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78
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47
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Status of beta- and gamma-decay and spontaneous-fission data from transactinium isotopes
Several categories of ..beta..- and ..gamma..-related decay data for the transactinium isotopes are assessed in the light of their potential use in applied areas. The status as of August, 1975, of these data is summarized for 142 transactinium nuclides with 228 less than or equal to A less than or equal to 257 by the listing of experimental values and errors where known. Several useful compilations of transactinium-isotope decay data are discussed. Recent developments related to the yields and energy distributions of prompt and delayed neutrons from spontaneous fission are briefly treated. Comments and observations about the interrelation of the important nuclear-data activities of measurement, compilation and evaluation and needs assessment are given. The applications-oriented file of decay data prepared at our laboratory for ENDF/B is discussed. Finally, a summary by G. Rudstam of the status of the OSIRIS work on delayed-neutron energy spectra of individual precursors is included.
Date:
April 1, 1976
Creator:
Reich, C. W.
Object Type:
Report
System:
The UNT Digital Library
Final report on investigation of stability of organic materials in salt cake
On the basis of this work the following conclusions, which all contribute to confidence that salt cake is stable against exothermic reactions, were reached. Organics added to the waste tanks were not nitrated at the time of addition and cannot have been subsequently transformed to detonatable nitrated organics. Whatever organic has found its way into the tanks has been and will be essentially unaffected by radiation. Mixtures of the types of organics which could have been added to the waste tanks with either simulated salt cake or pure sodium nitrate are not detonatable. The maximum amount of organic which could have been added to the waste tanks is less than 0.9 weight percent of the salt cake, a concentration far below the concentration required to support combustion. The many years during which the liquid high-level waste was boiling, and the subsequent evaporation-crystallization processing, have allowed many of the more volatile organics to be distilled off, further reducing the maximum expected concentration of organics. The occurrence of an explosive exothermic reaction of an organic in the waste tanks would require concentration and mixing by an unknown and uncontrolled means. The mixture would then have to remain in its concentrated state long …
Date:
April 1, 1976
Creator:
Beitel, G. A.
Object Type:
Report
System:
The UNT Digital Library
Research and Engineering Division semiannual report, KK process development and technology, May 1, 1975--October 31, 1975
This document represents the second of a series reporting on a semiannual basis the activities supported by KK funds in the areas of process development. These research and engineering activities have the goal of improving the performance of the plutonium processing and waste management programs being operated by the Atlantic Richfield Hanford Company.
Date:
April 1, 1976
Creator:
Fox, R. D. & Manry, C. W. (eds.)
Object Type:
Report
System:
The UNT Digital Library
Cold regions isotope applications
Pacific Northwest Laboratories (PNL) started the Cold Regions Isotope Applications Program in FY-1975 to identify special conditions in the Arctic and similar geographic areas (Cold Regions) where radioisotope power, heater, or sterilization systems would be desirable and economically viable. Significant progress was made in the first year of this program and all objectives for this initial 12-month period were achieved. The major conclusions and recommendations resulting for this effort are described below. The areas of interest covered include: radiosterilization of sewage; heating of septic tanks; and radioisotope thermoelectric generators as power sources for meteorological instruments and navigational aids. (TFD)
Date:
April 1, 1976
Creator:
Perrigo, L. D. & Divine, T. E.
Object Type:
Report
System:
The UNT Digital Library
TRUEX hot demonstration
In FY 1987, a program was initiated to demonstrate technology for recovering transuranic (TRU) elements from defense wastes. This hot demonstration was to be carried out with solution from the dissolution of irradiated fuels. This recovery would be accomplished with both PUREX and TRUEX solvent extraction processes. Work planned for this program included preparation of a shielded-cell facility for the receipt and storage of spent fuel from commercial power reactors, dissolution of this fuel, operation of a PUREX process to produce specific feeds for the TRUEX process, operation of a TRUEX process to remove residual actinide elements from PUREX process raffinates, and processing and disposal of waste and product streams. This report documents the work completed in planning and starting up this program. It is meant to serve as a guide for anyone planning similar demonstrations of TRUEX or other solvent extraction processing in a shielded-cell facility.
Date:
April 1, 1990
Creator:
Chamberlain, D. B.; Leonard, R. A.; Hoh, J. C.; Gay, E. C.; Kalina, D. G. & Vandegrift, G. F.
