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ANL analysis of ZPPR-13A

Description: The ZPPR-13 experiments provide basic physics data for radial heterogeneous LMFBR cores of approximately 700MWe size. Assemblies ZPPR-13A, ZPPR-13B and ZPPR-13C comprised the JUPITER-II cooperative program between the U.S. Department of Energy (US DOE) and PNC of Japan. The measurements were made between August 1982 and April 1984. The core designs and the measurements were planned jointly by the two parties with substantial input from U.S. industrial interests to ensure coverage of the design requirements. This report describes in detail the results of the Argonne National Laboratory (ANL) analyses of phase 13A.
Date: August 9, 1984
Creator: Collins, P.J. & Brumbach, S.B.
Partner: UNT Libraries Government Documents Department

A STUDY OF FISCHER 344 RATS EXPOSED TO SILICA DUST FOR SIX MONTHS AT CONCENTRATIONS OF 0, 2, 10 OR 20 MG / M3.

Description: The major objective of this study was to relate the results of a series of functional tests to the compositional and structural alterations in the rat lung induced by subchronic exposure to silica dust. Fischer-344 rats were exposed for 6 hours/day, 5 days/week for 6 months to either 0, 2, 10, or 20 mg SiO{sub 2}/m{sup 3}. The general appearance of the exposed rats was not different from that of the controls. Interestingly, female rats exposed to silica dust, at all tested concentrations, gained more weight than the controls. The lung weight and the lung-to-body weight ratio was greater in the male rats exposed to the highest concentration of silica dust.
Date: February 1, 1984
Creator: KUTZMAN,R.S.
Partner: UNT Libraries Government Documents Department

Manganese Availability - Market Economy Countries: A Minerals Availability Program Appraisal

Description: Report issued by the U.S. Bureau of Mines discussing the worldwide availability of manganese. As stated in the introduction, "the purpose of this report is to evaluate selected domestic and market economy country resources of manganese for metallurgical application. Individual mine and deposit evaluations were performed on the basis of tonnage, grade, and cost of production" (p. 2). This report includes tables, illustrations, and a map.
Date: 1984
Creator: Coffman, Joseph S. & Palencia, Cesar M.
Partner: UNT Libraries Government Documents Department

Preliminary design parameters of 6 GeV storage ring lattice for Synchrotron Light Source

Description: In this note, we describe a design of lattice, which is by no means optimized for the ultimate performance, but these parameters can be used for the starting point of other design efforts. Assumptions and features used in this design are: (1) 32 periods which is reasonably high periodicity for chromaticity corrections. (2) Achromatic bending cell which enables us to make all straight sections to be dispersion free. (3) Twiss parameters at dispersion area are the same for all cells to make undulator straight section can be tuned to wiggler straight section a-id vice versa. (4) No attempt is made to extract the photon beam from bending magnets, and when this feature is added, the lattice design may have to be changed in order to provide-the photon beam channel. (5) Natural emittance in the horizontal plane is made as small as possible in the range of 10-8m radians. This value can be optimized later by judicious choice of the Twiss parameters through the bending magnets. (6) The bending magnet should have parallel edges in order to simplify its construction. This assumption implies that there is vertical focussing from the edge. (7) The beta functions at the straight section should be tunable so that various configurations of the insertion devices should be accommodated.
Date: October 15, 1984
Creator: Cho, Y.
Partner: UNT Libraries Government Documents Department

Light source job list and plan: Part 1

Description: This note is intended to describe our current thinking and to show interconnections of various subtasks. The discussed topics are: (1) Storage Ring Group - A. Refinement of lattices to include: photons from bending magnets, dynamic aperture studies, refinement of accelerator physics straight section, B. Non-standard lattice, C. Touschek lifetime, D. Gas scattering lifetime, E. BBI (bunched beam instabilities), F. Magnet error considerations, G. tracking of particles, H. Orthogonal adjustments of beam positions and angles, (2) Injector Group, (3) Linac Group, (4) RF Group, (5) Alignment and stability, (6) Technical Components, (7) Vacuum, (8) Diagnostics, and (9) Control System.
Date: October 29, 1984
Creator: Cho, Y.
Partner: UNT Libraries Government Documents Department

