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Tritium handling in vacuum systems

Description: This report provides a course in Tritium handling in vacuum systems. Topics presented are: Properties of Tritium; Tritium compatibility of materials; Tritium-compatible vacuum equipment; and Tritium waste treatment.
Date: October 1, 1986
Creator: Gill, J.T. & Coffin, D.O.
Partner: UNT Libraries Government Documents Department

Liquid radioactive waste subsystem design description

Description: The Liquid Radioactive Waste Subsystem provides a reliable system to safely control liquid waste radiation and to collect, process, and dispose of all radioactive liquid waste without impairing plant operation. Liquid waste is stored in radwaste receiver tanks and is processed through demineralizers and temporarily stored in test tanks prior to sampling and discharge. Radwastes unsuitable for discharge are transferred to the Solid Radwaste System.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Class 1E dc power subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: The Class 1E DC Power System of the Electrical Group provides reliable and regulated 125 V dc electric power to the plant safety-related dc loads connected to the Four redundant and independent 125 V dc Class 1E buses to ensure plant safe shutdown or mitigate the effects of a design basis event. These four dc buses comprise the plant four Class 1E dc control and instrument channels (A, B, C and D).
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Pressure relief subsystem design description

Description: The primary function of the Pressure Relief Subsystem, a subsystem of the Vessel System, is to provide overpressure protection to the Vessel System. When the overpressure setpoint is reached, pressure is reduced by permitting the flow of primary coolant out of the Vessel System. This subsystem also provides the flow path by which purified helium is returned to the vessel system, either as circulating purge/flow from the Helium Purification Subsystem or make-up helium from the Helium Storage and Transfer Subsystem.
Date: July 1, 1986
Partner: UNT Libraries Government Documents Department

Guidance for UMTRA project surveillance and maintenance

Description: The Guidance for UMTRA Project Surveillance and Maintenance describes the procedures that will be used to verify that Uranium Mill Tailings Remedial Action (UMTRA) Project disposal sites continue to function as designed. The approach of this guidance document is to identify surveillance requirements and maintenance procedures that will be used to comply with NRC license requirements. This document addresses five primary activities: Definition and characterization of final site conditions. Site inspections; Ground-water monitoring; Aerial photography; and Custodial maintenance and contingency repair. Final site conditions will be defined and characterized prior to the completion of remedial actions at a site. As-built drawings will be compiled, a final topographic survey will be performed, a vicinity map will be prepared, and ground and aerial photographs will be taken. Survey monuments, site markers, and signs will be established as will a network of monitoring wells.
Date: January 1, 1986
Partner: UNT Libraries Government Documents Department

Probabilistic risk assessment of the modular HTGR plant. Revision 1

Description: A preliminary probabilistic risk assessment (PRA) has been performed for the modular HTGR (MHTGR). This PRA is preliminary in the context that although it updates the PRA issued earlier to include a wider spectrum of events for Licensing Basis Events (LBE) selection, the final version will not be issued until later. The primary function of the assessment was to assure compliance with the NRC interim safety goals imposed by the top-level regulatory criteria, and utility/user requirements regarding public evacuation or sheltering. In addition, the assessment provides a basis for designer feedback regarding reliability allocations and barrier retention requirements as well as providing a basis for the selection of licensing basis events (LBEs) and the safety classification of structures, systems, and components. The assessment demonstrates that both the NRC interim safety goals and utility/user imposed sheltering/evacuation requirements are satisfied. Moreover, it is not anticipated that design changes introduced will jeopardize compliance with the interim safety goals or utility/user requirements. 61 refs., 48 figs., 24 tabs.
Date: June 1, 1986
Creator: Everline, C.J.; Bellis, E.A. & Vasquez, J.
Partner: UNT Libraries Government Documents Department

Liquid Metal Reactor Program: JASPER USDOE/PNC Shielding Research Program: Technical progress report, August 1-September 30, 1986

Description: This report details activities on the JASPER Shielding Program for the time period of August 1, 1986 through September 30, 1986. This report contains the measurements in phases VI and VII, a graphite benchmark study and an alternate loop type shield design study for the Liquid Metal Reactor (LMR), respectively. This report also includes the results of analyses for phases I, II, III, V, and VI.
Date: December 31, 1986
Creator: Ingersoll, D.T.; Engle, W.W. Jr.; Muckenthaler, F.J. & Slater, C.O.
Partner: UNT Libraries Government Documents Department