Object Type:
Report
System:
The UNT Digital Library
Study of the effects of radiation of nucleic acids and related compounds. Progress report, August 15, 1975--August 14, 1976
Ionizing radiation produces genetic effects in biological systems. Since genetic effects are usually the result of modifications of DNA or sometimes of RNA, interest is being centered on the chemical and physical nature of radiation-induced lesions to nucleic acids and their components. These investigations have revealed the enormous complexity of chemical events and the possible degradation of nucleic acids by strand breakage. Therefore, work in the ionization radiation of nucleic acids has proceeded along a dual course. On the one hand, molecular changes have been characterized for a number of primary radiation products. On the other hand, strand breakage has been investigated intensively as a direct primary event. Both of these aspects were emphasized in our research last year. We succeeded in improving the synthesis of 5-hydroxy-methyl thymine (..cap alpha..-TOOH). ..cap alpha..-TOOH was found to be much more effective than cis-5,6-dihydro-6-hydroperoxy-5-hydroxy thymine (6-TOOH) in the inactivation of transforming DNA of H. influenzae cells although ..cap alpha..-TOOH is much less reactive chemically than 6-TOOH. 6-TOOH causes inactivation and acts as an inhibitor of DNA synthesis in mammalian cells. In addition, evidence may indicate that 6-TOOH does not induce strand breaks directly in DNA although we showed that 6-TOOH is a clastogenic …
Date:
April 1, 1976
Creator:
Wang, S. Y.
Object Type:
Report
System:
The UNT Digital Library
Simple method to unfold NE 213 and stilbene neutron spectral data
A very simple method is proposed wherein recoil proton scintillation data are reduced using the derivative unfolding technique. The approximations described require minimal calculation or storage and may be readily implemented on a mini computer. A digital filter is incorporated which yields a smoothed approximation to the slope of the pulse-height distribution, with error estimates. In order to accurately represent the scintillator light output without introducing discontinuities in the unfolded spectrum, the light output data are fitted using B-splines whose first and second derivatives are continuous.
Date:
April 1, 1976
Creator:
Slaughter, D. R.
Object Type:
Article
System:
The UNT Digital Library
Physical protection of nuclear facilities quarterly progress report, October--December 1976
Activities included the preparation of presentations for the NRC review committee. Also, a draft program plan on the Protection of Nuclear Materials for both fixed facilities and in-transit systems was submitted to the NRC. Other activities have focused primarily on the development of evaluation methodologies. These efforts have included the development of a computer graphics implementation of EASI (Estimate of Adversary Sequence Interruption), engagement model developments, ISEM (Insider Safeguards Effectiveness Model) documentation, pathing algorithm improvements, and facility characterization methodology improvements. A large effort has been expended in defining and interfacing with possible contractual support involvements. Areas of these involvements include a generic safeguards data base, fault tree analysis techniques, physical protection modeling, human attribute definitions, neutralization modeling, and safeguards network symbology models.
Date:
April 1, 1977
Creator:
Chapman, L. D. (ed.)
Object Type:
Report
System:
The UNT Digital Library
Effects of fueling profiles on plasma transport
A one-dimensional (1-D), multifluid transport model is used to investigate the effects of particle fueling profiles on plasma transport in an ignition-sized tokamak (TNS). Normal diffusive properties of plasmas will likely maintain the density at the center of the discharge even if no active fueling is provided there. This significantly relaxes the requirements for fuel penetration. Not only is lower fuel penetration easier to achieve, but it may have the advantage of reducing or eliminating density gradient-driven trapped particle microinstabilities. Simulation of discrete pellet fueling indicates that relatively low velocity (approximately 10/sup 3/ m/sec) pellets may be sufficient to fuel a TNS-sized device (approximately 1.25-m minor radius), to produce a relatively broad, cool edge region of plasma which should reduce the potential for sputtering, and also to reduce the likelihood of trapped particle mode dominated transport. Low penetrating pellets containing up to 10 to 20 percent of the total plasma ions can produce fluctuations in density and temperature at the plasma edge, but the pressure profile and fusion alpha production remain almost constant.
Date:
April 1, 1978
Creator:
Mense, A. T.; Houlberg, W. A.; Attenberger, S. E. & Milora, S. L.