The geology and hydrogeology of Bear Creek Valley Waste Disposal Areas A and B

Description: A study was undertaken of the Oil Landfarm and Burial Grounds A and B, which are three disposal sites within the Bear Creek Waste Disposal Area. The area is located west of the Y-12 plant, about 3 miles southwest of Oak Ridge, Tennessee. The purpose of this interim report is to present data collected at the Burial Grounds A and B, and to provide the results of hydrogeologic analyses. The Oil Landfarm geologic and hydrogeologic data and analyses have been submitted in a January 1984 interim report. The overall objectives of the study were to characterize the types and extent of wastes present and to define the occurrence and movement of ground water beneath the sites. The intention of this work is to provide criteria on which a design for containing the waste can be developed. Specific activities performed by Bechtel included: drilling for subsurface geologic data; installing monitoring wells; measuring permeability and ground-water flow directions; and collecting soil, sediment, surface- and ground-water, and liquid-waste samples for chemical analysis. Results are presented on the geology and ground waters.
Date: May 1, 1984
Partner: UNT Libraries Government Documents Department

JUPITER-II Program: ANL analysis of ZPPR-13A and ZPPR-13B

Description: The ZPPR-13 experiments provide basic physics data for radial heterogeneous LMFBR cores of approximately 700MWe size. Assemblies ZPPR-13A, ZPPR-13B and ZPPR-13A comprised the JUPITER-II cooperative program between the U.S. Department of Energy (US DOE) and PNC of Japan. The measurements were made between August 1982 and April 1984. The core designs and the measurements were planned jointly by the two parties with substantial input from U.S. industrial interests to ensure coverage of the design requirements. This report describes in detail the results of the Argonne National Laboratory (ANL) analyses of phases 13A and 13B/1 and includes preliminary results for the later assemblies of phase 13B..
Date: August 1, 1984
Creator: Collins, P.J. & Brumbach, S.B.
Partner: UNT Libraries Government Documents Department

Fuel Storage Facility Final Safety Analysis Report. Revision 1

Description: The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.
Date: March 1, 1984
Creator: Linderoth, C.E.
Partner: UNT Libraries Government Documents Department

Thermal analysis of NNWSI conceptual waste package designs

Description: Lawrence Livermore National Laboratory is involved in the design and testing of high-level nuclear waste packages. Many of the aspects of waste package design and testing (e.g., corrosion and leaching) depend in part on the temperature history of the emplaced packages. This report discusses thermal modeling and analysis of various emplaced waste package conceptual designs including the models used, the assumptions and approximations made, and the results obtained. 16 references.
Date: April 1, 1984
Creator: Stein, W.; Hockman, J.N. & O`Neal, W.C.
Partner: UNT Libraries Government Documents Department

Numerical studies of fluid and heat flow near high-level nuclear waste packages emplaced in partially saturated fractured tuff

Description: We have performed modeling studies on the simultaneous transport of heat, liquid water, vapor, and air in partially saturated fractured porous rock. Formation parameters were chosen as representative of the potential repository horizon in the Topopah Spring Unit of the Yucca Mountain tuffs. The presence of fractures makes the transport problem very complex, both in terms of flow geometry and physics. The numerical simulator "TOUGH" used for our flow calculations takes into account most of the physical effects which are important in multi-phase fluid and heat flow. It has provisions for handling the extreme non-linearities which arise in phase transitions, component disappearances, and capillary discontinuities at fracture faces. We model a region around an infinite linear string of nuclear waste canisters, taking into account both the discrete fractures and the porous matrix. From an analysis of the results obtained with explicit fractures, we develop equivalent continuum models which can reproduce the temperature, saturation, and pressure variation, and gas and liquid flow rates of the discrete fracture-porous matrix calculations. The equivalent continuum approach makes use of a generalized relative permeability concept to take into account the fracture effects. This results in a substantial simplification of the flow problem which makes larger scale modeling of complicated unsaturated fractured porous systems feasible. Potential applications for regional scale simulations and limitations of the continuum approach are discussed. 35 refs., 14 figs., 4 tabs.
Date: November 1, 1984
Creator: Pruess, K.; Tsang, Y.W. & Wang, J.S.Y.
Partner: UNT Libraries Government Documents Department