350 MW(t) design fuel cycle selection. Revision 1

Description: This document discusses the results of this evaluation and a recommendation to retain the graded fuel cycle in which one-half of the fuel elements are exchanged at each refueling. This recommendation is based on the better performance of the graded cycle relative to the evaluation criteria of both economics and control margin. A choice to retain the graded cycle and a power density of 5.9 MW/m{sup 3} for the upcoming conceptual design phase was deemed prudent for the following reasons: the graded cycle has significantly better economics, and essentially the same expected availability factor as the batch design, when both are evaluated against the same requirements, including water ingress; and the reduction in maximum fuel pin power peaking in the batch design compared to the graded cycle is only a few percent and gas hot streaks are not improved by changing to a batch cycle. The preliminary 2-D power distribution studies for both designs showed that maximum fuel pin power peaking, particularly near the inner reflector, was high for both designs and nearly the same in magnitude. 10 figs., 9 tabs.
Date: January 1986
Creator: Lane, R. K.; Lefler, W. & Shirley, G.
Partner: UNT Libraries Government Documents Department

Defect fractions for fissile and fertile TRISO-coated fuel

Description: High quality TRISCO-coated UCO and ThO{sub 2} particles with reference MHTGR dimensions were produced in a coating campaign in August and September 1986 for irradiation tests. The heavy metal contamination and the defect levels were below the limits established for the MHTGR fuel. Over 9 kg of uranium in UCO and 30 kg of thorium in ThO{sub 2} were TRISCO-coated in 4 fissile and 3 fertile batches in the 240mm Development Coater. These coated fuel particles will be used to produce fuel rods for testing in the irradiation validation tests to be conducted in capsules HRB-19, -20 and -21 on the DOE Fuel and Fission Product Technology Program. 3 refs., 6 figs., 6 tabs.
Date: September 1, 1986
Creator: Adams, C.C.
Partner: UNT Libraries Government Documents Department

Superlattice optical elements

Description: The performance of state-of-the-art Layered Synthetic Microstructures (LSM) or superlattices at x-ray energies even exceeding the soft x- ray domain is a promising sign that systems of this type may play an important role as x-ray optical elements in the energy region of interest to 6-GeV users. As will be discussed in this paper, they are particularly attractive because of their large energy bandpass compared to crystals such as Si of Ge. In fact, they have been suggested recently as elements in high throughput large bandpass x- ray monochromators tunable in the interval of 5-30 keV. For high flux applications, the hope is that LSM will prove to be stable in intense photon beams enabling them to filter out most of the heat load that will reach narrow bandpass crystal optical elements. A concurrent requirement is that their reflectivity in the x-ray region be large enough so that the gain in the bandpass will not be offset by and overall loss in flux. The effectiveness of these devices as optical elements will depend on optimization of the reflectivities of LSM through adequate design optimization modeling and fabrication techniques.
Date: March 1, 1986
Creator: Viccaro, P.J. & Ziegler, E.
Partner: UNT Libraries Government Documents Department

Advanced secondary recovery project for the Sooner D Sand Unit, Weld County, Colorado: Final report

Description: The objective of this project was to increase production at the Sooner D Sand Unit through geologically targeted infill drilling and improved reservoir management of waterflood operations. The Sooner D Sand Unit demonstration project should be an example for other operators to follow for reservoir characterization and exploitation methodologies to increase production by waterflood from the Cretaceous D Sandstone in the Denver-Julesburg (D-J) Basin. This project involved multi-disciplinary reservoir characterization using high-density 3D seismic, detailed stratigraphy and reservoir simulation studies. Infill drilling, water-injection conversion and re-completing some wells to add short-radius laterals were based on the results of the reservoir characterization studies. Production response were evaluated using reservoir simulation and production tests. Technology transfer utilized workshops, presentations and technical papers which emphasized the economic advantages of implementing the demonstrated technologies.
Date: June 1, 1986
Creator: Sippel, M.A. & Cammon, T.J.
Partner: UNT Libraries Government Documents Department

Security monitoring subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: Security Monitoring acquires and processes sensor data for use by security personnel in the performance of their function. Security Monitoring is designed and implemented as a part of an overall security plan which is classified as Safeguards Information under 10CFR73.21.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Nd-Fe-B undulator design for CESR

Description: It is proposed to build a Nd-Fe-B based undulator on CESR ring which would provide pseudomonochromatic tunable radiation in the hard x-ray range from 4 to 15 keV. Such an intense radiation source opens unlimited possibilities for doing exciting science in material science and condensed matter physics. Here, we present the design goals for such an undulator and discuss the influence of various parameters that govern the properties of radiation from undulators. The analysis of these results leads us to select the specific design parameters of the undulator that will meet the radiation needs of the experimental program.
Date: October 14, 1986
Creator: Shenoy, G.K.; Viccaro, P.J. & Kim, S.
Partner: UNT Libraries Government Documents Department

Subsurface geology of the A and M areas at the Savannah River Plant, Aiken, South Carolina