Object Type:
Report
System:
The UNT Digital Library
NACHOS: a finite element computer program for incompressible flow problems. Part I. Theoretical background
The theoretical background for the finite element computer program, NACHOS, is presented in detail. The NACHOS code is designed for the two-dimensional analysis of viscous incompressible fluid flows, including the effects of heat transfer. A general description of the fluid/thermal boundary value problems treated by the program is described. The finite element method and the associated numerical methods used in the NACHOS code are also presented. Instructions for use of the program are documented in SAND77-1334.
Date:
April 1, 1978
Creator:
Gartling, D. K.
Object Type:
Report
System:
The UNT Digital Library
Kernel migration for HTGR fuels from the Th--U--C--O--N system
Nuclear fuels for the high-temperature gas-cooled reactor (HTGR) consist of spherical kernels of actinide compounds contained within gastight pyrolytic carbon and SiC. This fuel is subjected to a significant in-reactor temperature gradient that leads to migration of the fuel kernel up the temperature gradient and into the coating layers. This phenomenon has been studied both in the laboratory and in-reactor for fuel kernels from the Th-U-C-O-N system. Application of theory to the analysis of in-reactor migration data indicates that a solid-state diffusion process operating across the kernel controls the migration rate in fissioned Th/sub 0/./sub 84/U/sub 0/./sub 16/C/sub 2/, UO/sub 2/, ThO/sub 2/, and Th/sub 0/./sub 8/U/sub 0/./sub 2/O/sub 2/ particles. The theoretically-based kernel migration coefficient (KMC), (cm/sec) /sup 0/K/sup 2/ (/sup 0/K/cm)/sup -1/, is thus used to correlate the data. The in-reactor KMC values were apparently not dependent on the extent of fission, the fission of either /sup 233/U or /sup 235/U, or the presence of a SiC coating layer. Laboratory KMC values were obtained from unirradiated dicarbide particles; these values were in excellent agreement with previously published laboratory KMC data and did not appear to be inconsistent with in-reactor dicarbide KMC values. Laboratory KMC values for ThO/sub 2/ …
Date:
April 1, 1976
Creator:
Lindemer, T. B. & Pearson, R. L.
Object Type:
Report
System:
The UNT Digital Library
Integration of the three-dimensional Vlasov equation for a magnetized plasma
A second order splitting scheme is developed to integrate the three dimensional Vlasov equation for a plasma in a magnetic field. The integration of the Vlasov equation is divided into a series of intermediate steps and Fourier interpolation and the ASD method with a third order Taylor expansion are used to integrate the fractional equations. Numerical experiments related to cyclotron waves in 2 and 2/sup 1///sub 2/ D are demonstrated with high accuracy and efficiency. The computer storage requirements are modest; for example, a typical 2D nonlinear electron plasma simulation requires only 4000 ''particles.''
Date:
April 1, 1976
Creator:
Cheng, C Z
Object Type:
Report
System:
The UNT Digital Library
Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol 11, No. 1 through Vol. 16, No. 6
This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970) through Vol. 16, No. 6 (Nov.-Dec. 1975). Included in the index is a chronological list of articles (including abstract) followed by both a KWIC index and an Author Index. Nuclear Safety is a bimonthly technical progress review prepared by the Nuclear Safety Information Center and covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 300 technical articles in the last six years of publication.
Date:
April 1, 1976
Creator:
Cottrell, W. B. & Klein, A.
Object Type:
Report
System:
The UNT Digital Library
Analytical and experimental study of instabilities in buoyancy-driven convection in porous media
During the second year of support under the DOE grant, significant progress was made in two directions: (1) Visualization of structure and tow field in randomly packed beds via Magnetic Resonance Imaging, and (2) Shadowgraphic visualization of natural convection in porous systems. This report describes the activities in detail, cite publications which resulted from this project, and conclude with plans for the last phase of the experimental investigation.
Date:
April 1, 1992
Creator:
Georgiadis, J. G.; Behringer, R. & Johnson, G. A.
