Current FFTF Transition Project plans call for construction of a Sodium Storage Facility to store the plant sodium until it is processed either as product or waste. This report evaluates an alternative concept which would store the sodium in rail tank cars. It is concluded that utilizing a simple facility for offloading the FFTF sodium to standard industrial tank cars is not technically viable. Mitigation of potential radioactive sodium spills requires that the offload facility incorporate many of the features of the sodium storage facility. With these mitigation features incorporated, there is no significant cost or schedule advantage for the option of storing the FFTF sodium in tank cars when compared to the currently planned SSF. In addition, it is believed that the tank car option results in higher risk to project success because of unknowns associated with technical, regulatory, and public perception issues. It is therefore recommended that the project proceed with definitive design of the SSF.

This report describes a rapid screening procedure used to test the enzymatic capabilities of bacterial consortia in groundwater from well clusters P-24, P-28, and P-29.

Equations of motion are presented, appropriate to interacting charged particles of diverse charge and mass, subject to the external forces produced by various kinds of magnetic fields and radio-frequency (rf) electric fields in storage rings. These equations are employed in the molecular dynamics simulations to study the properties of crystalline beams. The two necessary conditions for the formation and maintenance of crystalline beams are summarized. The transition from ID to 2D, and from 2D to 3D is explored, and the scaling behavior of the heating rates is discussed especially in the high temperature limit. The effectiveness of various cooling techniques in achieving crystalline states has been investigated. Crystalline beams made of two different species of ions via sympathetic cooling are presented, as well as circulating ``crystal balls`` bunched in all directions by magnetic focusing and rf field. By numerically reconstructing the original experimental conditions of the NAP-M ring, it is found that only at extremely low beam intensities, outside of the range of the original measurement, proton particles can form occasionally-passing disks. The proposed New ASTRID ring is shown to be suitable for the formation and maintenance of crystalline beams of all dimensions.

A new analytic model is presented that accurately estimates the radially averaged axial component of the space-charge field of an axisymmetric heavy-ion beam in a cylindrical beam pipe. The model recovers details of the field near the beam ends that are overlooked by simpler models, and the results compare well to exact solutions of Poisson`s equation. Field values are shown for several simple beam profiles and are compared with values obtained from simpler models. The model has been implemented in the fluid/envelope code CIRCE and used to study longitudinal confinement in beams with a variety of axial profiles. The effects of errors in the longitudinal-control fields are presented.

This Source Guide will assist those working with the National Environmental Policy Act of 1969 (NEPA) to become more familiar with the Environmental Assessments (EA) and Environmental Impact Statements (EIS) that apply to specific activities and facilities at the Hanford Site. This document should help answer questions concerning NEPA coverage, history, processes, and the status of many of the buildings and units on and related to the Hanford Site. This document summarizes relevant EAs and EISs by briefly outlining the proposed action of each and the decision made by the US Department of Energy (DOE) or its predecessor agencies, the US Atomic Energy Commission (AEC), and the US Energy Research and Development Administration (ERDA), concerning the proposed action and current status of the buildings and units discussed in the proposed action. If a decision was officially stated by the DOE, as in a Finding Of No Significant Impact (FONSI) or a Record of Decision (ROD), and was located, a summary is provided in the text. Not all federal decisions, such as FONSIs and RODS, can be found in the Federal Register (FR). For example, although significant large-action FONSIs can be found in the FR, some low-interest FONSIs may have been …

Compact tension specimens taken from FFTF primary piping materials (Type 316 stainless steel (SS) and 16-8-2 SS weld metal) and from reactor vessel materials (304 SS and 308 SS weld metal) were heated in laboratory furnaces from 100,000 hours. Fracture toughness testing was performed on these specimens, which are 7.62- and 25.4-mm thick, respectively at the aging temperature (482 and 427 degrees). Results were analyzed with the multiple-specimen method. Thermal aging continues to reduce the fracture toughness of FFTF component materials. Results show that thermal aging has a strong effect on the toughness degradation of weld metals, particularly for 16-8-2 SS weld whose aged/unaged Jc ratio is only 0.31 after 100,000-hour aging. The fracture toughness of the 308 and 16-8-2 SS weld metals fluctuated during 20,000 to 50,000-hour aging but deteriorated as the aging time increased to 100,000 hours; the toughness degradation is significant. Fracture control based on a fracture mechanics approach should be considered

Knowledge of how water flows through unsaturated, fractured rock is critical for understanding and predicting the performance of a high- level nuclear waste repository. For instance, during gravity driven fracture flow, the distance that water can travel through a fracture network might be controlled by (1) the amount of water available, (2) the fracture aperture, (3) the capillary properties of the matrix, and (4) the saturation of the matrix. We have experimentally investigated fracture flow and fracture-matrix interactions using x- ray radiography to image some of the above factors and processes.

