Advanced Thermohydraulic Simulation Code for Transients in LMFBRs (SSC-L code) (open access)

Advanced Thermohydraulic Simulation Code for Transients in LMFBRs (SSC-L code)

Physical models for various processes that are encountered in preaccident and transient simulation of thermohydraulic transients in the entire liquid metal fast breeder reactor (LMFBR) plant are described in this report. A computer code, SSC-L, was written as a part of the Super System Code (SSC) development project for the "loop"-type designs of LMFBRs. This code has the self-starting capability, i.e., preaccident or steady-state calculations are performed internally. These results then serve as the starting point for the transient simulation.
Date: February 1, 1978
Creator: Agrawal, A. K.
Object Type: Report
System: The UNT Digital Library
Temporal aspects of tumorigenic response to individual and mixed carcinogens. Comprehensive progress report, June 1, 1975--May 31, 1978. [Mouse skin, rats, hamsters] (open access)

Temporal aspects of tumorigenic response to individual and mixed carcinogens. Comprehensive progress report, June 1, 1975--May 31, 1978. [Mouse skin, rats, hamsters]

The research proposed here is designed to obtain a better understanding of the temporal kinetics of tumor induction when one or more carcinogens are present simultaneously or sequentially for prolonged periods of time. Studies done to date under this contract have shown that carcinogenesis in mouse skin by polycyclic aromatic hydrocarbon carcinogens is consistent with the induction of dependent and autonomous cell transformations by the carcinogen followed by the conversion of autonomous tumor cells into malignancies at a rate which is determined by the level of carcinogen exposure. Dependent cell transformations remain latent in the skin unless expressed by a promoting agent. Dependent neoplasia appears to follow one-hit kinetics while malignancy is a multihit endpoint. Dose-related and time-related aspects of tumor induction are separable in the initiation-promotion system of mouse skin which along with rat skin and hamster lung is being used as a model for testing hypotheses. Results to date provide the basis for a new interpretation of the linear non-threshold extrapolation model. The broad aim of the study is to provide a basis or rationale for estimating risks associated with prolonged exposures to carcinogens found in the environment and to predict how different tissues and species respond to …
Date: February 1, 1978
Creator: Albert, R. E.; Burns, F. J. & Altshuler, B.
Object Type: Report
System: The UNT Digital Library
Public Protection Strategies for Potential Nuclear Reactor Accidents: Sheltering Concepts with Existing Public and Private Structures (open access)

Public Protection Strategies for Potential Nuclear Reactor Accidents: Sheltering Concepts with Existing Public and Private Structures

Three generic sheltering/relocation strategies are identified and discussed. They are: population relocation only (no specific sheltering response initiated); sheltering at location following by relocation; and preferential sheltering followed by relocation. Shielding factors representative of these strategies are calculated, and the adequacy of using average shielding factors for the calculation of public health effects is discussed.
Date: February 1, 1978
Creator: Aldrich, David C.; Ericson, David M. Jr. & Johnson, Jay D.
Object Type: Report
System: The UNT Digital Library
Photon Dose Rate From Induced Activity in the Beam Stop of a 400 GeV Proton Accelerator (open access)

Photon Dose Rate From Induced Activity in the Beam Stop of a 400 GeV Proton Accelerator

Calculated results are presented of the photon dose rate from the induced activity produced in the beam stop of a high-energy proton accelerator. Incident proton energies of 400 GeV, 200 GeV, and 30 GeV are considered. In each case the photon dose rate is given as a function of radius in the beam stop and as a function of time after the beam is turned off for assumed operating times of 90 days and 10 years.
Date: February 1, 1978
Creator: Alsmiller, R. G., Jr.; Gabriel, T. A. & Barish, J.
Object Type: Report
System: The UNT Digital Library
Computerized transportation model for the NRC Physical Protection Project. Versions I and II (open access)

Computerized transportation model for the NRC Physical Protection Project. Versions I and II

Details on two versions of a computerized model for the transportation system of the NRC Physical Protection Project are presented. The Version I model permits scheduling of all types of transport units associated with a truck fleet, including truck trailers, truck tractors, escort vehicles and crews. A fixed-fleet itinerary construction process is used in which iterations on fleet size are required until the service requirements are satisfied. The Version II model adds an aircraft mode capability and provides for a more efficient non-fixed-fleet itinerary generation process. Test results using both versions are included.
Date: February 23, 1978
Creator: Anderson, G.M.
Object Type: Report
System: The UNT Digital Library
Status report to DOE Nuclear Data Committee (open access)

