6,354 Matching Results

Search Results

Summary Report on Transport of Contaminants in the Subsurface: The Role of Organic and Inorganic Colloidal Particles

Description: A meeting on ''Transport of Contaminants in the Subsurface: Role of Organic and Colloidal Materials'' was held on October 5-9, 1986, in Manteo, North Carolina. The meeting was part of the series of International Seminars on the Subsurface held by the Subsurface Transport Program o f the Office of Health and Environmental Research of the U.S. Department of Energy. The meeting was organized by Frank Wobber (OHER/DOE) and John McCarthy (Oak Ridge National Laboratory). The purpose of the meeting was to review current knowledge about the role played by colloids on the mobility of contaminants in the subsurface environment, and to identify important long-term research needs in this area. Participants included senior researchers in this field from national laboratories, government agencies, universities, and research institutes in four countries. Recent findings on the occurrence and nature of colloidal material in the subsurface as well as on the association of colloids with organic, metal, and radionuclide contaminants were presented and discussed. Field studies have demonstrated that colloidal particles do move through aquifers and that radionuclides have been transported much further than predicted due to their association with mobile colloids in the groundwater. The consensus of the meeting was that colloids do occur in the subsurface environment, are capable of binding organic and inorganic contaminants, and do alter the mobility of Contaminants. A major difficulty in understanding and predicting the role of colloids is their heterogeneous nature that hampers precise chemical characterization. Clay and metal oxide colloids can be formed or dissolved due to changes in solution chemistry in the aquifer. Organic colloids have variable and diverse functional groups, making it difficult to predict their association with metal and radionuclide contaminants Some important advances were reported toward understanding the assembly of organic colloids and the nature of their interactions with organic contaminants. Major ...
Date: January 1, 1987
Creator: McCarthy, J.F.
Partner: UNT Libraries Government Documents Department

Evaluation of Energy-Related Inventions Program: An Empirical Analysis of 204 Inventions

Description: This report is an evaluation of the Energy-Related Inventions Program (ERIP). It assesses the program's effectiveness and impacts, characterizes participating inventions and inventors, and identifies correlates of successful commercialization in order to suggest possible improvements. Seventy of the 204 ERIP inventions that were studied were successfully introduced into the market, accounting for more than $200M in sales from 1976 through 1984. During 1984, 921 full-time equivalent employees were supported directly by ERIP inventors or their licensees. (Estimates of indirect economic impacts are also contained in the report.) Data on patterns of fund raising clearly show a need for assistance by programs like ERIP. Commercially successful inventors shared several traits. They had less formal education, fewer patents, more work experience in small firms, more outside funding early in their work, more shared responsibility with others for invention development, more management experience, and greater previous experience with starting new businesses. Recommendations are made regarding: (1) priorities for allocating ERIP grants; (2) improved efficiency of the NBS/DOE operations; (3) delivery of technical and commercialization assistance to grant recipients; and (4) further evaluation research.
Date: January 1, 1987
Creator: Brown, M.A.
Partner: UNT Libraries Government Documents Department

Report of the task force on radioactivation

Description: Estimates have been made of the residual radioactivation of the components of the SSC accelerator and detector complex. Such activation is caused by the loss of a small fraction of the proton beams being transported in the SSC accelerator system, by deliberate removal (dumping) of the beams and by particles created in the proton-proton collisions in the SSC storage rings. Existing methodology that has been successfully used to determine activation levels at other accelerator facilities has also been used to estimate the activation of SSC components in those cases where calculational methods may be applied. In addition, we have used measurements from existing accelerators, primarily the Fermilab and CERN accelerators, to provide the means to estimate activation for those cases in which calculational methods, such as Monte Carlo shower codes, are difficult to apply. We have also used these measurements to check the calculations from the shower codes where possible. We have estimated activation levels and dose rates, where possible, for the following components of the SSC: The abort dumps for both the storage rings and the elements of the injector system; beam Collimators and scrapers; magnets and other apparatus in the region of injection/extraction from one accelerator to another, target stations used to create test beams from the high energy booster; superconducting magnets in the high energy booster and the storage rings; and representative detector elements. We also briefly discuss aspects of handling or dismantling the components most significantly activated and the relevance to decommissioning of the SSC complex. A short description of the decommissioning of the Intersecting Storage Rings at CERN, the only pp collider that has been decommissioned, is included in this report.
Date: October 1, 1987
Partner: UNT Libraries Government Documents Department

Development of a synthetic fuel reciprocating charge pump. Quarterly technical progress report for the period of: 1 January 1987--31 March 1987

