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Investigation of cooling coil corrosion in storage tanks for radioactive waste (open access)

Investigation of cooling coil corrosion in storage tanks for radioactive waste

The high frequency of cooling coil leaks observed in high-heat waste storage tanks soon after sludge removal operations is attributed to pitting, according to laboratory corrosion studies. Experiments show that the most likely series of events leading to coil leakage is (1) excessive dilution of basic nitrite in the supernate, (2) initiation of attack in crevices due to oxygen depletion cells, and (3) acceleration of the attack by sulfate dissolved from the sludge. When sludge was slurried with water, the interstitial liquid was diluted. Nitrite, the anodic inhibitor that prevented attack on coils and tanks in normal operation when its concentration was 0.5 to 3.0M, could accelerate attack when diluted to 10/sup -4/ to 10/sup -3/M. Attack was presumably initiated at oxygen depletion cells. The presence of sulfate, leached from the sludge, produced a conductive solution that could produce high current densities at the corroding steel surface. The proposed series of events leading to coil leakage agrees with the observations previously made on one leaking coil removed from Tank 2F after sludge removal in 1967. Examination revealed pitting that had originated on the outside of the coils. This pitting was attributed to oxygen depletion cells in coil crevices. To prevent …
Date: January 1, 1978
Creator: Ondrejcin, R.S.
Object Type: Article
System: The UNT Digital Library
Impacts of the national energy programme on solar economics (open access)

Impacts of the national energy programme on solar economics

The National Energy Plan (NEP) sets as a goal the use of solar energy in two and a half million homes in 1985. A key provision of the NEP (as well as congressional alternatives) provides for the subsidization of solar equipment. The extent to which these subsidies (income tax credits) might offset the impact of continued energy-price control is examined. Regional prices and availability of conventional energy sources (oil, gas, and electricity) were compiled to obtain a current and consistent set of energy prices by state and energy type. These prices are converted into equivalent terms ($/10/sup 6/ Btu) that account for combustion and heat-generation efficiencies. Projections of conventional-fuel price increases (or decreases) are made under both the NEP scenario and a projected scenario where all wellhead price controls are removed on natural gas and crude oil production. The economic feasibility (life-cycle cost basis) of solar energy for residential space heating and domestic hot water is examined on a state-by-state basis. Solar-system costs are developed for each state by fraction of Btu heating load provided. The total number of homes, projected energy savings, and sensitivity to heating loads, alternative energy costs, and prices are included in the analysis.
Date: January 1, 1978
Creator: Ben-David, S.; Noll, S.; Roach, F. & Schulze, W.
Object Type: Article
System: The UNT Digital Library
Measurement program to characterize the wind at a potential WECS site (open access)

Measurement program to characterize the wind at a potential WECS site

An onsite meteorological measurement program to characterize the wind at a potential wind turbine installation site is described. The basic informational requirements have been postulated, the analysis described, and an appropriate measurement program has been devised. This phase of siting measurements provides the information for the final installation decision process--which WECS to put at which site.
Date: March 1, 1978
Creator: Verholek, M.G.
Object Type: Report
System: The UNT Digital Library
Radioactive waste transportation systems analysis and program plan (open access)

Radioactive waste transportation systems analysis and program plan

The objective of the Transportation/Logistics Study is to ensure the availability of a viable system for transporting the wastes to a federal repository in 1985. In order to accomplish this objective, a systems analysis of waste transportation has been directed by ORNL to determine the problems that must be solved and to develop a program plan that identifies which problems must first be pursued. To facilitate this overall approach and to provide for short- and long-range waste management, logistics models have been developed to determine the transportation fleet requirements and costs. Results of the study are described in this report.
Date: March 1, 1978
Creator: Shappert, L. B.; Joy, D. S. & Heiskell, M. M.
Object Type: Report
System: The UNT Digital Library
Preliminary economic evaluation of a process for the production of fuel grade ethanol by enzymatic hydrolysis of an agricultural waste (open access)

Preliminary economic evaluation of a process for the production of fuel grade ethanol by enzymatic hydrolysis of an agricultural waste

This study concerns the preliminary economic feasibility of a process for converting agricultural waste (wheat straw) to fuel grade ethanol through enzymatic hydrolysis. A preliminary design for the process was developed on the basis of research concepts described in the literature. The base case design is for a 25 million gal/yr plant for 95 vol % ethanol from wheat straw. The preliminary design included material and energy balances and major equipment specifications and sizing, which in turn were used for estimating the required capital investment. Estimates of process operating costs and required selling prices were based on typical industrial conditions. The sensitivity of product ethanol cost to changes in key operating variables was determined in order to indicate where future process improvements are needed and more R and D effort is warranted. (JGB)
Date: January 1, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Uranium Hydrogeochemical and Stream Sediment Reconnaissance in southwestern Montana (open access)