Status report to DOE Nuclear Data Committee

This status report includes brief reports on measurements and calculations of quantities for nuclear data applications and data for reactor safety. Separate abstracts were prepared for those items with a significant amount of data. (RWR)
Date: February 16, 1978
Creator: Anderson, J. D.; Browne, J. C. & Struble, G. L.
Object Type: Report
System: The UNT Digital Library
Parasitic Components From Charge Transfer in Neutral Beams for Fusion (open access)

Parasitic Components From Charge Transfer in Neutral Beams for Fusion

Charge exchange within accelerating grids in neutral beam systems produces parasitic beam components which degrade the performance of the systems. These components also change the plasma confinement properties at the target. This note discusses parasitic beams produced in three types of grid systems: (1) TFTR/MFTF sources, (2) accel-decel grids for low energy beams, and (3) the JSC negative ion system.
Date: February 1, 1978
Creator: Anderson, O. A.
Object Type: Report
System: The UNT Digital Library
Parasitic Components from Charge Transfer in Neutral Beams for Fusion (open access)

Parasitic Components from Charge Transfer in Neutral Beams for Fusion

None
Date: February 1, 1978
Creator: Anderson, O. A.
Object Type: Report
System: The UNT Digital Library
The Value of Energy Storage for Direct-Replacement Solar Thermal Power Plants (open access)

The Value of Energy Storage for Direct-Replacement Solar Thermal Power Plants

None
Date: February 14, 1978
Creator: Anderson, T.; Kaplan, S. & Wilson, J.
Object Type: Article
System: The UNT Digital Library
Equipment develoment report: downhole fluid injector (open access)

Equipment develoment report: downhole fluid injector

The development, design, fabrication, and operation of a tool used for injecting a discrete quantity of fluid (e.g. a dye) at a desired location within a hot geothermal borehole are described. Assembly and operating instructions are included.
Date: February 1, 1978
Creator: Archuleta, J. R.; Fink, C. F. & Kurtenbach, J.
Object Type: Report
System: The UNT Digital Library
Equipment development report: borehole-fluid sampling tool (open access)

Equipment development report: borehole-fluid sampling tool

The design and development of a tool for collecting fluid samples from hot, deep geothermal boreholes are discussed. This tool has performed satisfactorily in the field at downhole temperatures of 200/sup 0/C and pressures of 34.5 MPa (5000 psi). Assembly and operating instructions are included.
Date: February 1, 1978
Creator: Archuleta, J.R.; Fink, C.F. & Kurtenbach, J.
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
DYMAC demonstration program: Phase I experience (open access)

DYMAC demonstration program: Phase I experience

The DYnamic MAterials Control (DYMAC) project tested a prototype system at the DP Site LASL plutonium facility, which consisted of a computerized accounting system based on material balancing by unit process. Transactions were written to describe the movement of material from one unit process to another. In the DYMAC prototype a specially designed computer program handled transactions that operators entered into the system via a terminal in the processing area. The transactions contained the same information that is used in the present LASL paper accounting system to create an inventory. During a 6-week period the DYMAC system operated in parallel with the paper system. At the end of the period results showed the DYMAC system was able to keep an accurate and timely inventory. Concurrent with testing the transaction-handling program, the project operated several nondestructive assay instruments in a glovebox environment, specifically the electronic balance, solution assay instrument, and thermal-neutron coincidence counter. From the instrument operation logs, project personnel were able to identify operational problems and incorporate design changes in the instrumentation for the new facility.
Date: February 1, 1978
Creator: Augustson, R.H.
Object Type: Report
System: The UNT Digital Library
Pacific Northwest Laboratory annual report for 1977 to the DOE Assistant Secretary for Environment. Part 5. Control technology, overview, health, safety and policy analysis (open access)

Pacific Northwest Laboratory annual report for 1977 to the DOE Assistant Secretary for Environment. Part 5. Control technology, overview, health, safety and policy analysis

Separate abstracts were prepared for seven sections of this report. A list is included of publications during the period covered.
Date: February 1, 1978
Creator: Bair, W.J.
Object Type: Report
System: The UNT Digital Library
High temperature molten carbonate fuel cells (open access)