[US Geological Survey research in radioactive waste disposal, fiscal year 1982:] Hydrology

Description: The objective is to determine present and past hydrologic regimes of the Nevada Test Site and vicinity in order to predict the potential for ground-water transport of radioactive waste from a proposed repository in Yucca Mountain to the accessible environment. Test drilling and hydraulic testing are being conducted in both the saturated and unsaturated zones to characterize in detail the hydrologic regimes of the Yucca Mountain area. Results will be used to interpret potential ground-water flow pathways and bulk hydrogeologic properties of unsaturated and saturated rocks, and to obtain information on the chemistry and age of the ground water. Progress is reported. 1 ref.
Date: January 1, 1984
Creator: Wilson, W. E.
Partner: UNT Libraries Government Documents Department

Americium thermodynamic data for the EQ3/6 database

Description: Existing thermodynamic data for aqueous and solid species of americium have been reviewed and collected in a form that can be used with the EQ3/6 database. Data that are important in solubility calculations for americium at a proposed Yucca Mountain nuclear waste repository were emphasized. Conflicting data exist for americium complexes with carbonates. Essentially no data are available for americium solids or complexes at temperatures greater than 25{sup 0}C. 17 references, 4 figures.
Date: July 1, 1984
Creator: Kerrisk, J.F.
Partner: UNT Libraries Government Documents Department

Behavior of nuclear waste elements during hydrothermal alteration of glassy rhyolite in an active geothermal system: Yellowstone National Park, Wyoming

Description: The behavior of a group of nuclear waste elements (U, Th, Sr, Zr, Sb, Cs, Ba, and Sm) during hydrothermal alteration of glassy rhyolite is investigated through detailed geochemical analyses of whole rocks, glass and mineral separates, and thermal waters. Significant mobility of U, Sr, Sb, Cs, and Ba is found, and the role of sorption processes in their observed behavior is identified. Th, Zr, and Sm are relatively immobile, except on a microscopic scale. 9 references, 2 figures, 2 tables.
Date: December 31, 1984
Creator: Sturchio, N.C. & Seitz, M.G.
Partner: UNT Libraries Government Documents Department

Petrologic and geochemical characterization of the Topopah Spring Member of the Paintbrush Tuff: outcrop samples used in waste package experiments

Description: This report summarizes characterization studies conducted with outcrop samples of Topopah Spring Member of the Paintbrush Tuff (Tpt). In support of the Waste Package Task within the Nevada Nuclear Waste Storage Investigation (NNWSI), Tpt is being studied both as a primary object and as a constituent used to condition water that will be reacted with waste form, canister, or packing material. These studies directly or indirectly support NNWSI subtasks concerned with waste package design and geochemical modeling. To interpret the results of subtask experiments, it is necessary to know the exact nature of the starting material in terms of the intial bulk composition, mineralogy, and individual phase geochemistry. 31 figures, 5 tables.
Date: June 1, 1984
Creator: Knauss, K.G.
Partner: UNT Libraries Government Documents Department

Corrosion behavior of carbon steels under tuff repository environmental conditions

Description: Carbon steels may be used for borehole liners in a potential high-level nuclear waste repository in tuff in Nevada. Borehole liners are needed to facilitate emplacement of the waste packages and to facilitate retrieval of the packages, if required. Corrosion rates of low carbon structural steels AISI 1020 and ASTM A-36 were determined in J-13 well water and in saturated steam at 100{sup 0}C. Tests were conducted in air-sparged J-13 water to attain more oxidizing conditions representative of irradiated aqueous environments. A limited number of irradiation corrosion and stress corrosion tests were performed. Chromium-molybdenum alloy steels and cast irons were also tested. These materials showed lower general corrosion but were susceptible to stress corrosion cracking when welded. 4 references, 4 tables.
Date: October 1, 1984
Creator: McCright, R.D. & Weiss, H.
Partner: UNT Libraries Government Documents Department

Effects of tuff waste package components on release from 76-68 simulated waste glass: Final report

