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Environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada; Volume 1

Description: In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high- level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guideline for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EA), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as of five sites suitable for characterization.
Date: May 1, 1986
Partner: UNT Libraries Government Documents Department

Environmental assessment: Yucca Mountain Site, Nevada Research and Development Area, Nevada; Volume 2

Description: In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EAs), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that is is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as one of five sites suitable for characterization.
Date: May 1, 1986
Partner: UNT Libraries Government Documents Department

Cost estimate of initial SSC experimental equipment

Description: The cost of the initial detector complement at recently constructed colliding beam facilities (or at those under construction) has been a significant fraction of the cost of the accelerator complex. Because of the complexity of large modern-day detectors, the time-scale for their design and construction is comparable to the time-scale needed for accelerator design and construction. For these reasons it is appropriate to estimate the cost of the anticipated detector complement in parallel with the cost estimates of the collider itself. The fundamental difficulty with this procedure is that, whereas a firm conceptual design of the collider does exist, comparable information is unavailable for the detectors. Traditionally, these have been built by the high energy physics user community according to their perception of the key scientific problems that need to be addressed. The role of the accelerator laboratory in that process has involved technical and managerial coordination and the allocation of running time and local facilities among the proposed experiments. It seems proper that the basic spirit of experimentation reflecting the scientific judgment of the community should be preserved at the SSC. Furthermore, the formal process of initiation of detector proposals can only start once the SSC has been approved as a construction project and a formal laboratory administration put in place. Thus an ad hoc mechanism had to be created to estimate the range of potential detector needs, potential detector costs, and associated computing equipment.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Thermal impact on host rock of geologic repository; Final report

Description: The initial stress of rock was estimated and analyzed based on the geological survey information collected during the site visits. Change in stress and its distribution in the rock due to excavation was investigated and predicted according to the repository geometry. Thermal effects on the magnitude and distribution of stress in rock was also investigated and predicted according to the repository geometry. Thermal effects on the magnitude and distribution of rock stresses were investigated under two different temperature conditions. Emphasis was placed on the development of fractures due to stress concentration at or near the repository openings. Permeability characteristics of host rock were evaluated at three temperature levels. Series of permeability tests were conducted for determining the thermal effect on the hydrological characteristics of rock. The following goals were achieved from this investigation: (1) Better understanding of stress changes in host rock due to repository excavation and thermal impact. (2) Better understanding of the development of rock fractures and its effect on the hydrological characteristics of host rock. (3) To provide the technical information obtained from this study to the Office of Civilian Radioactive Wastes Management (OCRWM) with a hope that it may assist OCRWM in the decision making of selecting a repository site. Due to limited time for this research, only one type of host media, granite, was included in the study.
Date: March 1, 1986
Creator: Mou, Ching-Hua
Partner: UNT Libraries Government Documents Department

Environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada; Volume 3

Description: In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EAs), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as one of five sites suitable for characterization.
Date: May 1, 1986
Partner: UNT Libraries Government Documents Department

Field study of disposed wastes from advanced coal process. Quarterly technical progress report, August--October, 1986 (final report)

Description: The Department of Energy/Morgantown Energy Technology Center (DOE/METC) has initiated research on the disposal of solid wastes from advanced coal processes. The objective of this research is to develop information to be used by private industry and government agencies for planning waste disposal practices associated with advanced coal processes. To accomplish this objective. DOE has contracted Radian Corporation and the North Dakota Mining and Minerals Resources Research Institute (MMRRI) to design, construct and monitor a limited number of field disposal tests with select advanced coal process wastes. These field tests will be monitored aver a three year period with the emphasis on collecting data on the field disposal behavior of these wastes. Objectives for the third quarter (and into October) were as follows: formalize the basis for the test designs; select design options; prepare a draft of the Test Design Manual; and initiate work on the Test Procedures Manual. The accomplishments under each task are described.
Date: November 20, 1986
Partner: UNT Libraries Government Documents Department

Environmental assessment overview, Yucca Mountain site, Nevada Research and Development Area, Nevada

Description: In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guidelines for the Recommendations of Sites for the Nuclear Waste Repositories. On the basis of the evaluations reported in this EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as one of five sites suitable for characterization. 3 figs.
Date: May 1, 1986
Partner: UNT Libraries Government Documents Department

Final report on the use of the modular-logic-nomenclature approach for the N-reactor probabilistic risk assessment