Uranium Hydrogeochemical and Stream Sediment Reconnaissance in southwestern Montana

The Los Alamos Scientific Laboratory conducted a Hydrogeochemical and Stream Sediment Reconnaissance in southwestern Montana from early August to mid-October of 1976. A total of 1240 water and 1933 sediment samples were collected from 1994 locations at a nominal density of one location per 10 km/sup 2/. The water samples were collected from streams, wells, and springs; sediment samples were taken at streams and springs. All samples were analyzed at Los Alamos for total uranium by fluorometry or delayed-neutron counting. The uranium content of water samples ranges from below the detection limit (less than 0.3 ppB) to 45.30 ppB and has a mean value of 1.40 ppB. The uranium content of the sediment samples ranges between 0.20 and 206.80 ppM and averages 6.12 ppM. The chosen uranium anomaly threshold value was 7 ppB for surface waters (streams), 9 ppB for groundwaters (wells and springs), and 25 ppM for all sediment samples. The study area consists of the following lithologic groups: Precambrian basement complex, Precambrian Belt metasediments, Paleozoic and Mesozoic shelf sediments, Cretaceous and early Tertiary volcanic and plutonic rocks, Laramide orogenic clastic sediments, and middle to late Tertiary volcanic rocks and intermontane basin sediments. Most of the anomalous water and …
Date: February 1, 1978
Creator: Broxton, D. E.
Object Type: Report
System: The UNT Digital Library
Precipitation kinetics of a continuous precipitator, with application to the precipitation of ammonium polyuranate (open access)

Precipitation kinetics of a continuous precipitator, with application to the precipitation of ammonium polyuranate

A mathematical model describing the kinetics of continuous precipitation was developed which accounts for crystal nucleation, crystal growth, primary coagulation, and secondary coagulation. Population density distributions, average particle sizes, dominant particle sizes, and suspension density fractions of the crystallites, primary agglomerates, and secondary agglomerates leaving the continuous precipitator can be determined. This kinetic model was applied to the continuous precipitation of ammonium polyuranate, which consists of: (1) elementary crystals, (2) clusters or primary coagulated particles, and (3) agglomerates or secondary coagulated particles. The crystallites are thin, submicron, hexagonal platelets. The clusters had an upper size limit of about 7 ..mu.. in diameter and contained numerous small voids (less than 0.3 ..mu..m) due to the packing of the crystallites. The agglomerates had an upper size limit of about 40 ..mu..m in diameter and contained large voids (approximately 1 ..mu..m). The particle size distribution and particle structure of the ammonium polyuranate precipitate can be controlled through proper regulation of the precipitation conditions. The ratio of clusters to agglomerates can be best controlled through the uranium concentration, and the cohesiveness or internal bonding strength of the particles can be controlled with the ammonium to uranium reacting feed mole ratio. These two conditions, in …
Date: April 1, 1978
Creator: Hoyt, R.C.
Object Type: Report
System: The UNT Digital Library
Isotope applications in the environmental field (open access)

Isotope applications in the environmental field

Established uses of enriched isotopes in the environmental field were surveyed to determine future trends in isotope needs. Based on established isotope uses, on the projected increase in the pollution problem, and on the apparent social and economic pressure for pollution abatement, a significant demand for enriched isotopes appears to be developing for the assessment and control of air, water, and soil pollutants. Isotopic techniques will be used in combination with conventional methods of detection and measurement, such as gas chromatography, x-ray fluorescence, and atomic absorption. Recent advances in economical isotope separation methods, instrumentation, and methodology promise to place isotopic technology within the reach of most research and industrial institutions. Increased application of isotope techniques appears most likely to occur in areas where data are needed to characterize the movement, behavior, and fate of pollutants in the environment.
Date: February 17, 1978
Creator: DeWitt, R.
Object Type: Report
System: The UNT Digital Library
NO/sub 2/ levels in diesel exhaust (open access)