Description: An experimental matrix has been conducted that will allow evaluation of the effects of waste package constituents on the waste form release behavior in a tuff repository environment. Tuff rock and groundwater were used along with 304L, 316, and 1020M ferrous metals to evaluate release from uranium-doped MCC 76-68 simulated waste glass. One of the major findings was that in the absence of 1020M mild steel, tuff rock powder dominates the system. However, when 1020M mild steel is present, it appears to dominate the system. The rock-dominated system results in suppressed glass-water reaction and leaching while the 1020M-dominated system results in enhanced leaching - but the metal effectively scavenges uranium from solution. The 300-series stainless steels play no significant role in affecting glass leaching characteristics. 6 refs., 28 figs., 5 tabs.
Date: April 1, 1984
Creator: McVay, G.L. & Robinson, G.R.
Partner: UNT Libraries Government Documents Department

Review of DOE waste package program. Subtask 1.1. National waste package program, April-September 1983. Volume 5

Description: The current effort is part of an ongoing task to review the national high-level waste package effort. It includes evaluations of reference waste form, container, and packing material components with respect to determining how they may contribute to the containment and controlled release of radionuclides after waste packages have been emplaced in salt, basalt, and tuff repositories. In the current Biannual Report a section on carbon steel container corrosion has been included to complement prior work on TiCode-12 and Type 304 stainless steel. The use of crushed tuff as a packing material is discussed and waste package component interaction test data are included. Licensing data requirements to estimate the degree of compliance with NRC performance objectives are specified. 41 figures, 24 tables.
Date: August 1, 1984
Creator: Soo, P. (ed.)
Partner: UNT Libraries Government Documents Department

In situ stress measurements at the Spent Fuel Test-Climax facility

Description: The status of the following studies is given: in situ state of stress; stress gradient into rib from south heater drift; pillar stresses; and rock deformational properties. 11 references, 38 figures, 12 tables.
Date: May 1, 1984
Creator: Creveling, J.B.; Shuri, F.S.; Foster, K.M. & Mills, S.V.
Partner: UNT Libraries Government Documents Department

SEM studies of stressed and irradiated Climax Stock quartz monzonite

Description: In an effort to find the mechanism by which gamma irradiation weakens the unconfined compressive strength of Climax Stock quartz monzonite (CSQM), sections of rock which had been irradiated and loaded to near failure were studied by scanning electron microscopy and compared to sections of rock which had been loaded but not irradiated. The quantities measured and compared were numbers and lengths of microfractures in the rock. We found that the crack parameters depended neither on irradiation treatment nor even on stress history, except in one sample which actually failed. By comparison to cracks counted in other granites by other workers, the crack statistics on CSQM are much noisier and much less indicative of stress history. CSQM is structurally more heterogeneous than the other granites, which is probably the cause of the greater noise level. 12 references, 3 figures, 5 tables.
Date: February 1, 1984
Creator: Beiriger, J.M. & Durham, W.B.
Partner: UNT Libraries Government Documents Department

Changes in permeability and fluid chemistry of the Topopah Spring Member of the Paintbrush tuff (Nevada Test Site) when held in a temperature gradient: summary of results

Description: The permeability and groundwater chemistry results for the Topopah Spring Member are reported and compared with the results from the previous work on Bullfrog. Permeability measurements made on samples of the Topopah Spring Member of the Paintbrush Tuff at room-temperature and in a temperature gradient show that the initially high (3-65 {mu}da) permeabilities are little affected by heating to at least 150{sup 0}C. These permeability relationships are favvorable for the disposal of nuclear waste in this stuff in an unsaturated zone at the Nevada Test Site. The fluids discharged from the samples of tuff during the experiments are dilute, nearly neutral solutions that differ only slightly from the starting groundwater composition. 8 references, 10 figures, 5 tables.
Date: June 1, 1984
Creator: Moore, D.E.; Morrow, C.A. & Byerlee, J.D.
Partner: UNT Libraries Government Documents Department

Reaction of the Topopah Spring tuff with J-13 well water at 90{sup 0}C and 150{sup 0}C

