Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977 (open access)

Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977

The exposures of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a ..beta.. dose of 10 ..mu..Ci/cm/sup 3/, a ..gamma.. dose of 10/sup -5/ ..mu..Ci/cm/sup 3/, and an ..cap alpha.. dose of 4.9 x 10/sup -3/ ..mu..Ci/cm/sup 3/ were completed. Exposure to ..beta.. and ..gamma.. radiation did not affect membrane performance. After a simulated six months of exposure to ..cap alpha.. radiation some degradation of membrane performance occurred. Several experiments were made on a laboratory-scale reverse-osmosis unit using the product from ultrafiltration as feed. Rejection of activity ranged from 88 to 99 percent. The ''continuous'' ultrafiltration pilot run was completed. Approximately 40,000 gal were processed in over 70 hr of operating time without shutdown for cleaning. Flux and rejection were maintained relatively steady over this period. Rejection of gross alpha ranged from 80 to 99.5 percent depending on the ionic content of the waste stream. Flux rates ranged from 5 to 8 liters/min over this period. The engineering column tests were continued using uranium-233 with product from the ultrafiltration pilot plant. Flow rates and pH were varied in order to determine optimum operating conditions.
Date: February 24, 1978
Creator: Koenst, J. W.; Herald, W. R. & Roberts, R. C.
Object Type: Report
System: The UNT Digital Library
Empirical tuff equation of state models (open access)

Empirical tuff equation of state models

None
Date: April 24, 1975
Creator: Wight, L. H.
Object Type: Report
System: The UNT Digital Library
Building 431 fire tests (open access)

Building 431 fire tests

An extensive discussion of considerations for fire protection in the LLL mirror fusion test facility (MFTF) is presented. Because of the large volume and high bays of the building, sufficient data on fire detection is unavailable. Results of fire detection tests using controlled fire sources in the building are presented. Extensive data concerning the behavior of the building atmosphere are included. Candidate fire detection instrumentation and extinguishing systems for use in the building are briefly reviewed. (RME)
Date: October 24, 1977
Creator: Alvares, N. J.; Beason, D. G.; Ford, H. W. & Magee, M. W.
Object Type: Report
System: The UNT Digital Library
Energy balance measurements for Shiva (open access)

Energy balance measurements for Shiva

The Lawrence Livermore Laboratory Shiva laser-target interaction facility is designed for experiments at 20 to 30 terawatts. At this power level there will be larger fluxes of neutrons, x-rays, electrons and ions than have been previously measured. The measurements of energy converted into the various reaction products is crucial both in target design and performance analysis of the actual experiment. The total energy absorbed is measured by a box calorimeter surrounding the target except for beam input holes. This measurement prevents the use of other diagnostics, so for normal operation an energy balance module was designed for location on ports on the Shiva target chamber. This module monitors the energy in scattered light at 10640 A and 5320 A or 7118 A. It also contains a faraday cup and plasma and x-ray calorimeters. The distribution of energy in scattered light, plasma and x-rays will be mapped by 58 such modules.
Date: October 24, 1977
Creator: Glaros, S.S.; Rupert, V.C.; Gunn, S.R.; Phillion, D.W. & Kornblum, H.N.
Object Type: Article
System: The UNT Digital Library
Shiva optical diagnostics (open access)

Shiva optical diagnostics

In the laser fusion program at Lawrence Livermore Laboratory, no target experiment is complete unless it is complemented by careful measurements of the laser pulse that irradiates the target. For this purpose, an incident beam diagnostics (IBD) package has been designed for the Shiva laser. The package will furnish data on items such as the total energy and the focusable energy out of the laser chain, and the spatial and temporal energy and power distribution at the target plane. Understanding laser-plasma interactions requires knowledge of the amount of 1.06 ..mu..m light energy that is scattered in various directions from the target. The light energy that is scattered toward the beam focusing lens is analyzed by a reflected beam diagnostic (RBD) package containing a calorimeter, a multiple image camera and a TV camera. This paper describes the detailed design and operation of the IBD and RBD packages as tools to align spatial filters and targets, as well as to diagnose the laser beams and target reflectivity.
Date: October 24, 1977
Creator: Rienecker, F.; Kobierecki, M.; Ozarski, R.; Seppala, L.; Manes, K. & Merritt, B.
Object Type: Article
System: The UNT Digital Library
Energy sensitivity and variability analysis of Populus hybrid short-rotation plantations in northeastern United States. Final report (open access)

