and adding a six- month period with each semiannual issue.
Date:
September 15, 1967
Creator:
DeNeal, D. L.
Object Type:
Report
System:
The UNT Digital Library
Transport properties of multi-component fluids and of suspensions. Annual progress report, June 15, 1988--June 14, 1989
This report describes work performed under grant No. DE-FG03-88ER13911 for the period June 15, 1988 through June 14, 1989. During this time, significant progress was made in the derivation of the fundamental equations describing suspensions and multicomponent fluid flow. We first considered a system consisting of spherical heavy (Brownian) particles immersed in a bath of spherical particles. The deviations of the bath from equilibrium are due to the nonequilibrium motions of the Brownian particles. The densities of the bath and of a Brownian particle are similar. An expansion in powers of the mass ratio, yields a Fokker-Planck equation for the distribution function of the Brownian particles, including the effects of direct and hydrodynamic interactions amongst these particles. The effect of the Brownian particle motion on the bath properties has been described. The conditions under which a closed equation for the coordinate space distribution function, can be obtained have been investigated and a Smoluchowski equation for this quantity has been derived.
Date:
September 15, 1989
Creator:
Oppenheim, I. & McBride, J.
Object Type:
Report
System:
The UNT Digital Library
Methane fluxes from rice fields in China: Spatial and temporal variability and estimates of contributions to the global budget. Progress report
During the last year we have made considerable progress on determining the emission rate of methane from rice fields in China and the factors that control the emissions. We have completed work on the methane emissions f rom rice fields for a period of four years at Tu Zu near Chengdu in Szchuan province in China. The available data is being entered into the computer. Flux calculations will be available within 2 months. The fluxes of methane from the rice fields and ambient methane concentrations near the fields are provided including temperature cloud cover, wind speeds, water level, planing density, fertilizer application, pests, ad diseases, growth rate, rice type, soil type, microbial ecology, root exchange exudates, and pH. for the 4-year period. The analysis of the data show that there are a number of internal and external variables that affect the emissions of methane from rice fields.
Date:
September 15, 1992
Creator:
Khalil, M. A. K.; Rasmussen, R. A. & Huntzicker, J. J.
Object Type:
Report
System:
The UNT Digital Library
Achievements in HAPO radiation monitoring, 1944--1954
At HAPO the protection of employees from nuclear radiations has paralleled or preceded the emphasis on atomic products production. The production of atomic products on the scale for which HAPO was designed presented voluminous problems in employee education, radiation detection, shielding, and indeed, fundamental research to determine working limits for the various types of radiation exposure which would necessarily be encountered, and to determine working limits for the deposition of radioactive isotopes and mixtures of isotopes in the human body. Since the time radioactive materials first arrived at HAPO and the start-up of the first HAPO reactor on February 23, 1944, there has been a fundamental philosophy that all employee exposure to nuclear radiations should be maintained at a minimum, as opposed to just some level of exposure below the accepted permissible limit. It was with this philosophy in mind that the many achievements and advances in the science of radiation protection at HAPO have been forthcoming. These advances in radiation protection ar discussed in this report.
Date:
September 15, 1954
Creator:
Unruh, C. M.; Selby, J. M. & Sanders, F. H.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories Operation monthly activities report, August 1961
This is the monthly report for the Hanford Laboratories Operation August 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.
Date:
September 15, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Operational fueling incentives cursory estimate
Equipment Development is testing a system of operational fueling at 105-KE. This cursory review is made for assurance that the program continues to merit risk of small production loss and development priority. Production Test IP-429-K, which is now circulating for approvals and which provides for up to 150 tubes fitted for operational fueling, is an indication of the immediacy with which, presuming due diligence and barring unforeseen circumstances, the system can be available for production.
Date:
September 15, 1961
Creator:
Wood, E. C.
Object Type:
Report
System:
The UNT Digital Library
Vertical bowing measurements: B Reactor, tube 1575
None
Date:
September 15, 1965
Creator:
DeMers, A. E.
Object Type:
Report
System:
The UNT Digital Library
Results of tests investigating panellit protection to ``C`` and ``K`` process tubes without rear pigtail
None
Date:
September 15, 1959
Creator:
Cremer, B. R.; Fitzsimmons, D. E. & Hesson, G. M.
Object Type:
Report
System:
The UNT Digital Library
Effects of irradiation on intergranular stress corrosion cracking of Type 304 stainless steel
Constant extension rate tests (CERT) were run on ten irradiated specimens in continuation of a study of environmental effects on intergranular stress corrosion cracking of type 304 stainless steel. Specimens of both furnace sensitized and annealed material were irradiated to fluences of 1 to 2 {times} 10{sup 21} neutrons (E {ge} 0.1 Mev) per square centimeter at a temperature of {approximately}150{degree}C in a reflector position of the High Flux Isoptope Reactor at ORNL. CERT test conditions duplicated conditions for testing of non-irradiated specimens. The time-to-failure for the sensitized and irradiated specimens showed the same pattern of dependence on test variables as the non-irradiated specimens in an associated study. The annealed and irradiated specimens showed no evidence of irradiation assisted stress corrosion cracking.
Date:
September 15, 1989
Creator:
Caskey, G. R.; Ondrejcin, R. S.; Aldred, P.; Davis, R. B. & Wilson, S. A.