Description: This report covers the third quarter of the third phase of the reciprocating charge pump improvement program. The program was begun in 1982 for the purpose of improving the operating life of packings and plungers used in 300 psig, 300F coal/solvent slurry pumps employed in synthetic fuel generating plants. The testing to be performed during this phase has been modified since the last quarterly report. This test measured the effects of slurry migration past the floating piston seal and the time to wear the packing and plunger beyond the acceptable limit. Table 1 summarizes all testing to date, 456 hours total at this time with 72 hours on 35% slurry. It denotes the valve problems seen with rapid pressure decay when pumping slurry. Throughout this time, 33 specific and different equipment failures and operation problems occurred that delayed the testing.
Date: December 31, 1987
Creator: Bonney, G.E.
Partner: UNT Libraries Government Documents Department

Safety Analysis Report for Packaging (SARP): Models AL-M3 and AL-M6 nuclear packaging (DOE C of C No. USA/5790/BLF and No. USA/5791/BLF)

Description: This revised Safety Analysis Report for Packaging (SARP) satisfies the requirement of the US Department of Energy (DOE) for an updated formal safety analysis of the two insulated drum shipping containers identified as USA/5790/BLF and USA/5791/BLF. The report makes available to all potential users the technical information and limits pertinent to the construction and use of the shipping containers. This SARP includes discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. Complete physical and technical descriptions of the packages are presented. Each package consists of a cylindrical steel inner container centered within an insulating steel drum assembly. The contents may be any radioactive materials that satisfy the requirements established in this SARP. A shipment of plutonium-238 in the form of a solid oxide is evaluated in this SARP as an example. Design and development considerations, the tests and evaluations required to prove the ability of the containers to withstand normal transportation conditions, and the sequence of four hypothetical accident conditions (free drop, puncture, thermal, and water immersion) are discussed. Tables, graphs, dimensional sketches, photographs, technical references, loading and shipping procedures, Mound Facility experience in using the containers, and copies of the DOE Certificates of Compliance are included.
Date: November 24, 1987
Creator: Coleman, H.L.; Whitney, M.A.; Williams, M.A.; Alexander, B.M. & Shapiro, A.
Partner: UNT Libraries Government Documents Department

Global orbit corrections

Description: There are various reasons for preferring local (e.g., three bump) orbit correction methods to global corrections. One is the difficulty of solving the mN equations for the required mN correcting bumps, where N is the number of superperiods and m is the number of bumps per superperiod. The latter is not a valid reason for avoiding global corrections, since, we can take advantage of the superperiod symmetry to reduce the mN simultaneous equations to N separate problems, each involving only m simultaneous equations. Previously, I have shown how to solve the general problem when the machine contains unknown magnet errors of known probability distribution; we made measurements of known precision of the orbit displacements at a set of points, and we wish to apply correcting bumps to minimize the weighted rms orbit deviations. In this report, we will consider two simpler problems, using similar methods. We consider the case when we make M beam position measurements per superperiod, and we wish to apply an equal number M of orbit correcting bumps to reduce the measured position errors to zero. We also consider the problem when the number of correcting bumps is less than the number of measurements, and we wish to minimize the weighted rms position errors. We will see that the latter problem involves solving equations of a different form, but involving the same matrices as the former problem.
Date: November 1, 1987
Creator: Symon, K.
Partner: UNT Libraries Government Documents Department

ZPPR progress report: August 1987-October 1987

Description: This progress report details activities during the time period of August through October, 1987. Results are presented from the axially heterogeneous assembly ZPPR-17, a part of the Jupiter-III program. The loading of the ZPPR-17B assembly, with 25 control rod positions, is described along with operational measurements, calculation models, measurements and predictions of criticality and measured axial worth profiles for B[sub 4]C. From ZPPR-17A, calculated and measured results are given for banks of control rod positions along with revised measured values for various single, central control rods.
Date: November 16, 1987
Creator: Brumbach, S.B. & Collins, P.J.
Partner: UNT Libraries Government Documents Department

Core fluctuations test. Revision 1

Description: Fluctuations were first encountered in the Fort St. Vrain reactor early in cycle 1 operation, during the initial rise from 40% to 70% power. Subsequent in-core tests and operation throughout cycles 1 and 2 demonstrated that fluctuations were repeatable, occurring at core pressure drops of between 2.5 psi and 4.0 psi, and that in each instance their characteristics were very similar. Subsequently, tests and analysis were done to understand the core fluctuation phenomenon. These efforts also lead to a design fix which stopped these fluctuations in the FSV reactor core. This fix required that keys be used in addition to the keys in the core support floor which already existed. This report outlines a test plan to validate that core fluctuations will not occur in the MHTGR core. 2 refs., 12 figs., 3 tabs.
Date: June 1, 1987
Creator: Betts, W.S.
Partner: UNT Libraries Government Documents Department