Energy sensitivity and variability analysis of Populus hybrid short-rotation plantations in northeastern United States. Final report

Production of biomass by corn-like plantations has been demonstrated by a number of researchers. These forest analogs of agronomic cropping systems have the potential to yield substantially more biomass per unit area than traditional forests. Care is needed in choosing the appropriate sites, species, spacing, and harvesting strategies. Opportunities for increased yields have been suggested for fertilization and irrigation. Utilization of the biomass from these dense plantations for energy was the focus of this study. Although the amount of energy potential of the biomass is important, the energy output must be greater than the energy input for biomass to have a positive benefit to society. Further, in order to completely evaluate the net energy of the system it is necessary to examine the energy out-to-in ratios on the basis of usable energy (for example, usable heat, process steam and electricity), as well as all of the energies expended in producing, harvesting, transporting and processing the biomass. The objective of this study is to establish and analyze the energy inputs for selected management strategies in order to evaluate the sensitivity and variability of the energy inputs in the net energy analysis, and based on the net energy analysis to recommend a …
Date: October 24, 1979
Creator: Bowersox, T.W. & Blankenhorn, P.R.
Object Type: Report
System: The UNT Digital Library
Rock equation of state: a constitutive computer model (open access)

Rock equation of state: a constitutive computer model

A constitutive model for a rock equation of state was developed in HEMP and CEL-HEMP computer codes. The model includes the mechanical and thermal properties of soil, such as elasticity, pore closure, compaction, and vaporization. Three test problems were computed using the equation of state: ground motion following the LATIR event, impact vaporization of preheated plates, and surface motion produced from exploding a 3.7-kg(10-lb) charge at a depth of 6.5 m. Agreement between our computations from the model and actual measurements is remarkably close.
Date: August 24, 1977
Creator: Kamegai, M.
Object Type: Report
System: The UNT Digital Library
Seismic analysis of the nuclear fuel service reprocessing plant at West Valley, N. Y (open access)

Seismic analysis of the nuclear fuel service reprocessing plant at West Valley, N. Y

This report was prepared at the request of the Nuclear Regulatory Commission as a part of a license review of the nuclear fuel reprocessing plant operated by Nuclear Fuel Services, Inc., at West Valley, N.Y. The report discusses the approach used by the Lawrence Livermore Laboratory in performing an independent seismic analysis of the facility. It includes a description of the facility, our modeling and analysis techniques, failure criteria, results, and conclusions. Two modes of failure are identified and their consequences discussed.
Date: May 24, 1977
Creator: Murray, R. C.; Nelson, T. A. & Davito, A. M.
Object Type: Report
System: The UNT Digital Library
High performance inertial fusion targets (open access)

High performance inertial fusion targets

Inertial confinement fusion (ICF) designs are considered which may have very high gains (approximately 1000) and low power requirements (<100 TW) for input energies of approximately one megajoule. These include targets having very low density shells, ultra thin shells, central ignitors, magnetic insulation, and non-ablative acceleration.
Date: August 24, 1977
Creator: Nuckolls, J.H.; Bangerter, R.O.; Lindl, J.D.; Mead, W.C. & Pan, Y.L.
Object Type: Article
System: The UNT Digital Library
Fallout model for system studies (open access)

Fallout model for system studies

A versatile fallout model was developed to assess complex civil defense and military effect issues. Large technical and scenario uncertainties require a fast, adaptable, time-dependent model to obtain technically defensible fallout results in complex demographic scenarios. The KDFOC2 capability, coupled with other data bases, provides the essential tools to consider tradeoffs between various plans and features in different nuclear scenarios and estimate the technical uncertainties in the predictions. All available data were used to validate the model. In many ways, the capability is unmatched in its ability to predict fallout hazards to a society.
Date: October 24, 1979
Creator: Harvey, T. F. & Serduke, F. J. D.
Object Type: Report
System: The UNT Digital Library
General Chemistry Division quarterly report, January--March 1977 (open access)

