Tests are ongoing at Argonne National Laboratory to examine the reaction of glass with water under conditions that may exist in the proposed repository at Yucca Mountain, Nevada. Examination of glass reaction using the Unsaturated Test method as applied to simulated defense glass (SRL 165 black frit based) and simulated West Valley glass (ATM-10) is ongoing. The tests on SRL 165 glass have been ongoing for 104 weeks with nonstoichiometric release of Li, Na, B, and actinide elements being observed throughout the test period. The tests on ATM-10 glass have been in progress for 26 weeks and it is too early in the test cycle to assess the glass reaction. The influence of penetrating gamma radiation on the reaction of synthetic nuclear waste glasses in tuff groundwater was also investigated. Modified MCC-1 static leaching experiments were performed under radiation exposures of 1 {times} 10{sup 3} R/h and O R/h at 90{degree}C. The groundwater was acidified by nitrous and nitric acids radiolytically produced in the air. The high bicarbonate ion concentration of the groundwater prevented the pH from dropping below 6.4, however. The glass reaction, as measured by the release of glass species and the thickness of an alteration layer formed …

This paper presents selected preliminary results obtained during the first 54 days of the Prototype Engineered Barrier System Field Tests (PEBSFT) that are being performed in G-Tunnel within the Nevada Test Site. The test described is a precursor to the Engineered Barrier Systems Field Tests (EBSFT). The EBSFT will consist of in situ tests of the geohydrologic and geochemical environment in the near field (within a few meters) of heaters emplaced in welded tuff to simulate the thermal effects of waste packages. The PEBSFTs are being conducted to evaluate the applicability of measurement techniques, numerical models, and procedures for future investigations that will be conducted in the Exploratory Shaft Facilities of the Yucca Mountain Project (YMP). The paper discusses the evolution of hydrothermal behavior during the prototype test, including rock temperatures, changes in rock moisture content, air permeability of fractures, gas pressures, and rock mass gas-phase humidity. 10 refs., 12 figs.

The environmental radiation shielding requirements of the SSC have been evaluated using currently available computational tools that incorporate the well known processes of energy loss and degradation of high energy particles into Monte Carlo computer codes. These tools permit determination of isodose contours in the matter surrounding a source point and therefore the specification of minimum thicknesses or extents of shielding in order to assure annual dose equivalents less than some specified design amount. For the general public the annual dose equivalent specified in the design is 10 millirem, small compared to the dose from naturally occurring radiation. The types of radiation fall into two classes for the purposes of shielding determinations-hadrons and muons. The sources of radiation at the SSC of concern for the surrounding environment are the interaction regions, the specially designed beam dumps into which the beams are dumped from time to time, and beam clean-up regions where stops remove the beam halo in order to reduce experimental backgrounds. A final, unlikely source of radiation considered is the accidental loss of the full beam at some point around the ring. Conservative choices of a luminosity of 10{sup 34} cm{sup {minus}2}s{sup {minus}1} and a beam current three times …

Static leaching experiments have been performed to determine the influence of penetrating gamma radiation on the reaction of simulated nuclear waste glass in tuff groundwater at 90{degree}C. Both the leachates and the reacted glass monoliths were analyzed to characterize the reaction. Radiation was seen to acidify the leachates, but the high bicarbonate content of the groundwater prevented the pHs from dropping below 6.4. The glass reaction tended to raise the pH. Glass based on SRL 165 black frit and PNL 76-68 glass compositions were leached. The SRL 165 type glasses were quite durable and unaffected by radiation [NL(B) {approximately}4 g/m{sup 2} after 278 days at all exposure rates]. The PNL 76-68 glasses were much less durable, with the durability decreasing as the exposure rate was increased [NL(B) was about 20 g/m{sup 2} after 278 days at 1 {times} 10{sup 3} R/h for both ATM-1c and ATM-8 glasses]. 8 refs., 5 figs.

This report is intended to provide a summary of the cost and schedule performance for the Civilian Radioactive Waste Management Program. Performance data are presented for each of the major program elements. Also included in this report is the status of the Nuclear Waste Fund revenues and disbursements. This report includes project performance data reported through March 1989.

EQ3/6 is a software package for modeling chemical and mineralogic interactions in aqueous geochemical systems. The major components of the package are EQ3NR (a speciation-solubility code), EQ6 (a reaction path code), EQLIB (a supporting library), and a supporting thermodynamic data base. EQ3NR calculates aqueous speciation and saturation indices from analytical data. It can also be used to calculate compositions of buffer solutions for use in laboratory experiments. EQ6 computes reaction path models of both equilibrium step processes and kinetic reaction processes. These models can be computed for closed systems and relatively simple open systems. EQ3/6 is useful in making purely theoretical calculations, in designing, interpreting, and extrapolating laboratory experiments, and in testing and developing submodels and supporting data used in these codes. The thermodynamic data base supports calculations over the range 0-300{degree}C. 60 refs., 2 figs.