Preliminary thoughts on the Aladdin experiments

Description: The author suggests three sets of experiments for comparing tracking results with experimental data on the dynamic aperture in Aladdin. They are: (1) aperture determined by a single dominant resonance; (2) dominance by a group of intersecting resonances; and (3) many non-intersecting resonances. Note that one advantage of the suggested experiments is that one can inject, accelerate, and get set for the experiment, and then excite the driving terms slowly, watching the aperture.
Date: November 1, 1987
Creator: Symon, K.
Partner: UNT Libraries Government Documents Department

Vessel support subsystem design description. Revision 1

Description: The Vessel Support Subsystem is one of three subsystems comprising the Vessel System of the Modular High Temperature Gas-Cooled Reactor 4 x 350 MW(t) Plant. The design of this subsystem has been developed by means of the Integrated Approach. This document establishes the functions and system design requirements of the Vessel Support Subsystem from the Functional Analysis, and includes institutional requirements from the Overall Plant Design Specification and the Vessel System Design Description. A description of the subsystem design which satisfies these requirements is presented. Lower-tier requirements at the subsystem level are next defined for the component design. This document also includes information on aspects of subsystem construction, operation, maintenance, and decommissioning.
Date: July 1, 1987
Creator: Perry, R.A. & Mehta, D.D.
Partner: UNT Libraries Government Documents Department

TMI-2 core bore acquisition summary report

Description: Core bore samples were obtained from the severely damaged TMI-2 core during July and August, 1986. A description of the TMI-2 core bore drilling unit used to obtain samples; a summary and discussion of the data from the ten core bore segments which were obtained; and the initial results of analysis and evaluation of these data are presented in this report. The impact of the major findings relative to our understanding of the accident scenario is also discussed.
Date: February 1, 1987
Creator: Tolman, E.L.; Smith, R.P.; Martin, M.R.; McCardell, R.K. & Broughton, J.M.
Partner: UNT Libraries Government Documents Department

Design data needs modular high-temperature gas-cooled reactor. Revision 2

Description: The Design Data Needs (DDNs) provide summary statements for program management, of the designer`s need for experimental data to confirm or validate assumptions made in the design. These assumptions were developed using the Integrated Approach and are tabulated in the Functional Analysis Report. These assumptions were also necessary in the analyses or trade studies (A/TS) to develop selections of hardware design or design requirements. Each DDN includes statements providing traceability to the function and the associated assumption that requires the need.
Date: March 1, 1987
Partner: UNT Libraries Government Documents Department

Helium Storage and Transfer Subsystem design description. Revision

Description: The Helium Storage and Transfer Subsystem (HSTS) consists of two parts. The first consists of nine (9) high pressure storage tanks containing helium at 15.6 MPa (2250 psig). These tanks provide makeup and purge helium at a rate of 1216 kg per y (2680 lb/y) to the various helium users, including circulator bearing seals, analysis packages, and cooling system surge tanks. The second, larger part of the system, provides for the low pressure storage of 6078 kg (13,400 lb) of primary coolant helium in 180 storage tanks at 7.0 MPa (1000 psig). The system serves all four (4) reactor modules. The low pressure storage part of the system receives helium from the discharge of Helium Purification Subsystem (HPS) and is activated during depressurization and pumpup operations only. It is not required to operate continuously. Storage capacity is provided for primary helium coolant from two reactor modules. However, since depressurization and pumpup operations are performed for only one reactor module at a time, two 50% capacity low pressure transfer compressors are provided having a total transfer capacity of 340 am{sup 3}/h (200 acfm) which is sufficient to service one module. High pressure helium is supplied continuously to all the four reactor modules simultaneously from the high pressure storage tanks. These tanks are replaced periodically with fresh tanks.
Date: July 1, 1987
Partner: UNT Libraries Government Documents Department

Evaluation of the effectiveness of the M-Area extraction system September 1985 to October 1986

Description: A groundwater extraction system designed to remove volatile organic compounds from groundwater has been in operation in the M-Area at the Savannah river Plant since September 1985. This extraction system has been operated at a rate of approximately 410 gallons per minute during the past year, and about 55,000 lbs of volatile organic compounds have been removed from groundwater during the first year of operation. The Raw Materials Engineering and Technology Department at the Savannah River Plant is currently evaluating the operation of the extraction system. In support of the effort, S. S. Papadopulos and Associates, Inc. was requested to: (1) evaluate the performance of the extraction system in terms of its capability to prevent migration of volatile organic chemicals from the M-Area; (2) evaluate the length of time required to remove groundwater from the capture zones of the extraction wells; (3) evaluate long-term effects of the extraction system; and (4) evaluate alternative extraction strategies. The performance of the groundwater extraction system was evaluated by calculating where the groundwater that is pumped from the extraction system enters the groundwater table as recharge, and by calculating the flow paths and travel times for this groundwater from the recharge area to the extraction wells. The groundwater flow paths that end in the extraction wells encompass the volume of groundwater captured by the extraction system.
Date: March 1, 1987
Creator: Jackson, D.
Partner: UNT Libraries Government Documents Department