General Chemistry Division quarterly report, January--March 1977

Reported are: development of analytical capabilities of a submillimeter spectrometer; improved minimum detectibility of laser-induced molecular fluorescence; use of laser photoionization sources for analytical mass spectrometry; photoacoustic spectroscopy of solids; development of time-resolved spectroscopy for multicomponent mixtures; excited-state reactions of Ba/sup +/ + N/sub 2/O ..-->.. BaO +N/sub 2/; development of an ion-cyclotron-resonance spectrometer; development of glow-discharge multielement analytical systems; analysis of deposits on exploding gold bridgeware detonators; results of /sup 13/C-NMR study of toluene-2,4-diisocyanate polymers; analysis of 1,6-hexanediamine and 1,3-dipiperiodylpropane; studies of discrepancies between chromatographic and mass spectrometric data. (JRD)
Date: June 24, 1977
Creator: Harrar, J.E. (ed.)
Object Type: Report
System: The UNT Digital Library
Goose River, Maine, demonstration project, January 1978-October 1978. Final report (open access)

Goose River, Maine, demonstration project, January 1978-October 1978. Final report

The proposed Goose River Project is a commercial power development consisting of 4 power dams and one storage dam. All available energy is to be wholesaled to the Central Maine Power Company, the utility holding the franchise for the area. A description of the economic feasibility of the proposed project is presented.
Date: November 24, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
324 building safety analysis report supplement (open access)

324 building safety analysis report supplement

Process engineering designs, major equipment and plant facilities to be utilized in commercial nuclear waste preparation and vitrification in the 324 Radiochemical Engineering Building are reviewed with regard to accident potential and consequences. This Safety Analysis Report Supplement compares calculated environmental doses anticipated from the Commercial Nuclear Waste Vitrification Project (CNWVP) routine operations with the average doses from past waste management operations conducted at the Hanford Project and finds them to be significantly less. The calculated CNWVP environmental doses are found to be far below presently applicable ERDA standards and standards proposed by the EPA for nuclear power operations. (DLC)
Date: June 24, 1977
Creator: Dodd, A. O. & Wittenbrock, N. G.
Object Type: Report
System: The UNT Digital Library
Simulations of intermediate density laser fusion targets: recent progress in design and analysis (open access)

Simulations of intermediate density laser fusion targets: recent progress in design and analysis

The attainment of low-adiabat compression to high final state density is essential for achieving high gain thermonuclear micro-implosions. Using 1- and 2-dimensional numerical simulations with LASNEX, the target performance which can be expected and the limitations imposed by absorption heating, and transport for targets designed to reach 100 x liquid DT density (20g/cm/sup 3/) are discussed. The requirements imposed by the need for low preheat, adequate implosion symmetry, and the behavior of fluid instabilities are discussed for these recent target designs. Methods for diagnosis of density are discussed.
Date: August 24, 1977
Creator: Mead, W. C.; Lindl, J. D.; Nuckolls, J. H.; Larsen, J. T.; Bailey, D. S. & Pan, Y. L.
Object Type: Article
System: The UNT Digital Library
Analytical chemical system for the determination of heavy metals and organic compounds. Annual progress report, December 1, 1978-November 30, 1979 (open access)

Analytical chemical system for the determination of heavy metals and organic compounds. Annual progress report, December 1, 1978-November 30, 1979

Progress has been made in the synthesis and characterization of new resins for sequestering inorganic and organic compounds. The capabilities of the poly(dithiocarbamate) resin have been extended, a new poly(acrylamidoxime) resin prepared and characterized, and a series of resins for organic compounds prepared and tested. Limited actual sample analyses have been performed with these resins. A new inductively coupled plasma source, spectrometer, and computer system have been received and they are undergoing tests and installation. With this system in place, the multielement analysis of metals during the forthcoming period will insure the application of sequestering resins to practical analysis of energy-related materials. An automated sample handling and data system has been designed, some components purchased, and construction is scheduled for 1980.
Date: October 24, 1979
Creator: Siggia, S. & Barnes, R. M.
Object Type: Report
System: The UNT Digital Library
Analysis of dense pusher laser-driven implosions for intermediate densities (open access)