High temperature molten carbonate fuel cells

Progress is reported on four tasks: (1) component development, (2) cell testing, (3) stack design and development, and (4) modeling and systems analysis. A hydrogen sintering furnace capable of producing 0.5 sq meter electrodes was installed and operating procedures are being established. To develop stabilized anode structures, a fine particle nickel-cobalt alloy powder was prepared from their hydroxide mixture through the steps of co-precipitation, spray-drying and reduction. Electrodes have been produced for small cell tests using this high surface area alloy powder. The in situ method of electrolyte preparation was studied in detail to establish the effect of various thermal treatments and to optimize the reagent processing and mixing techniques. DTA and TGA analysis were performed for the reaction mixture. Procedures were developed for the separate controlled syntheses of ..cap alpha..-..beta..-..gamma..-lithium aluminates. Metal fiber reinforced tiles were fabricated with fibers of different diameters, lengths and loadings. Equipment has been assembled to conduct potentiostatic corrosion tests on candidate materials for the cell frame and current collector. Efforts were directed towards improving anode and cathode structures, corrosion protection, wet seal efficiency, cell hardware design and thermal cycling capabilities. A steady performance has been achieved for 1300 hours, with the test continuing. (WHK)
Date: February 1, 1978
Creator: Baker, B.; Burns, D.; Dharia, D.; Herscovici, C.; Kinnibrugh, D.; Paetsch, L. et al.
Object Type: Report
System: The UNT Digital Library
Nondestructive evaluation of LWR spent fuel shipping casks (open access)

Nondestructive evaluation of LWR spent fuel shipping casks

An analysis of nondestructive testing (NDT) methods currently being used to evaluate the integrity of Light Water Reactor (LWR) spent fuel shipping casks is presented. An assessment of anticipated NDT needs related to breeder reactor cask requirements is included. Specific R and D approaches to probable NDT problem areas such as the evaluation of austenitic stainless steel weldments are outlined.
Date: February 1, 1978
Creator: Ballard, D. W.
Object Type: Article
System: The UNT Digital Library
Nondestructive evaluation of LWR spent fuel shipping casks (open access)

Nondestructive evaluation of LWR spent fuel shipping casks

An analysis of nondestructve testing (NDT) methods currently being used to evaluate the integrity of Light Water Reactor (LWR) spent fuel shipping casks is presented. An assessment of anticipated NDT needs related to breeder reactor cask requirements is included. Specific R and D approaches to probable NDT problem areas such as the evaluation of austenitic stainless steel weldments are outlined. A comprehensive bibliography of current NDT methods for cask evaluation in the USA, Great Britain, Japan and West Germany was compiled for this study.
Date: February 1, 1978
Creator: Ballard, D.W.
Object Type: Report
System: The UNT Digital Library
Steam generator tube denting simulation testing. [PWR] (open access)

Steam generator tube denting simulation testing. [PWR]

Tube denting has been reported in steam generators in a number of commercial nuclear power plants in recent years. In order to aid in understanding of the mechanism leading to tube denting in the steam generators, a Bettis laboratory test program was initiated to attempt to reproduce tube denting and to investigate the effects of chemistry, design, and temperature. The results of the tests indicate that denting can be reproduced in the small model steam generator test apparatus devised for this testing. Denting was observed under carbon steel support plates in seawater-contaminated secondary water in a test with hydrazine-ammonia chemistry and a primary water inlet temperature of 590/sup 0/F and in a test with hydrazine-morpholine chemistry and a primary water inlet temperature of 545/sup 0/F. The parameters of these two tests simulate conditions in a typical commercial steam generator and the Shippingport Atomic Power Station steam generators, respectively.
Date: February 1978
Creator: Battaglia, P. J. & Singley, W. J.
Object Type: Report
System: The UNT Digital Library
Investigative study of engine limiting (open access)

Investigative study of engine limiting

An experimental study was conducted to determine the effect of cylinder cut-out or ''engine limiting'' on fuel consumption and exhaust emissions for a current technology V-type 8-cylinder engine. Increases in energy conversion efficiency while operating with only 4 cylinders ranged from 10 to 40% compared to operation with 8 cylinders at the same power outputs. The speeds and loads chosen were representative of those required to operate a 4,500-lb vehicle at speeds up to 60 mph. Hydrocarbon emissions increased at low speed/load points under 4 cylinder operation. An insignificant change in carbon monoxide emissions was observed while an increase in oxides of nitrogen emissions resulted at the higher speed/load points.
Date: February 1, 1978
Creator: Bechtold, R.L.
Object Type: Report
System: The UNT Digital Library
Geostatistics project of the National Uranium Resource Evaluation program (open access)

