The TWRS mission is to store, treat, and immobilize highly radioactive Hanford waste (current and future tank waste and the encapsulated cesium and strontium) in a safe, environmentally sound, and cost-effective manner (TWRS JMN Justification for mission need). The mission includes retrieval, pretreatment, immobilization, interim storage and disposal, and tank closure. As part of this mission, DOE has established the TWRS Office to manage all Hanford Site tank waste activities. The TWRS program has identified the need to store, treat, immobilize, and dispose of the highly radioactive Hanford Site tank waste and encapsulated cesium and strontium materials in an environmentally sound, safe, and cost-effective manner. To support environmental remediation and restoration at the Hanford Site a two-phase approach to using private contractors to treat and immobilize the low-activity and high-level waste currently stored in underground tanks is planned. The request for proposals (RFP) for the first phase of waste treatment and immobilization was issued in February 1996 (Wagoner 1996) and initial contracts for two private contractor teams led by British Nuclear Fuels Ltd. and Lockheed-Martin Advanced Environmental Services were signed in September 1996. Phase 1 is a proof-of-concept and commercial demonstration effort to demonstrate the technical and business feasibility of …

This report is a guide to basic sources useful in tracking federal legislation and regulations. It has been prepared primarily for the use of constituents who wish to follow the federal government's legislative or regulatory activities at the local level. Brief annotations for the selected printed, telephone, electronic, and related sources describe their scope, focus, and frequency, include publisher contact information, and provide Internet addresses where available.

This report focuses on selected aspects of the general obstruction of justice provisions found in 18 U.S.C. 1503, 1505, and 1512. It is essentially a replica, without footnotes or citations, of CRS Report 98-832, Obstruction of Justice Under Federal Law: A Review of Some of the Elements.

This project plan has a two fold purpose. First, it provides a plan specific to the Hanford Tank Waste Remediation System (TWRS) Immobilized High-Level Waste (EMW) Storage Subproject for the Washington State Department of Ecology (Ecology) that meets the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestone M-90-01 (Ecology et al. 1996) and is consistent with the project plan content guidelines found in Section 11.5 of the Tri-Party Agreement action plan. Second, it provides an upper tier document that can be used as the basis for future subproject line item construction management plans. The planning elements for the construction management plans are derived from applicable U.S. Department of Energy (DOE) planning guidance documents (DOE Orders 4700.1 (DOE 1992a) and 430.1 (DOE 1995)). The format and content of this project plan are designed to accommodate the plan`s dual purpose. A cross-check matrix is provided in Appendix A to explain where in the plan project planning elements required by Section 11.5 of the Tri-Party Agreement are addressed.

This document presents the results of operational testing of the 241-C-106 In-Tank Video Camera Imaging System. This imaging system was installed as a component of Project W-320 to monitor sluicing and waste retrieval activities in Tank 241-C-106.

This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable.

A mathematical model is developed to describe the permeation of hydrogen through thin-film palladium ceramic composite membrane in cocurrent flow configuration. Numerical simulation results show that the model under predicts reject composition and over predicts the product purity. These results suggest that the gas phase mass transfer resistance could be important. The difference between the predicted and actual hydrogen composition is less than 12%. Thus the model appears to be adequate for predicting the membrane module performance.

The purpose of this analysis is to develop a layout configuration and location for the E-W Cross Drift with the objective to meet repository, testing, and construction requirements.

Subsurface data is being collected, organized, and a digital database is being prepared. An ACCESS database and PC-Arcview if being used to manage and interpret the data. Well data and base map have been successfully imported to Arcview and customized. All of the four 30 feet by 60 feet geologic surface geologic quadrangles have been scanned to produce a digital surface data base for the Crow Reservation. Field investigations inventoried for the presence of valley-fill deposits. These appear to represent at least a four major westward-trending valley systems.

This study evaluated DuoliteTM GT-73 performance for removing mercury ions from several high level waste streams under consideration by the Salt Disposition Systems Engineering Team as a technical risk. Experiments conducted over an eight week period address the technical uncertainties for GT-73 performance

This report provides an overview of the immigration and naturalization service's budget during Fiscal Year 1999.

The Appalachian Development Highway Program is a road building program that is intended to break Appalachia's regional isolation and encourage Appalachian economic development. Administered by the Appalachian Regional Commission, the Appalachian Development Highway Program is authorized to develop a network of 3,025 miles of corridor roads. This report details the program origins, administration and organization, spending history, and issues for Congress.

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This report provides an overview of the financial outlook for social security and medicare programs.

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This report is one of a series of reports that document normal operation and accident simulations for the Accelerator Production of Tritium (APT) blanket heat removal (HR) system. These simulations were performed for the Preliminary Safety Analysis Report.

This report is one of a series of reports that document LBLOCA analyses for the Accelerator Production of Tritium primary blanket Heat Removal system. This report documents the analysis results of a LBLOCA where the accelerator beam is shut off without primary pump trips and neither the RHR nor the cavity flood systems operation.

This report provides background information for a series of reports documenting accident scenario simulations for the Accelerator Production of Tritium blanket heat removal systems.

The model results are used to determine if beam power shutdown is necessary (or not) as a result of the LOHGA accident to maintain the blanket system well below any of the thermal-hydraulic constraints imposed on the design. The results also provide boundary conditions to the detailed bin model to study the detailed temperature response of the hot blanket module structure. The results for these two cases are documented in the report.

This report is one of a series of reports documenting accident scenario simulations for the Accelerator Production of Tritium (APT) blanket heat removal systems. The simulations were performed in support of the Preliminary Safety Analysis Report (PSAR) for the APT.

This report provides documentation of the necessary source code modifications made to the TRAC-PF1/MOD2 code version 5.4.28a developed at Los Alamos National Laboratory.

This report documents the approaches taken in establishing a 1-dimensional integrated blanket system model using the TRAC code, developed by Los Alamos National Laboratory.

This study was initiated in order to determine the advantages of using a mixed-bed rather than a fixed-bed reactor (i.e. furnace) for separation of gallium from PuO{sub 2} by the Thermal Induced Gallium Removal (TIGR) process. The TIGR process is based upon vaporization of gallium suboxide (Ga{sub 2}O). from essentially nonvolatile PuO{sub 2}. The gallium suboxide is formed by passing a reducing gas (i.e. hydrogen) over the PuO{sub 2} particles. Several mechanisms are involved in the reduction and convective vaporization of the gallium suboxide. If the mass transfer of the gallium suboxide across the solid to gas interface significantly affects the processing time, it may be advantageous to use a mixed-bed reactor rather than a fixed-bed reactor. However, due to the difficulty of handling PuO{sub 2} powder, a mixed-bed reactor should be used only if significant advantages can be demonstrated. Based on available data, the results of this study provide strong evidence that a mixed-bed reactor (i.e. furnace) would provide little advantage over a fixed-bed reactor. This is due to the conclusion that the mechanism of internal gallium diffusion within the particle has the predominant affect on the processing time. This is an important conclusion since the use of a …

This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. The report contains the following calculations: Exhaust airflow sizing for Tank 241-C-106; Equipment sizing and selection recirculation fan; Sizing high efficiency mist eliminator; Sizing electric heating coil; Equipment sizing and selection of recirculation condenser; Chiller skid system sizing and selection; High efficiency metal filter shielding input and flushing frequency; and Exhaust skid stack sizing and fan sizing.