Special Operations Forces (SOF) technical analysis and evaluation

Description: In response to Task Order 001, Los Alamos National Laboratory Contract 9-L5H-1508P-1, Betac Corporation is pleased to provide ten quick-response, short-term analytical papers in support of Low Intensity Conflict (LIC) and Special Operations (SO). The papers are study methodologies which provide background, baseline, concepts, approaches, and recommendations in the mission areas identified in the Statement of Work. Although the Statement of Work specifies only nine papers, a tenth paper has been included addressing Command Relationships, since this subject affects all other topics and is of critical importance to USCINCSOC in establishing the United States Special Operations Command (USSOCOM). Each paper addresses the feasibility of further effort in each area of interest. The ten papers address: (1) mission support systems; (2) research, development, and acquisition; (3) headquarters equipment; (4) C3I architecture; (5) intelligence dissemination; (6) intelligence collection management; (7) intelligence support to SOF targeting; (8) joint mission area analysis (JMAA); (9) joint SOF master plan; and (10) command relationships.
Date: August 31, 1987
Partner: UNT Libraries Government Documents Department

Radiation effects and annealing kinetics in crystalline silicates, phosphates and complex Nb-Ta-Ti oxides. FInal Report

Description: Interaction of heavy particles (alpha-recoil nuclei, fission fragments, implanted ions) with ceramics is complex because they have a wide range of structure types, complex compositions and chemical bonding is variable. Radiation damage can produce diverse results, but most commonly, crystalline periodic materials become either polycrystalline or aperiodic (metamict state). We studied the transition from crystalline to aperiodic state in natural materials that have been damaged by alpha recoil nuclei in the U and Th decay series and in synthetic, analogous structure types which have been amorphized by ion implantation. Transition from crystalline to aperiodic was followed by analysis of XRD, high resolution TEM, and EXAFS/XANE spectroscopy. Use of these techniques with increasing dose provided data on an increasing finer scale as the damage process progressed.
Date: August 10, 1987
Creator: Ewing, R.C.
Partner: UNT Libraries Government Documents Department

Centrifugal slurry pump wear and hydraulic studies. Quarterly technical progress report for the period of 1 April 1987--30 June 1987

Description: This report marks the fourth quarter of the third phase of the centrifugal slurry pump improvement program. The program was begun in 1982 to improve the operating life of centrifugal slurry pumps for coal liquefaction service. The first phase reviewed pilot plant experience with centrifugal slurry pumps and identified, with the help of a literature search, the critical design parameters and materials required for such improvement. The second phase encompassed extensive small-scale testing of several hydraulic design concepts and materials testing and selection - the results being incorporated in a prototype slurry pump design. This third phase of the work has included i) prototype slurry pump testing against a state-of-the-art coal liquefaction slurry pump, wherein substantial reduction of wear was obtained at 60% higher speed at the same head and flow rate therefore at 60% higher specific speed - and ii) an investigation as to whether still higher specific speed is possible. The prototype pump tested in (i) had a specific speed of 600. Another pump of this same design was re-fitted for investigation (ii) with a smaller impeller and associated liners so as to operate at a specific speed of 1000. Both the 600 and the 1000 impellers for this latter investigation (ii) were made of mild carbon steel to accelerate the testing time. The two pumps were run in series in the slurry test loop using AS {number_sign}110 sand ({approximately} 110 mesh) at a concentration of 30% by weight in water at 80{degrees}F. As previously reported, 24 hours of test time revealed a slightly lower overall wear rate for the 1000-specific-speed pump; however, excessive local wear occurred in the impeller eye area of that pump. This was attributed to too large a clearance between the pump-out vanes and the suction side of the volute liner. Wear elsewhere in ...
Date: December 31, 1987
Creator: Cooper, P
Partner: UNT Libraries Government Documents Department