NO/sub 2/ levels in diesel exhaust

The safe operation of diesel-powered equipment in underground mines is predicated on there being sufficient ventilation to dilute the exhaust such that none of the toxicants in the dilute mixture exceed allowable levels. In order to determine the ventilation requirement for an engine, it is necessary to measure levels of the various toxicants in the exhaust. Measurements in the past typically either have excluded nitrogen dioxide or have not provided information on nitrogen dioxide specifically. Primarily this exclusion has resulted from lack of a fast, on-line analytical method. Development of the chemiluminescence analyzer appears now to provide the requisite capability; this instrument has been demonstrated to yield valid information for nitrogen dioxide levels and has been applied in a series of experiments conducted at the Department of Energy's Bartlesville (Okla.) Energy Research Center (BERC). Measurements of nitrogen dioxide in the exhaust from several diesel engines operated over wide ranges in speed and load were made as part of BERC's cooperative program with the U. S. Bureau of Mines. Results of these experiments indicate that nitrogen dioxide concentrations vary from less than 10% to approximately 30% of the total oxides of nitrogen. The nitrogen dioxide fraction was maximum at light load …
Date: January 1, 1978
Creator: Marshall, W.F.
Object Type: Report
System: The UNT Digital Library
RLPORINC: the RELAP4/MOD5 interface to ORINC (open access)

RLPORINC: the RELAP4/MOD5 interface to ORINC

The Oak Ridge Inverse code, ORINC, calculates the temperature distribution in an electric core pin from internal temperatures and the conditions in the surrounding environment. While the internal temperatures can be obtained from thermocouples in the Thermal Hydraulic Test Facility, the needed environmental conditions cannot be determined as directly from experimental data. However, this information can be determined from a modified version of the Reactor Linearized Analysis Program, RELAP. In particular, the IBM form of RELAP/MOD5 UPDATE2, as released by the Idaho National Engineering Laboratory, was modified to save the proper information in a convenient format. This document describes this RELAP-to-ORINC interface version of RELAP4 which has been named RLPORINC.
Date: January 10, 1978
Creator: Cliff, S.B.
Object Type: Report
System: The UNT Digital Library
Analysis of a neutron scattering and gamma-ray production integral and experiment on silicon dioxide for neutron energies from 1 to 15 MeV (open access)

Analysis of a neutron scattering and gamma-ray production integral and experiment on silicon dioxide for neutron energies from 1 to 15 MeV

Monte Carlo calculations were made to analyze the results of an integral experiment with a sample of SiO/sub 2/ to determine the adequacy of ENDF/B-IV neutron scattering and gamma-ray production cross-section data for silicon and oxygen. The experimental results analyzed included energy-dependent NE-213 detector neutron and gamma-ray count rates at a scattering angle of 90 deg and pulse-height spectra for scattered neutrons and gamma rays. The experiments were carried out with the ORELA 1- to 20-MeV pulsed neutron source. The pulse-height data were unfolded to generate secondary neutron and gamma-ray spectra at 90 deg as a function of incident neutron energy. Multigroup Monte Carlo calculations using the MORSE code and ENDF/B-IV cross sections were made to analyze all reported results. No outstanding discrepancies between calculated and measured responses were found on the neutron data below 12 MeV. Possible discrepancies in the inelastic scattering data above 12 MeV are indicated. This is consistent with a previous analysis of an oxygen experiment. A more detailed analysis will have to be performed before any definite conclusions can be drawn from these comparisons.
Date: January 1, 1978
Creator: Cramer, S. N. & Oblow, E. M.
Object Type: Report
System: The UNT Digital Library
Simple measurement of line density (open access)

Simple measurement of line density

Energy line density, E/sub l/ = ..integral..(F/2)nk(T/sub e/ + T/sub i/)dA, has proved to be one of the easiest (and most critical) measurements made on the Scylla IV-P, 5-m linear theta pinch. A quantitative evaluation of end-stoppering techniques is made available by extracting the line energy containment time, tau/sub E/sub l//, from the time history of E/sub l/. To model E/sub l/(t) properly and, hence, determine the details of energy loss mechanisms (streaming and thermal conduction) requires separate measurements of n and T. A simple measurement of line density, n/sub l/ = ..integral..ndA, is proposed, in which a single laser beam is passed repeatedly through the plasma column along different chords. A discussion is presented of the measurement accuracy as a function of the number of passes.
Date: February 1, 1978
Creator: Armstrong, W.T. & Siemon, R.E.
Object Type: Report
System: The UNT Digital Library
Field procedures for the uranium hydrogeochemical and stream sediment reconnaissance as used by the Los Alamos Scientific Laboratory (open access)

Field procedures for the uranium hydrogeochemical and stream sediment reconnaissance as used by the Los Alamos Scientific Laboratory