Description: A study of the subsurface geology of A and M areas at the Savannah River Plant was begun in the summer of 1984 with the establishing of a sedimentological laboratory at Building 704-U. Here, core samples, recovered during the drilling of selected A and M area monitoring wells, were examined by trained geologists under the supervision of Dr. W. C. Fallaw. This project was continued during the summer of 1985. The results of these studies were used, along with available borehole geophysics, to delineate the subsurface geology. This report is based on these investigations. The sedimentological data obtained are summarized by monitor well as a lithologic log and are presented along with the borehole geophysics in the Appendix. The geological interpretation is presented in the forms of structure contour maps, isopach maps, and cross-sections. The study is limited to existing data from A and M areas, and the interpretation may change as additional data become available.
Date: June 1, 1986
Creator: Fallaw, W.C. & Sargent, K.A.
Partner: UNT Libraries Government Documents Department

Enthalpies of combustion of four N-phenylmethylene benzenamine N-oxide derivatives, of N-phenylmethylene benzenamine, and of trans-diphenyldiazene N-oxide: the dissociation enthalpy of the (N-O) bonds

Description: Article on enthalpies of combustion of four N-phenylmethylene benzenamine N-oxide derivatives, of N-phenylmethylene benzenamine, and of trans-diphenyldiazene N-oxide and the dissociation enthalpy of the (N-O) bonds.
Date: August 1, 1986
Creator: Kirchner, James J.; Acree, William E. (William Eugene); Pilcher, Geoffrey & Shaofeng, Li
Partner: UNT College of Arts and Sciences

Evaluation of the effectiveness of the M-Area extraction system

Description: The effect of the M-Area extraction system on groundwater flow patterns in the vicinity of the M-Area was investigated using the groundwater flow model of the A- and M-Areas developed by S. S. Papadopulos and Associates, Inc. The purpose of this investigation was 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, and (2) evaluate the length of time required to remove groundwater from the capture zones of the extraction wells. The effectiveness 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. If the groundwater flow paths to the extraction wells encompass the zones containing the chemicals of concern, the extraction system, if operated long enough, will prevent migration of the chemicals from the M-Area. The time required to reduce the concentrations of the chemicals of concern, the nature of the source of the chemicals, and the interaction of the chemicals with the groundwater environment. This investigation focused on the patterns of groundwater velocity created by the extraction systems, the zones of capture for the extraction wells, and the rate of groundwater evacuation from the capture zones.
Date: July 1, 1986
Creator: Jackson, D.
Partner: UNT Libraries Government Documents Department

6 GeV synchrotron x-ray source: Conceptual design report. Supplement A - characteristics of the insertion devices for the 6 GeV synchrotron source

Description: Historically, synchrotron radiation (SR) has been obtained primarily from bending-magnet (BM) sources. These continuous sources of electromagnetic radiation have contributed in a major way to our understanding of the structure and dynamics of biological, chemical and material systems. During the past few years, newer sources of SR based on sophisticated periodic magnetic structures, called insertion devices (IDs), have been developed. The electromagnetic radiation from these IDs can be used as a very versatile probe in scientific and technological research which is far superior to that based on a BM source.
Date: March 1, 1986
Partner: UNT Libraries Government Documents Department

Research in chemical kinetics. Annual report

Description: Accomplishments to date are described for the four projects which make up this investigation. The project titles are: (1) photochemistry of phosphine as studied by FTIR spectroscopy; (2) photolytic studies with radioactive tracers; (3) heterogeneous atmospheric reactions; and (4) reactions of tritium, {sup 38}Cl and {sup 18}F from nuclear recoil. Details of the study and results are presented for the first two projects.
Date: December 31, 1986
Creator: Rowland, F. S.
Partner: UNT Libraries Government Documents Department

Magnetic Fustion Reactor Design Studies Program final report, 1 July 1986--30 September 1986

Description: This report presents progress reported during the period, 7/1/86 - 9/30/86 for the Technical Support Services (TSS) for the Magnetic Fusion Reactor Design Studies Program. Tasks reported include: systems studies work plan, normalization of reactor design studies, interpretation of design study activities, research and development plan, conference support, and reports generated.
Date: September 30, 1986
Partner: UNT Libraries Government Documents Department

Maintenance building structural design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: The Maintenance Building is a grade-founded, two-story, steel-framed structure, located adjacent to the Turbine Building in the Energy Conversion Area. It has a reinforced concrete foundation and slab on grade, and insulated sheet metal exterior walls and roof decking.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

HVAC [Heating, Ventilation and Air Conditioning] subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: The HVAC system is a subsystem within the Mechanical Services Group (MSG). The HVAC system for the 4 x 350 MW(t) Modular HTGR Plant presently consists of ten, nonsafety-related subsystems located in the Nuclear Island (NI) and Energy Conversion Area (ECA) of the plant.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department