Stanford Synchrotron Radiation Laboratory activity report for 1986

Description: 1986 was another year of major advances for SSRL as the ultimate capabilities of PEP as a synchrotron radiation source became more apparent and a second PEP beam line was initiated, while effective development and utilization of SPEAR proceeded. Given these various PEP developments, SSRL abandoned its plans for a separate diffraction limited ring, as they abandoned their plans for a 6--7 GeV ring of the APS type last year. It has become increasingly apparent that SSRL should concentrate on developing SPEAR and PEP as synchrotron radiation sources. Consequently, initial planning for a 3 GeV booster synchrotron injector for SPEAR was performed in 1986, with a proposal to the Department of Energy resulting. As described in Chapter 2, the New Rings Group and the Machine Physics Group were combined into one Accelerator Physics Group. This group is focusing mainly on the improvement of SPEAR`s operating conditions and on planning for the conversion of PEP into a fourth generation x-ray source. Considerable emphasis is also being given to the training of accelerator physics graduate students. At the same time, several improvements of SSRL`s existing facilities were made. These are described in Chapter 3. Chapter 4 describes new SSRL beam lines being commissioned. Chapter 5 discusses SSRL`s present construction projects. Chapter 6 discusses a number of projects presently underway in the engineering division. Chapter 7 describes SSRL`s advisory panels while Chapter 8 discusses SSRL`s overall organization. Chapter 9 describes the experimental progress reports.
Date: December 31, 1987
Creator: Cantwell, K.
Partner: UNT Libraries Government Documents Department

Solubility in Binary Solvent Systems: 8. Estimation of Binary Alkane plus p-Dioxane Solvent Nonideality from Measured Anthracene Solubilities

Description: Article on solubility in binary solvent systems and the estimation of binary alkane plus p-dioxane solvent nonideality from measured anthracene solubilities.
Date: August 1, 1987
Creator: Procyk, Alexander D.; Bissell, Margaret; Street, Kenneth W. & Acree, William E. (William Eugene)
Partner: UNT College of Arts and Sciences

Bifunctional chelates of Rh-105 and Au-199 as potential radiotherapeutic agents

Description: Since last year we have (1) Investigated the production of Rh-105 by the Szilard-Chalmers process using Ru(acac){sub 3} targets, (2) Synthesized several new ligands and their rhodium complexes, (3) Done preliminary studies of the radiochemical properties of some of these complexes of Rh-105 at 10{sup -4} -10{sup -3} M concentration, and (4) Done preliminary animal studies on one of the complexes.
Date: August 31, 1987
Creator: Troutner, D.E. & Schlemper, E.O.
Partner: UNT Libraries Government Documents Department

Evaluation of need for integral fuel oxidation tests

Description: This document establishes the need for an integral fuel oxidation test which can give confidence to the predictions made by the OXIDE computer code for fuel and core damage during water ingress events in the Modular High Temperature Gas Cooled Reactor (MHTGR). This testing will provide clear engineering evidence to demonstrate that the core of the MHTGR can survive a moisture ingress incident with minimum investment risk and without danger to the reactor personnel or to the public. In particular, these tests will determine the degree of particle debonding and compact stack densification as a function of the fractional compact matrix burnoff. Also included in the document is a description of the proposed tests, and, a test matrix of the planned experiments. 3 refs., 1 fig., 1 tab.
Date: February 1, 1987
Creator: Montgomery, F.C.
Partner: UNT Libraries Government Documents Department

Shielding estimates for the ANL advanced photon source

Description: Shielding estimates for the Advanced Photon Source (APS) have been computed utilizing presently available design parameters. Calculations of the resulting radiation fields have been made for several considerations involving normal beam loss, as well as for certain postulated accidental beam losses. Whenever available, experimental data from existing accelerators and light sources have been used in lieu of theoretical estimates.
Date: April 1, 1987
Creator: Moe, H.J. & Veluri, V.R.
Partner: UNT Libraries Government Documents Department

Site fuel handling subsystem design description. Revision

Description: The Site Fuel Handling Subsystem (SFHS) consists of equipment and facilities located in the reactor Service Building which are used to handle hexagonal graphite fuel and reflector blocks. This equipment interfaces closely with the core refueling equipment. The SFHS uses some of the equipment in the Core Refueling System to transfer fuel elements between the spent fuel storage facility (part of Core Refueling Subsystem, HFD-43413) and the fuel sealing and inspection facility (FSIF).
Date: July 1, 1987
Partner: UNT Libraries Government Documents Department

Hot Service Facility subsystem design description. Revision

Description: The Hot Service Facility Subsystem, which is also referred to as the Reactor Equipment Service Facility (RESF), is located in an environmentally controlled shielded vault and provides inspection, maintenance, care, and repair of reactor service equipment and tools. The shielded vault is located in the Reactor Service Building.
Date: July 1, 1987
Partner: UNT Libraries Government Documents Department