This manual of field procedures is prepared to aid personnel involved in the field sampling of natural waters and waterborne sediment for the Los Alamos Scientific Laboratory (LASL) as part of the US Department of Energy (DOE) Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of the National Uranium Resource Evaluation (NURE) program. It presents the procedural guidelines to be followed by all contractors, contractor employees, and others who collect, treat, or otherwise handle samples taken for the LASL as part of the HSSR program. Part I relates to all sampling in the conterminous states of the US for which the LASL is responsible to the DOE for carrying out the HSSR work. Part II describes procedures to be followed for HSSR work, using helicopter support, in the state of Alaska. The objective of the manual is to insure that consistent techniques are used throughout the survey. If any procedure is unclear or cannot be followed, telephone collect to Group G-5, LASL, (505) 667-7590, for further instructions. No variations in the specific procedures should be made without prior approval of the LASL.
Date: April 1, 1978
Creator: Sharp Jr., R. R. & Aamodt, P. L.
Object Type: Report
System: The UNT Digital Library
Germanium detector system for the detection of transuranics at low-activity concentrations in soil. [/sup 241/Am, /sup 240/Pu, /sup 239/Pu, /sup 238/U, /sup 232/Th] (open access)

Germanium detector system for the detection of transuranics at low-activity concentrations in soil. [/sup 241/Am, /sup 240/Pu, /sup 239/Pu, /sup 238/U, /sup 232/Th]

A photon spectroscopy system is described which is designed for the detection of plutonium and /sup 241/Am in soil samples with a minimum turnaround time. Quantification is based upon the 60-keV gamma emitted in /sup 241/Am decay and upon the uranium L x-rays (energies from 13 to 22 keV) emitted by plutonium isotopes during alpha decay. The detector is a single-crystal, intrinsic-germanium-planar detector with a surface area of 21 cm/sup 2/. Sensitivity is increased by incorporating a detector window with a larger than normal surface area. This optimized window size was established by Monte Carlo calculations. For small, Petri-dish samples, detection limits at the 3 sigma level for a 4-hr counting time are better than 4 pCi/g for plutonium and better than 0.05 pCi/g for /sup 241/Am. The specifications, performance, and cost of the system are discussed.
Date: January 1, 1978
Creator: West, L.; Umbarger, C.J. & Dempsey, T.
Object Type: Article
System: The UNT Digital Library
Process for cleaning and removal of sulfur compounds from low Btu gases. Quarterly summary report, October--December 1977 (open access)

Process for cleaning and removal of sulfur compounds from low Btu gases. Quarterly summary report, October--December 1977

Problems which occurred in the startup of the remodelled process development unit are described. The extraction section of the plant performed well with sulfur recoveries exceeding the design value of 95%. (LTN)
Date: January 1, 1978
Creator: Moore, R. H.; Ham, D. G.; Mitchell, D. H.; Robertus, R. J. & Stegen, G. E.
Object Type: Report
System: The UNT Digital Library
Geothermal environmental seminar-'78 (open access)

Geothermal environmental seminar-'78

Thirty-seven papers are included. Two were abstracted for EDB previously. Abstracts were prepared for the remaining thirty-five. (MHR)
Date: January 1, 1978
Creator: Tucker, F. L. & Tanner, L. R.
Object Type: Article
System: The UNT Digital Library
Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Shipping Cask D-38 (open access)

Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Shipping Cask D-38

An analytical evaluation of the Oak Ridge National Laboratory Shipping Cask D-38 (solids shipments) was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.
Date: April 1, 1978
Creator: Klima, B. B.; Shappert, L. B.; Seagren, R. D. & Box, W. D.
Object Type: Report
System: The UNT Digital Library
Preliminary concepts for materials measurement and accounting in critical facilities (open access)

Preliminary concepts for materials measurement and accounting in critical facilities

Preliminary concepts are presented for improved materials measurement and accounting in large critical facilities. These concepts will be developed as part of a study that will emphasize international safeguarding of critical facilities. The major safeguards problem is the timely verification of in-reactor inventory during periods of reactor operation. This will require a combination of measurement, statistical sampling, and data analysis techniques. Promising techniques include integral measurements of reactivity and other reactor parameters that are sensitive to the total fissile inventory, and nondestructive assay measurements of the fissile material in reactor fuel drawers and vault storage canisters coupled with statistical sampling plans tailored for the specific application. The effectiveness of proposed measurement and accounting strategies will be evaluated during the study.
Date: January 1, 1978
Creator: Cobb, D.D. & Sapir, J.L.
Object Type: Report
System: The UNT Digital Library
Semi-annual report on strategic special nuclear material inventory differences (open access)

Semi-annual report on strategic special nuclear material inventory differences

This periodic report of Inventory Differences covers the period October 1, 1976, through March 31, 1977 for Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of Strategic Special Nuclear Material (SSNM). Included in this report are the low enriched uranium inventory differences for DOE's gaseous diffusion plant cascades. (LK)
Date: January 1, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Assessment of lamellar tearing (open access)