Radcalc for Windows is a user-friendly menu-driven Windows-compatible software program with applications in the transportation of radioactive materials. It calculates the radiolytic generation of hydrogen gas in the matrix of low-level and high-level radioactive waste using NRC-accepted methodology. It computes the quantity of a radionuclide and its associated products for a given period of time. In addition, the code categorizes shipment quantities as radioactive, Type A or Type B, limited quantity, low specific activity, highway route controlled, and fissile excepted using DOT definitions and methodologies, as outlined in 49 CFR Subchapter C. The code has undergone extensive testing and validation. Volume I is a User`s Guide, and Volume II is the Technical Manual for Radcalc for Windows.

To satisfy the safety requirements of a terrestrial 60-watt radioisotope heat source, it was necessary to determine whether the internal pressure buildup from the helium generated from Pu-238 decay would pose problems in a fire environment. Nine strength members (capsules), three of the end-cap weld design and six of the girth weld design, were pressure-burst tested. The end-cap weld design was not successful, with failure times of less than three minutes. The girth weld design gave favorable results, with life times ranging from 8 to 240 hours. All of the girth weld capsules failed in the center of the weld. The Oak Ridge National Laboratory stress rupture model equation for determining test life does not predict the test hours to failure for the girth weld design.

This report lists the Hanford specific files (Table 1) that make up the Hanford Site Technical Baseline Database. Table 2 includes the delta files that delineate the differences between this revision and revision 0 of the Hanford Site Technical Baseline Database. This information is being managed and maintained on the Hanford RDD-100 System, which uses the capabilities of RDD-100, a systems engineering software system of Ascent Logic Corporation (ALC). This revision of the Hanford Site Technical Baseline Database uses RDD-100 version 3.0.2.2 (see Table 3). Directories reflect those controlled by the Hanford RDD-100 System Administrator. Table 4 provides information regarding the platform. A cassette tape containing the Hanford Site Technical Baseline Database is available.

NMR experiments are reported for Sr{sub 2}CuO{sub 2}Cl{sub 2}, HgBa{sub 2}CuO{sub 4+d}, YNi{sub 2}B{sub 2}C and YBa{sub 2}Cu{sub 3}O{sub 7}. NMR studies typify three different aspects of microscopic properties of HTSC. In non-superconducting antiferromagnetic (AF) prototype Sr{sub 2}CuO{sub 2}Cl{sub 2}, we used NMR to investigate Cu{sup 2+} correlated spin dynamics and AF phase transition in CuO2 layers. In the superconductors, we used NMR both to investigate the electronic properties of the Fermi-liquid in normal and superconducting states and to investigate flux lattice and flux-line dynamics in the superconducting state in presence of magnetic field. A summary of each study is given: {sup 35}Cl NMR was measured in Sr{sub 2}CuO{sub 2}Cl{sub 2} single crystals with T{sub N}=257K. {sub 35}Cl NMR relaxation rates showed crossover of Cu{sup 2+} spin dynamics from Heisenberg to XY-like correlation at 290 K well above T{sub N}. A field-dependent T{sub N} for H{perpendicular}c was observed and explained by a field-induced Ising-like anisotropy in ab plane. {sup 199}Hg NMR was measured in HgBa{sub 2}CuO{sub 4+d}. Properties of the Fermi-liquid are characterized by a single-spin fluid picture and opening of a spin pseudo-gap at q=0 above {Tc}. Below {Tc}, spin component of Knight shift decreases rapidly in agreement with …

Sampling analysis plans (SAP) are a recognized manner of providing applicable requirements for conducting media sampling and analysis in a manner consistent with prescirbed objectives. This SAP has been prepared to satisfy the data quality objectives listed in this SAP with respect to the operation of the 183 KE potable water for K Area.

Significant changes have been made to all of the original vapor characterization reports. This report documents specific headspace gas and vapor characterization results for all vapor sampling events to date. In addition, changes have been made to the original vapor reports to qualify the data based on quality assurance issues associated with the performing laboratories

The Yucca Mountain Site Characterization Project is investigating Yucca Mountain, Nevada, for its suitability as a potential repository for high-level nuclear wastes. United States federal regulation 10CFR60 requires that radioactive nuclides be substantially contained in waste packages for 300 to 1000 years after the emplacement. To meet the regulation, a waste package container should remain intact for several hundreds of years. It has been shown that high humidity increases the corrosion potential of metallic container materials. Relative humidity as a function of water saturation in intact rock is measured. The results of this test can be used to calibrate the relative humidity in the near-field environment predicted by model calculations using thermal-hydrological codes such as VTOUGH. This is a report on the progress of that experiment.