Two potential degradation mechanisms, creep and stress corrosion cracking, of Zircaloy cladding during repository storage of spent nuclear fuel have been investigated. The deformation and fracture map methodology has been used to predict maximum allowable initial storage temperatures to achieve a thousand year life without rupture as a function of spent-fuel history. A stress analysis of fuel rods has been performed. Stresses in the outer zirconium oxide layer and the inner Zircaloy tube have been predicted for typical internal pressurization, oxide layer thickness, volume expansion from formation of the oxide layer and thermal expansion coefficients of the cladding and oxide. Stress relaxation occurring in-reactor has also been taken into account. The calculations indicate that for the anticipated storage conditions investigated, the outer zirconium oxide layer is in a state of compression thus making it unlikely that stress corrosion cracking of the exterior surface will occur. 20 refs., 6 figs., 9 tabs.

This report is intended to provide a summary of the cost and schedule performance for the Civilian Radioactive Waste Management Program. Performance data are presented for each of the major program elements. Also included in this report is the status of the Nuclear Waste Fund revenues and disbursements. This report includes performance data through December 1988.

Operation of the Gravimelt Integrated Test Circuit for desulfurization and demineralization of coal has been completed. A 48-test process matrix was performed over 750 hours of operational time resulting in production of 3,000 pounds of treated coal suitable for further test and evaluation. Optimization testing was performed resulting in product coal containing 0.4 percent sulfur (0.6 lbs SO{sub 2}/MMBtu) and 0.15 percent ash with more than 85 percent organic sulfur removal, 95 percent SO{sub 2} reduction from ROM coal and 91 percent SO{sub 2} reduction from precleaned process feed. This report contains all of the product sulfur, ash, volatiles and heat content data obtained to date.

In late 1987 Congress issued an amendment to the Nuclear Waste Policy Act of 1982 which directed the characterization of Yucca Mountain, Nevada as the only remaining potential site for the Nation`s first underground high-level radioactive waste repository. The evaluation of a potential underground repository is guided and regulated by policy established by the Department of Energy (DOE), Nuclear Regulatory Commission (NRC), Environmental Protection Agency (EPA), Department of Transportation (DOT), and the US Congress. The Yucca Mountain Project is the responsibility of the DOE. The purpose of this field trip is to introduce the present state of geologic and hydrologic knowledge concerning this site. This report describes the field trip. 108 refs., 6 figs., 1 tab.

This report presents an analysis of the in-situ geomechanical testing needs for the Exploratory Shaft (ES) test facility at the Yucca Mountain site in Nevada. The testing needs are derived from 10CFR60 regulations and simple thermomechanical canister- and room-scale numerical studies. The testing approach suggested is based on an ``iterative`` procedure of full-scale testing combined with numerical and empirical modeling. The testing suggested is based heavily on demonstration of excavation and thermal loading of full-scale repository excavations. Numerical and/or empirical models are compared to the full-scale response, allowing for adjustment of the model and evaluation of confidence in their predictive ability. Additional testing may be specified if confidence in prediction of the rock mass response is low. It is suggested that extensive drifting be conducted within the proposed repository area, including exploration of the bounding Drill Hole Wash and Imbricate fault structures, as well as the Ghost Dance fault. This approach is opposed to an a priori statistical specification of a number of ``point`` tests which attempt to measure a given property at a specific location. 40 refs., 49 figs., 6 tabs.

Conceptual designs for waste packages containing spent fuel or high-level waste glass have been developed for use in a repository at Yucca Mountain. The basis for these designs reflects the unique nature of the expected service environment associated with disposal in welded tuff in the unsaturated zone. In addition to a set of reference designs, alternative design concepts are being considered that would contain and isolate the waste radionuclides in a more aggressive service environment. Consideration is also being given to the feasibility of a concept known as ``heat tailoring`` that employs the thermal energy released by the wasteforms to enhance and extend the performance of the containers. 5 refs., 3 figs.

Data is presented concerning cost estimates and schedules for process facilities and nuclear facilities modernization.

The cold support concept for the ARIES TF coil design was developed further. This concept not only works for aspect ratio 6 and 4.5 machines, but it also works for ITER. Beryllium was added to the two blanket concepts to improve energy multiplication and reduce COE. During the quarter a US-Japan steering committee meeting was held to discuss the US-Japan ICRH tube tests. They reviewed and approved the proposed X2242 ICRH tube improvements. Ed Cheng attended IAEA meeting on the International Fusion Evaluated Nuclear Data Library (FENDL). The first version of FENDL should be ready for use by mid-1990. Exposure of 12 well-characterized graphite tiles in the divertor region of DIII-D continues. Work has been initiated on the laser ellipsometry technique to be used for in situ on-line measurement of erosion and redeposition in the DIII-D divertor. A Neutron Interaction materials (NIM) report has been drafted compiling published and unpublished data on manganese-stabilized austenitic steels. These steels are being considered for the ITER.