Object Type:
Article
System:
The UNT Digital Library
LIMB Demonstration Project Extension. Quarterly report no. 5, May, June and July 1988
The basic goal of the Limestone Injection Multistage Burner (LIMB) demonstration is to extend LIMB technology development to a full-scale application on a representative wall-fired utility boiler. The successful retrofit of LIMB to an existing boiler is expected to demonstrate that (a) reductions of 50 percent or greater in SO and NO emissions can be achieved at a fraction of the cost of add-on FGD systems, (b) boiler reliability, operability, and steam production can be maintained at levels existing prior to LIMB retrofit, and (c) technical difficulties attributable to LIMB operation, such as additional slagging and fouling, changes in ash disposal requirements, and an increased particulate load, can be resolved in a cost-effective manner. The primary fuel to be used will be an Ohio bituminous coal having a nominal sulfur content of 3 percent or greater.
Date:
September 15, 1988
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Fabrication of hot die sized diffusion bonded fuel elements from oil and water quenched cores for production test IP-708-A
The hot die sizing (HDS) process is being considered as a replacement for the existing AlSi brazing process. Fuel cores are clad by passing a preheated core-component assembly through a die to bond the outside surface. Concurrently, the assembly is passed over a die plug to bond the internal surface. End bonding is accomplished in a following step by applying heat and pressure to the sized fuel element. Remaining fabrication steps are essentially the same as those used for AlSi brazed fuel. Initial irradiation tests indicated that hot die sized fuels experienced in-reactor growth behavior which differed from that of the matched AlSi fuels in the tests. Presently, two tests are being irradiated in the reactor for determining the effect of end-bonding method, and end-bonding pressure in combination with fuel core geometry, upon fuel element diametral growth during irradiation. Due to the length of time required for irradiation and examination, a third test to determine the effect of core heat treatment and stress relieving has been prepared and is ready for reactor charging. This report summarizes the fabrication of oil and water-quenched cores pretreated by both alpha annealing and AlSi brazing for {open_quotes}Production Test IP-708-A, Evaluation of Oil Quenched Hot …
Date:
September 15, 1964
Creator:
Strand, C. A.
Object Type:
Report
System:
The UNT Digital Library
Effects of fuel element heat capacity on reactor outlet temperatures following flow reduction or power surges
The purpose of this report is to present a semi-quantitative discussion of the effect of the heat capacity of the process tube assembly on the outlet water temperature following a mild inadequate cooling incident involving an entire reactor.
Date:
September 15, 1959
Creator:
Hesson, G. M. & Moulton, R. W.
Object Type:
Report
System:
The UNT Digital Library
Molecular biological enhancement of coal biodesulfurization. First quarterly technical progress report
The objective of this project is to produce one or more microorganisms capable of removing the organic and inorganic sulfur in coal. The original specific technical objectives of the project were to: Clone and characterize the genes encoding the enzymes of the ``4S`` pathway (sulfoxide/sulfone/sulfonate/sulfate) for release of organic sulfur from coal; return multiple copies of genes to the original host to enhance the biodesulfurization activity of that organism; transfer this pathway into a fast-growing chemolithotropic bacterium; conduct a batch-mode optimization/analysis of scale-up variables.
Date:
September 15, 1989
Creator:
Litchfield, J. H.; Palmer, D. T.; Zupancic, T. J. & Conkle, H. N.
Object Type:
Report
System:
The UNT Digital Library
The study of the phase structure of hadronic matter by searching for the deconfined quark-gluon phase transition using 2 TeV {bar p}-p collisions; and by searching for critical phenomena in an exclusive study of multifragmentation using 1 GeV/nucleon heavy ion collisions. Progress report, January 1--December 31, 1993
This report discusses the Fermilab experiment E735 which is dedicated to the search for the quark-gluon plasma from proton-antiproton interactions; multifragmentation using the EOS-TPC; STAR R&D; silicon avalanche diodes as direct time-of-flight detectors; and soft photons at the AGS-E855.
Date:
September 15, 1993
Creator:
Scharenberg, R.; Hirsch, A. & Tincknell, M.
Object Type:
Report
System:
The UNT Digital Library
Development of advanced NO{sub x} control concepts for coal-fired utility boilers. Quarterly technical progress report no. 6, January 1, 1992--March 31, 1992
All three of the CombiNO{sub x} NO{sub x} control technologies were performed simultaneously for the first time. Tests were performed while firing coal as the primary fuel, and natural gas and coal as reburn fuels. The results for the complete CombiNO{sub x} process for coal firing and natural gas reburning are displayed in Figure 3-1. NO/NO{sub x} measurements were taken with the new sample system. The filter and line were cleaned periodically throughout testing to avoid ash build-up; ash has also been shown to convert NO{sub 2} to NO. Reduction due to natural gas reburning was 54% with burnout air injected at a downstream location of approximately 1600{degree}F. Advanced Gas Reburning produced a 79% reduction -- although it is suspected that better reduction would have been possible if injection resolution in the furnace allowed the urea to be injected at a more optimum temperature of 1850{degree}F. The methanol injection step converted 45% of the existing NO to NO{sub 2}, achieving an overall CombiNO{sub x} NO reduction of 89%. The coal reburning CombiNO{sub x} test results are displayed in Figure 3-2. Results are similar to those obtained for natural gas reburning. Reduction due to urea injection was better while reburning with …
Date:
September 15, 1992
Creator:
Evans, A.; Pont, J. N.; England, G. & Seeker, W. R.
Object Type:
Report
System:
The UNT Digital Library
Proceedings of the Japan - U.S. Seminar on HTGR Safety Technology - Helium Technology Volume II
None
Date:
September 15, 1977
Creator:
unknown
Object Type:
Article
System:
The UNT Digital Library