Analysis of dense pusher laser-driven implosions for intermediate densities

Post-shot analysis of targets designed to achieve a diagnosible compression of DT gas to 2. g/cm/sup 3/ or 10 x liquid density is reported. The SHIVA laser provided 15 to 20 TW of 1.06 ..mu..m laser light. Detailed comparisons of diagnostic results with hydro-code calculations are made. Implications for laser light absorption/scattering, thermal conduction, suprathermal electron preheat, implosion symmetry, and pusher-fuel mix are discussed. Uncertainties of the density determination methods are analyzed. Good overall consistency is found, indicating strong support for the successful attainment of 1.-3. g/cm/sup 3/.
Date: October 24, 1979
Creator: Mead, W. C.; Orth, C. D.; Bailey, D. S.; McClellan, G. & Estabrook, K. G.
Object Type: Article
System: The UNT Digital Library
Analysis of LOFT containment nozzles 11A, 11B, 11D, 12A, 13B, 13C, and 13D by Bijlaard method (open access)

Analysis of LOFT containment nozzles 11A, 11B, 11D, 12A, 13B, 13C, and 13D by Bijlaard method

The purpose of this analysis was the calculation of stresses in the LOFT Containment Vessel at the point of nozzle penetration produced by loads on the nozzles and to show that those stresses are within the 1965 ASME Boiler and Pressure Vessel Code allowables. The stress determination was done by the method developed by P. P. Bijlaard on the worst load case for each diameter nozzle. The operating basis earthquake (OBE) at nozzle 11D produced the most severe load case. All load cases resulted in containment vessel stresses that were less than the allowables as stated in N-414 of the 1965 ASME Boiler and Pressure Vessel Code.
Date: July 24, 1978
Creator: McFadden, D.F.
Object Type: Report
System: The UNT Digital Library
Theoretical considerations in solid bowl centrifugation (open access)

Theoretical considerations in solid bowl centrifugation

A combination of literature survey and independent analysis determined three relationships for the prediction of the critical (or minimum recoverable) particle size in a solid bowl centrifuge. The relationships were derived based on three different theories of fluid behavior within the centrifuge; (1) laminar film flow (laminar film model), (2) plug flow (Sharples Model), and parabolic flow (modified Sharples Model). The critical particle size for the centrifuge used in Cs-PTA recovery in the CAW process predicted by the three relationships range from 0.19 to 0.34 ..mu..m (1 ..mu..m = 10/sup -6/m). The laminar film model gives the most conservative estimate of critical particle size (0.34 ..mu..m) and the resulting relationship is recommended for use to predict solid bowl centrifuge performance. Three correction factors are incorporated into the predictive equations to account for the effects of fluid turbulence near the centrifuge feed point, fluid lag and hindered settling. Of these factors, turbulence near the feed point (which is accounted for by using an effective centrifuge length) has the greatest impact, increasing the predicted critical particle size by 15%, while the combination of fluid lag and hindered settling factors increase the recoverable particle size by 4%. The overall effect of the correction …
Date: August 24, 1979
Creator: Hamilton, R. T.
Object Type: Report
System: The UNT Digital Library
P. G. and E. Geysers Retrofit Project, Units 1-12: Final Report, Technical Data, Volume I - Sections 1-8 (open access)

P. G. and E. Geysers Retrofit Project, Units 1-12: Final Report, Technical Data, Volume I - Sections 1-8

The purpose of this work is to demonstrate whether there is a cost benefit to Pacific Gas and Electric Company in replacing the present iron catalyst/caustic/peroxide system used in the direct contact condenser units with an alternative approach using surface condensers and the Stretford System for hydrogen sulfide abatement.
Date: August 24, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
P. G. and E. Geysers Retrofit Project, Units 1-12 Condensed Final Report (open access)