Under provisions of the Surplus Facilities Management Program (SFMP), the US Department of Energy, Chicago Operations Office, proposes to provide funding for Surveillance and Maintenance (S & M) and subsequent Decontamination and Decommissioning (D & D) of fifteen facilities and associated premises belonging to Battelle Columbus Division. The fifteen facilities are contaminated as a result of nuclear research and development activities conducted over a period of approximately 43 years for DOE and its predecessor agencies--the Energy Research and Development Administration (ERDA), the Atomic Energy Commission (AEC) and the Manhattan Engineer District (MED). The proposed action includes continuation of ongoing S & M as well as a D & D of the facilities. The S & M activities include a continued environmental monitoring program to maintain assurance that radioactive contamination has not escaped to the surrounding environment; regularly scheduled inspection and maintenance of health, safety, and radiation protection equipment and instrumentation; a program of health physics surveillance monitoring, personnel dosimetry, and equipment and instrumentation maintenance and calibration; and emergency planning, training, and drills. The so- called dismantlement D & D mode is the proposed alternative for D & D of these facilities. For the facilities in question this will generally involve …

This appendix is an assessment of the present conditions of the inactive uranium mill site near Mexican Hat, Utah. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan. Plan is to characterize the conditions at the mill and tailings site so that the Remedial Action Contractor may complete final designs of the remedial action.

Several of the monitoring wells installed at the Savannah River Plant in the past few years exhibit pH values of 8 or higher. These pHs are significantly higher than average values for the aquifers involved and are also higher than expected for natural waters. They are also inconsistent with observations in nearby wells. It is therefore suspected that the high pHs are not representative of true aquifer conditions. Two previous studies conducted at SRP (Price, 1984; Schreeder, 1986) conclude that high pH readings in M-Area monitoring wells and Z-Area piezometers are the result of contact between groundwater and grout. Price bases his conclusion on water chemistry. Schreeder`s evidence is the relationship between pH and amount of water withdrawn from the piezometers--an initially high pH drops as more water is removed. This conclusion is supported by laboratory measurements on water samples collected from cement-bentonite grout which show pH values of 13. This investigation was undertaken to evaluate contamination by grout and drilling fluid as a possible cause of elevated pH in monitoring wells at SRP and to develop techniques to rehabilitate the affected wells. FSB and HSB wells were used in this study.

This Remedial Action Plan (RAP) has been developed to serve a two- fold purpose. It presents the activities proposed by the Department of Energy (DOE) to accomplish long-term stabilization and control of the residual radioactive materials (RRM) from Monument Valley Arizona, and Mexican Hat, Utah, at the Mexican Hat disposal site. It also serves to document the concurrence of both the Navajo Nation and the Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by DOE and the Navajo Nation and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement. This document has been structured to provide a comprehensive understanding of the remedial action proposed for the Monument Valley and Mexican Hat sites. It includes specific design and construction requirements for the remedial action. Pertinent information and data are included with reference given to the supporting documents. Appendices A,B, and C are provided as part of this document. Appendix A presents regulatory compliance issues, Appendix B provides details of the engineering design, and Appendix C presents the radiological support plan.

This document provides Appendix E of the Remedial Action Plan (RAP) presented in 1988 for the stabilization of the inactive uranium mill tailings at the Mexican Hat, Utah site. The RAP was developed to serve a two- fold purpose. It presents the activities proposed by the Department of Energy (DOE) to accomplish long-term stabilization and control of the residual radioactive materials (RRM) from Monument Valley, Arizona, and Mexican Hat, Utah, at the Mexican Hat disposal site. It also serves to document the concurrence of both the Navajo Nation and the Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the Navajo Nation and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement. The RAP has been structured to provide a comprehensive understanding of the remedial action proposed for the Monument Valley and Mexican Hat sites. It includes specific design and construction requirements for the remedial action.

This note will wrap up the numerical results that were obtained in our calculations of the wake potentials, the loss factors, and the impedances for a variety of structures in the APS storage ring. It consists of five sections and one appendix. Section 1 is an introduction. Section 2 summarizes the hand calculations. The computer calculations are the subject 1 of Section 3. Section 4 discusses several tests in our numerical methods. Section 5 presents the APS impedance budget, along with some discussion. The appendix contains the figures of the structures, the longitudinal/transverse wake potentials and the real/imaginary part of the impedances of various sorts of geometries that have been included in the budget.

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).

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 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.

Experiments and calculations indicate that laser-induced fluorescence (LIF) lacks the sensitivity needed for sorptivity measurements of I{sub 2} or other molecular species at partial pressures below 10{sup {minus}11} atm. Although the technique may have sufficient sensitivity for measurements of atomic species, the species of interest are, in all likelihood, not atomic. Methods of measurement which would allow the determination of species are proposed. 9 refs., 6 figs.