Geostatistics project of the National Uranium Resource Evaluation program

Additional work has been done to display radiometric data from the Lubbock quadrangle in pseudocolor maps. A digitized topographic map of the quadrangle was obtained from the U.S. Geological Survey and this is being incorporated into the study of the radiometric data. Single-record data from the Lake Mead calibration range and from the Slayton test line have been obtained from GeoMETRICS: Inc. and analysis of this data has begun. Principal component analyses have been used to investigate the relationship of geological formation to the location of points in a (Tl, Bi, K) coordinate system. LASL personnel attended a workshop in Grand Junction, Colorado, where some of the problems of calibrating aerial gamma-ray spectrometers were addressed.
Date: February 1, 1978
Creator: Bement, T.R.; McKay, M.D. & Wecksung, G.W.
Object Type: Report
System: The UNT Digital Library
SCORE-EVET: a computer code for the multidimensional transient thermal-hydraulic analysis of nuclear fuel rod arrays. [BWR; PWR] (open access)

SCORE-EVET: a computer code for the multidimensional transient thermal-hydraulic analysis of nuclear fuel rod arrays. [BWR; PWR]

The SCORE-EVET code was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code ocntains: (a) a one-dimensional steady state solution scheme to initialize the flow field, (b) steady state and transient fuel rod conduction models, and (c) comprehensive correlation packages to describe fluid-to-fuel rod interfacial energy and momentum exchange. Velocity and pressure boundary conditions can be specified as a function of time and space to model reactor transient conditions such as a hypothesized loss-of-coolant accident (LOCA) or flow blockage.
Date: February 1, 1978
Creator: Benedetti, R. L.; Lords, L. V. & Kiser, D. M.
Object Type: Report
System: The UNT Digital Library
Recent Developments in the Sesame Equation-of-State Library (open access)

Recent Developments in the Sesame Equation-of-State Library

The Sesame Library is a computer file of tabular equations of state and other material properties, developed in Group T-4 of the Los Alamos Scientific Laboratory. This report describes some of the theoretical models used in the library, the structure of the data storage and acquisition system, and the computer routines that were developed to access and use the tables in practical applications. It also discusses how non-LASL users can obtain the Sesame data and subroutine libraries.
Date: February 1, 1978
Creator: Bennett, B. I.; Johnson, J. D.; Kerley, G. I. & Rood, G. T.
Object Type: Report
System: The UNT Digital Library
Capital requirements for energy sector: capital market access. The shift to successful efforts accounting: preliminary review of probable effects on oil and gas industry participants (open access)

Capital requirements for energy sector: capital market access. The shift to successful efforts accounting: preliminary review of probable effects on oil and gas industry participants

This report provides an initial assessment of the effects that the adoption of uniform successful efforts accounting might have on access to capital markets and investment behavior in the oil and gas industry. It also proposes a plan of interviews and analysis which would permit informed revision and expansion of that initial assessment. Section II presents a discussion of the origins and current status of the controversy between advocates of successful efforts and full cost accounting. An important underpinning of the argument in favor of uniform successful efforts accounting is the premise that all industry participants are fundamentally comparable and, thus, should be subject to uniform accounting treatment. Section III questions this premise by examining the various classes of industry participants. Section IV presents data on the roles of those classes of industry participants, paying particular attention to the importance of the independents in the exploration phase of the business. Section V discusses the effects which a shift to uniform successful efforts accounting might have on the various industry participants. A discussion of our initial conclusions are presented in Section VI. Section VII reviews a plan of interviews and analysis which would permit a more informed evaluation of policy options. …
Date: February 1, 1978
Creator: Bennett, V.
Object Type: Report
System: The UNT Digital Library
CHILES 2: a finite element computer program that calculates the intensities of linear elastic singularities in isotropic and orthotropic materials (open access)

CHILES 2: a finite element computer program that calculates the intensities of linear elastic singularities in isotropic and orthotropic materials

CHILES 2 is a finite-element computer program that calculates the strength of singularities in linear elastic bodies. A generalized quadrilateral finite element that includes a singular point at a corner node is incorporated in the code. The displacement formulation is used and interelement compatibility is maintained so that monotone convergence is preserved. Plane stress, plane strain, and axisymmetric conditions are treated. Isotropic and orthotropic crack tip singularity problems are solved by this version of the code, but any type of singularity may be properly modeled by modifying selected subroutines in the program.
Date: February 1, 1978
Creator: Benzley, S.E. & Beisinger, Z.E.
Object Type: Report
System: The UNT Digital Library