This Double-Shell Tank Retrieval Allowable Heel Trade Analysis evaluates the effects a remaining heel has on subsequent waste storage requirements after initial retrieval. The information contained in this analysis will be used as a basis to identify crucial double-shell tank (DST) retrieval system design and performance requirements for continued storage of waste in DSTs. The information presented in this analysis is summarized by the DST initial retrieval and reuse strategy. The strategy is based on the waste compatibility and consolidation requirements that are governed by the remaining heel after initial retrieval

This document serves as a User`s Manual and Reference for the library of Tcl and Tk procedures produced by the Operations Analysis Group. Also covered are compiled interpreter extensions.

This report summarizes work authorized for technical and scientific support to waste cementation and saltcrete processing operations. During this report period, tasks described in amendment M003 were initiated, some were completed, and an additional task not listed in M003 also was completed at the request of DOE RF. Summaries of task-specific activities are in four enclosures to this progress report. Other activities during this quarter included negotiation and initiation of amendment M004, to extend the period of performance and continue WES assistance to DOE RF. The four enclosures are: continuing support to waste cementation and saltcrete operations at DOE Rocky Flats Facility; review of ``Analyses of saltcrete``; review of Connell, et al ``Saltcrete evaluation`` report dated August 16, 1993; and scoping study of simulated saltcrete.

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This plan describes a configuration management program for K Basins that establishes the systems, processes, and responsibilities necessary for implementation. The K Basins configuration management plan provides the methodology to establish, upgrade, reconstitute, and maintain the technical consistency among the requirements, physical configuration, and documentation. The technical consistency afforded by this plan ensures accurate technical information necessary to achieve the mission objectives that provide for the safe, economic, and environmentally sound management of K Basins and the stored material. The configuration management program architecture presented in this plan is based on the functional model established in the DOE Standard, DOE-STD-1073-93, {open_quotes}Guide for Operational Configuration Management Program{close_quotes}.

Obtaining high-resolution gamma-ray measurements using high-purity germanium (HPGe) detectors in the field has been of limited practicality due to the need to use and maintain a supply of liquid nitrogen (LN{sub 2}). This same constraint limits high-resolution gamma measurements in unattended safeguards or treaty Verification applications. We are developing detectors and software to greatly extend the applicability of high-resolution germanium-based measurements for these situations.

The overall objective of the Project is the expedited commercialization of advanced coal-fired low-emission boiler systems. The goals for emissions and plant efficiency are: NO{sub x} emissions not greater than 0.1 lb/million Btu; SO{sub x} emissions not greater than 0.1 lb/million Btu; particulate emissions not greater than 0.01 lb/million Btu; and net plant efficiency (HHV basis) not less than 42%. Other goals include: improved ash disposability and reduced waste generation; and reduced air toxics emissions. The final deliverables are a design data base that will allow future coal-fired power plants to meet the stated objectives, and a preliminary design of a Commercial Generation Unit. The work in Phase I covered a 24- month period and included system analysis, RD&T Plan formulation, component definition, and preliminary Commercial Generating Unit (CGU) design. Phase II will cover a 15-month period and will include preliminary Proof-of-Concept Test Facility (POCTF) design and subsystem testing. Phase III will cover a 9-month period and will produce a revised CGU design and a revised POCTF design, cost estimate and a test plan. Phase IV, the final Phase, will cover a 36- month period and will include POCTF detailed design, construction, testing, and evaluation.

This sampling and analysis plan will identify characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for vapor samples and one rotary mode core sample from tank 241-BY-106.

LLNL has an ongoing program of weapons disablement using energetic charged particle beams; this program combines theoretical and experimental expertise in accelerators, high-energy and nuclear physics, plasma physics and hydrodynamics to simulate/measure effects of electron and proton beams on weapons. This paper reviews work by LLNL, LANL and NSWC on detonating sensitive and insensitive high explosives and land mines using high-current electron beams. Computer simulations are given. 20--160 MeV electron beams incident on wet/dry soils are being studied, along with electron beam propagation in air. Compact high current, high energy accelerators are being developed for mine clearing. Countermine missions of interest are discussed. 25 refs., 9 figs.

Integrated Pest Management Services is responsible for management and control of noxious weeds on the Hanford Site. Weed species and populations are prioritized and objective defined, according to potential site and regional impact. Population controls are implemented according to priority. An integrated approach is planned for noxious weed control in which several management options are considered and implemented separately or in coordination to best meet management objectives. Noxious weeds are inventories and monitored to provide information for planning and program review.