Assessment of lamellar tearing

Information on lamellar tearing is summarized and related to proposed ASME Code requirements. Lamellar tearing is characterized as a complex phenomenon related to poor short transverse ductility and through-thickness strain. The material, welding, and design variables that affect lamellar tearing are shown to be complex and interrelated. The commonly reported tests for assessing material susceptibility are described, with the controversy over their validity being carefully detailed. Although the use of a nondestructive test such as ultrasonic examination is most desirable, a widely applicable test method does not appear to be available. Of the destructive tests, the short transverse tensile reduction-of-area currently offers the most applicable means of assessing material susceptibility. However, because of the importance of matrix toughness, the short transverse Charpy V-notch test should be considered for use as an additional test if acceptance limits are developed. The ultrasonic detection of lamellar tears is susceptible to interpretation errors, which can make it overly conservative and lead to unnecessary repairs. The repair of tears is described as costly, difficult, and sometimes ineffective. Current design requirements appear to preclude any failures during static and fatigue service loads. However, without improvement of short transverse ductility, certain dynamic service loads could cause lamellar …
Date: March 1, 1978
Creator: McEnerney, J.W.
Object Type: Report
System: The UNT Digital Library
Initial results from the first Los Alamos hot dry rock energy system (open access)

Initial results from the first Los Alamos hot dry rock energy system

The pressurized-water loop for extraction of natural heat from dry crustal rock is, as this is written, eight weeks into its initial long-term continuous circulation test. During most of this time, flow-impedance through the man-made fracture system has decreased continuously so that, with a nearly constant pressure difference between injection and recovery wells, flow rate has increased steadily to the maximum capacity of the surface piping--about 16 liters per second. Temperature of water entering the recovery well from the fracture system at first decreased rapidly; however, the rate of decrease has diminished steadily, and temperature is now nearly constant at about 94/sup 0/C. The increase in flow rate so far has overwhelmed the temperature decrease, so that rate of heat extraction has approximately doubled, to above 5 MW. Composition of the recirculated water apparently has not yet stabilized, but total dissolved solids (chiefly silica) is relatively low and rate of water loss from the loop has decreased to about 2% of the total flow rate. Both the effective volume and the effective surface area of the fracture system have recently increased significantly which, together with stabilization of the effluent temperature, suggests that thermal contraction is having its expected effect on …
Date: January 1, 1978
Creator: Smith, M.C.
Object Type: Article
System: The UNT Digital Library
Cost of splitting in Monte Carlo transport (open access)

Cost of splitting in Monte Carlo transport

In a simple transport problem designed to estimate transmission through a plane slab of x free paths by Monte Carlo methods, it is shown that m-splitting (m > or = 2) does not pay unless exp(x) > m(m + 3)/(m - 1). In such a case, the minimum total cost in terms of machine time is obtained as a function of m, and the optimal value of m is determined.
Date: March 1, 1978
Creator: Everett, C.J. & Cashwell, E.D.
Object Type: Report
System: The UNT Digital Library
Depth distributions of low energy deuterium implantations in (110) tungsten: a theoretical model (open access)

Depth distributions of low energy deuterium implantations in (110) tungsten: a theoretical model

The depth distributions of 80 eV D/sup +/ implants in (110) W have recently been measured by field desorption microscopy. Prominent structure, consisting of seven major and several minor peaks, is observed in the measured distributions. This contrasts with conventional implantation theory which predicts two peaks, one for the channeled D/sup +/ and one for the nonchanneled D/sup +/. The observed structure is explained in the present report by a model which ascribes the various peaks to D/sup +/ groups which have been scattered into planar channels by the surface impurities. The model allows a determination of D/sup +/ stopping powers in the various planar channels and the stopping power of C and O impurities which recoil down the (110) axis. The model suggests that surface location of the impurities as well as their elastic scattering cross section for D/sup +/ projectiles could be extracted from more elaborate calculations and experiments.
Date: March 1, 1978
Creator: Brice, D.K.
Object Type: Report
System: The UNT Digital Library
Summary data for U. S. commercial nuclear power plants in the United States (open access)

Summary data for U. S. commercial nuclear power plants in the United States

A compilation of data is presented for all United States commercial nuclear power plants for which a construction permit application was made through the Nuclear Regulatory Commission. The data are compiled in four separate tables with cross-referencing indexes: Table 1--General Data; Table 2--Reactor Data; Table 3--Site Data, and Table 4--Circulating-Water System Data. The power plants are listed in numerical order by docket number in all four tables.
Date: March 20, 1978
Creator: Heddleson, F.A.
Object Type: Report
System: The UNT Digital Library