Description: As part of the Nevada Nuclear Waste Storage Investigations Project, the Lawrence Livermore National Laboratory is responsible for the design and testing of waste packages suitable for use in the Topopah Spring tuff at Yucca Mountain. Definition of the physical and chemical environment of the waste package is part of that task. This report describes a series of hydrothermal experiments using crushed tuff from the Topopah Spring Member and natural groundwater from Well J-13. The purpose of these experiments is to define the changes in water chemistry that would result from temperature changes caused by emplacement of high-level nuclear waste in a repository in the Topopah Spring tuff. Experiments were conducted at 90{sup 0}C and at 150{sup 0}C in Teflon-lined reaction vessels. Results are given for four rock-to-water ratios at 90{sup 0}C and for reaction times up to 72 days. Data for 150{sup 0}C cover reaction times up to 64 days and four rock-to-water ratios. The composition of evaporite deposits contained in the pores of surface outcrop rock material used in these experiments is determined and for two of the data sets rock material was pretreated to remove this calishe-type material. The main conclusion that can be drawn from this work is that changes in the water chemistry due to heating of the rock-water system can be expected to be very minor. There is no significant source of anions (F{sup -}, Cl{sup -}, NO{sub 3}{sup -}, or SO{sub 4}/sup =/) in the rock; solution anion compositions after reaction of pretreated rock with J-13 water differ very little from the starting compositions. The major changes in cations are an increase in silica to approximately the level of cristobalite solubility, supersaturation of aluminum followed by slow precipitation, and fairly rapid precipitation of Ca and Mg due to retrograde solubility of calcite. 7 ...
Date: May 30, 1984
Creator: Oversby, V.M.
Partner: UNT Libraries Government Documents Department

Hydrothermal interaction of Topopah Spring tuff with J-13 water as a function of temperature

Description: In support of the Nevada Nuclear Waste Storage Investigations Project experiments were conducted to study the hydrothermal interaction of rock and water representative of a potential repository in tuff. These experiments provided data relevant to near-field repository conditions that can be used to: assess the ability to use accelerated tests based on the SA/V (surface area/volume) parameter and temperature; allow the measurement of chemical changes in phases present in the tuff before reaction as well as the identification and chemical analysis of secondary phases resulting from hydrothermal reactions; and demonstrate the usefulness of geochemical modeling in a repository environment using the EQ3/6 thermodynamic/kinetic geochemical modeling code. Crushed tuff and polished wafers of tuff were reacted with a natural ground water in Dickson-type gold-cell rocking autoclaves which were periodically sampled under in-situ conditions. Results were compared with predictions based on the EQ3/6 geochemical modeling code. Eight short-term experiments (2 to 3 months) at 150{sup 0}C and 250{sup 0}C have been completed using tuff from both drillcore and outcrop. Long-term experiments at 90{sup 0}C and 150{sup 0}C using drillcore polished wafers are in progress. This paper will focus on the results of the 150{sup 0}C and 250{sup 0}C experiments using drill core polished wafers. 11 references, 4 figures.
Date: November 30, 1984
Creator: Knauss, K.G.; Delany, J.M.; Beiriger, W.J. & Peifer, D.W.
Partner: UNT Libraries Government Documents Department

Location performance objectives for the NNWSI area-to-location screening activity

Description: Fifty-four objectives were identified to guide the screening of the Nevada Research and Development Area of the Nevada Test Site for relatively favorable locations for the disposal of nuclear waste in a mined geologic repository. The objectives were organized as a hierarchy composed of 4 upper-level, 12 middle-level, and 38 lower-level objectives. The four upper-level objectives account for broad national goals to contain and isolate nuclear waste in an environmentally sound and economically acceptable manner. The middle-level objectives correspond to topical categories that logically relate the upper-level objectives to site-specific concerns such as seismicity, sensitive species, and flooding hazards (represented by the lower-level objectives). The relative merits of alternative locations were compared by an application of decision analysis based on standard utility theory. The relative favorabilities of pertinent physical conditions at each alternative location were weighted in relation to the importance of objectives, and summed to produce maps indicating the most and the least favorable locations. Descriptions of the objectives were organized by the hierarchical format; they detail the applicability of each objective to geologic repository siting, previously published siting criteria corresponding to each objective, and the rationale for the weight assigned to each objective, and the pertinent attributes for evaluating locations with respect to each objective. 51 references, 47 figures, 4 tables.
Date: January 1, 1984
Creator: Sinnock, S. & Fernandez, J.A.
Partner: UNT Libraries Government Documents Department