Object Type:
Report
System:
The UNT Digital Library
Engine testing of ceramic cam-roller followers
For several years, DDC has been developing monolithic ceramic heat engine components. One of the components, developed for an application in our state-of-the-art on-highway, heavy-duty diesel engine, the Series 60, is a silicon nitride cam-roller follower. Prior to starting this program, each valve train component in the Series 60 was considered for conversion to a ceramic material. Many advantages and disadvantages (benefits and risks) were considered. From this effort, one component was selected, the cam-roller follower. Using a system design approach, a ceramic cam-roller follower offered functional improvement at a reasonable cost. The purpose of the project was to inspect and test 100 domestically produced silicon nitride cam-roller followers built to the requirements of the DDC series 60 engine.
Date:
April 1, 1992
Creator:
Kalish, Y. (Detroit Diesel Corp., MI (United States))
Object Type:
Report
System:
The UNT Digital Library
Measurement of the elastic modulus of Kapton perpendicular to the plane of the film at room and cryogenic temperatures
Understanding the short term elastic properties, (i.e. the instantaneous modulus) of Kapton is essential in determining the loss of prestress during storage and operation of SSC dipole magnets. The magnet prestress contributes directly to the coil response to the Lorentz forces during ramping. The instantaneous modulus is important in extrapolating short term stress relaxation data to longer times. Most theoretical fits assume a time independent component and a time dependent component. The former may be represented by the Kapton modulus near zero K where all relaxation processes have been frozen'' out. Modulus measurements at 77K and 4.2K may point to a correct value for the near zero K modulus. Three companion papers presented at this conference will be: Stress Relaxation in SSC 50 mm Dipole Coils'' Temperature Dependence of the Viscoelastic Properties of SSC Coil Insulation (Kapton)'' Theoretical Methods for Creep and Stress Relaxation Studies of SSC Coil.''
Date:
April 1, 1992
Creator:
Davidson, M.; Bastian, S. & Markley, F.
Object Type:
Article
System:
The UNT Digital Library
Nuclear safeguards research. Program status report. Progress report, September--December 1975
This report presents the status of the Nondestructive Assay R and D program of the LASL Nuclear Safeguards Research Group, R-1, covering the period September-December 1975. It covers: holdup measurements at the Kerr-McGee Pu facility at Crescent, Okla.; calculations for Random Driver; instrument development and measurement controls; ERDA nondestructive assay training program; and in-plant dynamic materials control (DYMAC) program. 22 figures, 5 tables. (DLC)
Date:
April 1, 1976
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Engineering feasibility evaluation of a peristaltic pinch
A recent proposal for reducing the end loss of a linear theta pinch is to produce moving magnetic mirrors at the coil ends. The concept entails the sequential pulsing of an axially arranged series of two-turn coaxial coils. The electrical design of such a system presents some unique problems. Ideally, the individual pulse circuits should be completely independent. This would facilitate the design by eliminating interactive effects. In practice, the circuits must be interconnected through isolating inductors to enable the production of a uniform biasing magnetic field. Moreover, the coils must be located physically close together. This produces strong magnetic coupling between the pulse circuits, which can seriously affect the shape and speed of the inward-moving magnetic-mirror field. Possible systems were modeled for the NET-2 circuit analysis code. The models took account of the inductive coupling between the individual circuits in the model. The results show that an increasing magnetic mirror can be produced provided the radius of the theta pinch is not too great compared to the intercoil spacing. The peristaltic field can be maintained for several cycles in the inner coils. The voltage hold-off requirements on the pulse circuit switches are found to be severe, but not impossible …
Date:
April 1, 1977
Creator:
Boicourt, G. P.
Object Type:
Report
System:
The UNT Digital Library
Research in theoretical physics. Annual report, September 1, 1975--August 31, 1976. [Summaries of research activities at Johns Hopkins University]
Results are reported on an algebraic approach to the quark problem, strong coupling approximation to field theories and, spontaneous symmetry breaking in the presence of gravitation. A supersymmetry albebra was constructed which obeys triality exactly and allows for separate conservation of lepton and baryon numbers. The existence of higher lying color singlet states is predicted. Investigations into a perturbation expansion around a strong coupling (''independent valued'') limit of field theories were completed. The result is a generalized classical field theory with correct clustering properties; unitarity is satisfied at the tree diagram level. Vacuum solutions to conformal relativity were found, exhibiting spontaneous symmetry breaking. A ''second Higgs mechanism'' was discovered; as a consequence, scalar mesons are removed from the theory altogether. Significance of the results from the point of view of quark confinement and some cosmological consequences are discussed.