Description: The N-Reactor probabilistic risk assessment adaption of the modular logic approach for fault tree modeling has led to the update of the master logic diagram (MLD) nomenclature to conform with a standard modular-logic-model-nomeclature format. This report describes the MLD nomenclature system and provides a listing of the updated MLD label codes, along with the original codes.
Date: June 10, 1986
Partner: UNT Libraries Government Documents Department

Remedial action plan for stabilization of the inactive uranium mill tailings site at Monument Valley, Arizona

Description: This Remedial Action Plan (RAP) has been developed to serve a two-fold purpose. It presents the series of activities which are proposed by the U.S. Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at the inactive uranium processing site located near Monument Valley, Arizona It also serves to document the concurrence of both the Navajo Nation and the U.S. Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by DOE and the Navajo Nation and concurrence by NRC, becomes Appendix B of the Cooperative Agreement.
Date: February 1, 1986
Partner: UNT Libraries Government Documents Department

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

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

Report on policy and activities concerning public awareness of health effects of low-level radiation

Description: In the summer of 1986, the Executive Committee authorized a study limited to determining policy and practices relevant to dissemination of information to the public on radiation health effects in three federal agencies. This report summarizes findings on two broad questions related to the communication issue: What, if any, are the policies under which federal agencies operate in disseminating information on health effects of radiation and what are the current programs and activities designed to provide the public information on health effects of radiation.
Date: November 1, 1986
Partner: UNT Libraries Government Documents Department

Reports of Jupiter II: Measurements and analysis

Description: This report provides the reaction rate measurements and analyses and the basic data for reaction rate measurements for ZPPR-13C in: The high [sup 240]Pu zone of ZPPR-13C; The high-heavy-metal-volume- fraction zone;The pin zone; The [sup 235]U fuel zone; and the enriched uranium zone. In-cell reaction rate measurements and cell factors for the zone studies in ZPPR Assembly 13C are provided.
Date: December 31, 1986
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

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

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

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

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

Angular distribution of power from an undulator and a wiggler on a 6-GeV storage ring

Description: There are two fundamental reasons to have a full knowledge of the angular distribution of power from an insertion device: 1. To evaluate the heat-load distribution on the first optical element in a beamline. 2. To estimate the total radiated power which will impinge on the walls of an insertion device. This is important to ensure needed cooling of the insertion device walls. The photodesorption is another closely related phenomenon determined by the exposure of the insertion device walls to the radiated power and of consequence to the successful operation of the storage ring. In this paper, we will primarily focus on undulators, but also consider situations as the value of K increases to the wiggler regime. These calculations are very involved and cumbersome and we shall only present some specific results related to the 6-GeV insertion devices.
Date: February 1, 1986
Creator: Shenoy, G.K.
Partner: UNT Libraries Government Documents Department

Specifications for the JASPER Program attenuation experiment

Description: An integral shielding experiment has been designed to investigate neutron penetration through benchmark and representative mockups of the radial shield designs for advanced sodium-cooled reactor concepts. The experiment will be performed in FY 1986 at the ORNL Tower Shielding Facility to study neutron penetration through various combinations of graphite, boron carbide, and steel configurations using representative near-core and sodium-pool source spectra. Detailed configuration descriptions and measurement specifications for the experiment are included.
Date: 1986
Creator: Engle, W. W., Jr.; Ingersoll, D. T.; Slater, C. O. & Mukenthaler, F. J.
Partner: UNT Libraries Government Documents Department

Cornell undulator/summary of discussions

Description: Based on an earlier statement made by CESR (during the meeting in March 1986 at Cornell) that the ring energy can be 6-GeV and the minimum gap can be 0.9 cm, we performed design calculations for the Cornell undulator. These are presented and briefly summaried in this report.
Date: August 5, 1986
Creator: Shenoy, G. & Viccaro, J.
Partner: UNT Libraries Government Documents Department

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

Description: The Circulating Water System is a subsystem within the Heat Rejection Group (HRG). The Circulating Water System consists of two independent loops to remove waste heat from the turbine building closed cooling water system and from the condensers associated with each turbine generator set. In normal plant operation circulating water is pumped from the cooling tower basin through the condensers and heat exchangers and back to the cooling tower where the waste heat is released to the atmosphere via mechanical draft cooling towers. The system consists of two flow paths with two half-size, vertical pumps associated with each path.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department