P. G. and E. Geysers Retrofit Project, Units 1-12 Condensed Final Report

Geysers Power Plant Units 1-12 conceptual study of two H{sub 2}S abatement systems. The study is to provide a cost benefit and technical analysis of the existing (iron/caustic/peroxide) abatement system compared to retrofitting Units 1-12 with surface condensers and vent gases processing with the Stretford process. The study is based on the understanding that both H{sub 2}S abatement system compared meet the Air Pollution Board's requirements for H{sub 2}S emissions. The summary of this paper is that it is economical to convert from the existing abatement (iron/caustic/peroxide) to the alternative (surface condenser/Stretford) by a substantial amount. There is also a most economical timing sequence to accomplish the conversion to the surface condenser/Stretford abatement. The project if started immediately would be finished and operating by 1984. It is felt that the surface condenser/Stretford abatement system will ultimately meet the Air Pollution Board's requirements and improve the capacity factor of the Geysers power plant Units 1-12.
Date: August 24, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Data analysis for nuclear materials accounting (open access)

Data analysis for nuclear materials accounting

Materials accounting for special nuclear material in future fuel cycle facilities will draw heavily on sophisticated data-analysis techniques. Decision analysis, which combines elements of estimation theory, decision theory, and systems analysis, can be used to reduce errors caused by subjective data evaluation and to condense large collections of data to a smaller set of more descriptive statistics. The methods and requirements of decision analysis are discussed and illustrated by a conceptual design example of an advanced materials accounting system for a plutonium nitrate-to-oxide conversion facility.
Date: April 24, 1979
Creator: Shipley, J.P.
Object Type: Article
System: The UNT Digital Library
Double-shelled target simulations with LASNEX (open access)

Double-shelled target simulations with LASNEX

Double-shelled inertial confinement fusion targets in which the outer shell is exploded have been studied with LASNEX. To achieve high DT density, configurations have been found in which the inner shell is ablatively driven by the hot outer shell. Calculations indicate that greater than 100 times liquid DT density can be achieved with the Shiva laser while still retaining some of the symmetry and stability advantages of the single-shelled exploding pusher target. The relative merits of transferring energy to the inner shell by electron conduction and by hydrodynamic work will be discussed.
Date: October 24, 1978
Creator: McClellan, G.
Object Type: Article
System: The UNT Digital Library
Nuclear criticality experiments from 1943 to 1978: an annotated bibliography. Volume 1. Main listing (open access)

Nuclear criticality experiments from 1943 to 1978: an annotated bibliography. Volume 1. Main listing

The bibliography contains 1067 citations from the literature of critical and near-critical nuclear experiments. It provides an up-to-date index to reports containing useful data for many types of criticality studies. Most of the reports can provide specifications for relatively simple critical configurations necessary for validating nuclear constants and calculational techniques. The reports of more than 1143 experimentors at 38 international facilities since 1943 are cross-referenced. The collection contains the prototypes of many different designs of nuclear reactors and studies performed to insure the safe use of fissile materials in chemical processing plants, storage facilities, and transportation containers. The bibliography has three volumes. Volume 1 contains the main listing of citations with abstracts. Volume 2 is a set of indexes organized by report number, publication date, experimental facility, and author name. Volume 3 provides a subject index, concorded on the significant keyphrases derived from titles, and an index of keyterms derived from titles, and an index of keyterms extracted from titles and abstracts. The bibliography was printed by computer as a selection from a computerized system at Lawrence Livermore Laboratory contaning information and data on criticality experiments.
Date: April 24, 1979
Creator: Koponen, B. L.; Wilcox, T. P. & Hampel, V. E.
Object Type: Report
System: The UNT Digital Library
Nuclear criticality experiments from 1943 to 1978: an annotated bibliography. Volume 2. Lookup tables (open access)

Nuclear criticality experiments from 1943 to 1978: an annotated bibliography. Volume 2. Lookup tables

None
Date: April 24, 1979
Creator: Koponen, B. L.; Wilcox, T. P. & Hampel, V. E.
Object Type: Report
System: The UNT Digital Library