Date:
April 1, 1976
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Neutral-beam design options. [Design and cost optimization]
The designs and costs of magnetic-confinement experimental devices and reactors can be affected strongly by the choice of parameters for the neutral-beam injection system. To provide the designer with information with which to estimate the physical and cost consequences of variations in energy, neutralizer thickness, ion-species mixtures, etc., we are carrying out parametric studies of the neutralization efficiency. Some of the results are reported here. The data base is too small and uncertain to permit calculations which would optimize all aspects of designs at this time.
Date:
April 1, 1976
Creator:
Stearns, J. W.; Berkner, K. H. & Pyle, R. V.
Object Type:
Article
System:
The UNT Digital Library
Aerosol sampling and characterization for hazard evaluation. Progress report, July 1, 1975--September 30, 1976. [Pu aerosols]
A draft Manual of Recommended Practice for Aerosol Sampling and Evaluation was completed and sent to the Energy Research and Development Administration (ERDA) Division of Safety, Standards, and Compliance (DSSC) for review. The results of the Survey of Sampling Techniques for Defining Respirable Concentration and/or Particle Size Characteristics of Aerosols were published as LA-6087. The need for greater standardization of ERDA aerosol sampling techniques was indicated. The Aerosol Training Course was presented in 11 sessions to 85 persons. General elements of good practice were emphasized, and recommendation of specific sampling devices or procedures was avoided. A system for estimating dissolution rates of plutonium aerosols was developed. Studies indicate that plutonium aerosols found in the field have a rapid initial dissolution phase followed by a slower secondary phase. Three methods of particle sizing air samples collected on membrane filters were investigated. The most promising was a scanning electron microscope electron microprobe (SEM-EMp) method. An operating plutonium handling facility was a model for development of techniques to evaluate aerosol surveillance systems performance. Airborne contamination records were studied. The physicochemical properties of a plutonium aerosol existing in the facility were investigated in relation to plutonium handling operations. The techniques developed have indicated some …
Date:
April 1, 1977
Creator:
Scripsick, R. C.; Gray, D. C.; Tillery, M. I.; Stafford, R. G. & Romero, P. O.
Object Type:
Report
System:
The UNT Digital Library
Commercial scale demonstration enhanced oil recovery by miceller-polymer flooding. M-1 project: facilities report
ERDA and Marathon Oil Company contracted together for a commercial scale demonstration of enhanced oil recovery by the Maraflood (TM) oil recovery process. This M-1 Project is located within Sections 15, 16, 21 and 22, T6N, R13W, Crawford County, Illinois, encompassing approximately 407 acres of Robinson Sand reservoir developed in the first decade of the century. The area covers portions of several waterfloods developed on 10-acre spacing in the 1950's that were approaching their economic limit. This report describes all M-1 Project facilities, how they were prepared or constructed, their purpose and how they operate: (1) wells (drilling and completion); (2) production facility; (3) injection facility; and (4) various service systems required during project development and/or operation. (48 fig, 7 tables) (DLC).
Date:
April 1, 1977
Creator:
Knight, B. L.
Object Type:
Report
System:
The UNT Digital Library
Infrared analysis techniques for oil identification
None
Date:
April 1, 1977
Creator:
Grizzle, P. L. & Coleman, H. J.
Object Type:
Report
System:
The UNT Digital Library
Molten salt blanket calculations for a tokamak fusion-fission hybrid reactor
Several possible blanket designs for use in a tokamak fusion-fission hybrid reactor are investigated. The main constituent of the blanket is a molten salt, possibly with a separate convertor region for multiplication of the source neutrons. Both the thorium and uranium fuel cycles are analyzed subject to constraints on the blanket performance such as high blanket energy multiplication and sufficient breeding of tritium and fissile fuel. It is found that the behavior depends strongly on the salt composition through the ratios of fertile material to fissile material and lithium to fissile material. It is also very important to have multiplication of the high energy source neutrons in a convertor zone between the plasma and the salt. Ways of optimizing this neutron multiplication through variations in the convertor zone composition and thickness are investigated.
Date:
April 1, 1976
Creator:
Chapin, D. L.
Object Type:
Report
System:
The UNT Digital Library