A method making a titanium ceramic composite involves forming a hot pressed powder body having a microstructure comprising at least one titanium metal or alloy layer and at least one ceramic particulate reinforced titanium metal or alloy layer and hot forging the hot pressed body follwed by hot rolling to substantially reduce a thickness dimension and substantially increase a lateral dimension thereof to form a composite plate or sheet that retains in the microstructure at least one titanium based layer and at least one ceramic reinforced titanium based layer in the thickness direction of the composite plate or sheet.

The Single Heater Test (SHT) is one of two in-situ thermal tests included in the site characterization program for the potential underground nuclear waste repository at Yucca Mountain. The heating phase of the SHT started in August 1996, and was completed in May 1997 after 9 months of heating. The coupled processes in the unsaturated fractured rock mass around the heater were monitored by numerous sensors for thermal, hydrological, mechanical and chemical data. In addition to passive monitoring, active testing of the rock mass moisture content was performed using geophysical methods and air injection testing. The extensive data set available from this test gives a unique opportunity to improve the understanding of the thermal-hydrological situation in the natural setting of the repository rocks. The present paper focuses on the 3-D numerical simulation of the thermal-hydrological processes in the SHT using TOUGH2. In the comparative analysis, they are particularly interested in the accuracy of different fracture-matrix-interaction concepts such as the Effective Continuum (ECM), the Dual Continuum (DKM), and the Multiple Interacting Continua (MINC) method.

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This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

The acceptance test for the Westronics driver. This driver connects the Westronics Smart Multiplexer with the TMACS monitoring system.

This document describes the formal documentation for maintaining the control system associated with the 1,000 CFM portable exhauster`s. The objective of the software configuration control plan is to provide assurances that the portable exhauster`s control system will be operable for the duration of 241-C-106 and 241-AY-102 operations (project 320). The design was based upon the criteria documented in the portable exhauster functional design criteria (HNF-SD-WM-DB-035) and procurement specification (HNF-S-0490) for the exhauster interlock systems.

The high heat content solids contained in Tank 241-C-106 are to be removed and transferred to Tank 241-AY-102 by sluicing operations, to be authorized under project W320. While sluicing operations are underway, the state of these tanks will be transformed from unagitated to agitated. This means that the partition fraction which describes the aerosol content of the head space will increase from IE-10 to IE-8 (see WHC-SD-WM-CN062, Rev. 2 for discussion of partition fractions). The head spare will become much more loaded with suspended material. Furthermore, the nature of this suspended material can change significantly: sluicing could bring up radioactive solids which normally would lay under many meters of liquid supernate. It is assumed that the headspace and filter aerosols in Tank 241-AY-102 are a 90/10 liquid/solid split. It is further assumed that the sluicing line, the headspace in Tank 241-C-106, and the filters on Tank 241-C-106 contain aerosols which are a 67/33 liquid/solid split. The bases of these assumptions are discussed in Section 3.0. These waste compositions (referred to as mitigated compositions) were used in Attachments 1 through 4 to calculate survey meter exposure rates per liter of inventory in the various system components. Three accident scenarios are evaluated: …

Fluor Daniel Hanford, Inc. (FDH) is currently adopting streamlined business processes through integrated software solutions. Replacing the legacy software (current/replacement systems, attached) also avoids significant maintenance required to resolve Year 2000 issues. This initiative is being referred to as `HANDI 2000`. The software being implemented in the first phase of this project includes Indus International`s PASSPORT Software, Peoplesoft and Primavera P3 Software. The project, which encompasses all the system replacements that will occur, has been named `HANDI 2000.` The PASSPORT applications being implemented are Inventory Management, Purchasing, Contract Management, Accounts Payable, and MSDS (Material Safety Data Sheets).

B and W Hanford Company have two Oak Ridge National Laboratory (ORNL) Type 4 canisters filled with cesium chloride (CsCl) originally produced at WESF (Waste Encapsulation and Storage Facility). These canisters are constructed of 304L stainless steel per drawing ORNL 970-294. Instead of removing the CsCl from the Type 4 canisters and repacking into an Inner Capsule, it is intended (for ALARA, schedule and cost purposes) that the Type 4 canisters be decontaminated (scrubbed) and placed [whole] inside a Type ``W`` overpack. The overpack is constructed from 316L stainless steel. Several tests have been run by Pacific Northwest National Laboratory (PNNL) over the. years documenting the corrosion compatibility of 316L SS with CsCl (Bryan 1989 and Fullam 1972). However, no information for 304L SS compatibility is readily available. This document estimates the corrosion resistance of 304L stainless steel in a WESF CsCl environment as it compares with that of 316L stainless steel.

This document provides estimates of the volume of sludge (1) expected from Integrated Process Strategy (IPS) processing of the fuel elements and (2) in the fuel storage canisters in K West Basin. The original estimates were based on visual observations of fuel element condition in the basin and laboratory measurements of KE canister sludge density. Revision 1 revised the volume estimates of sludge based on additional data from evaluations of material from the KW Basin fuel subsurface examinations and KW canister sludge characterization data. A nominal Working Estimate and an upper level Working Bound is developed for the canister sludge and the fuel wash sludge components in the KW Basin.

The US Department of Energy (DOE), established in the K Basin Spent Nuclear Fuel Project Regulatory Policy, dated August 4, 1995 (hereafter referred to as the Policy), the requirement for new Spent Nuclear Fuel (SNF) Project facilities to achieve nuclear safety equivalency to comparable US Nuclear Regulatory Commission (NRC)-licensed facilities. For activities other than during transport, when the Multi-Canister Overpack (MCO) is used and resides in the Canister Storage Building (CSB), Cold Vacuum Drying (CVD) facility or Hot Conditioning System, additional NRC requirements will also apply to the MCO based on the safety functions it performs and its interfaces with the SNF Project facilities. An evaluation was performed in consideration of the MCO safety functions to identify any additional NRC requirements needed, in combination with the existing and applicable DOE requirements, to establish nuclear safety equivalency for the MCO. The background, basic safety issues and general comparison of NRC and DOE requirements for the SNF Project are presented in WHC-SD-SNF-DB-002.

The Environmental Compliance Program is developing and implementing a PHMC-wide chemical management system with the goal being to: (1) manage and control chemicals from procurement through use and final disposition; (2) develop and maintain procedures for identifying and evaluating hazards and environmental impacts present in facilities, and the hazard classification of the facilities. The US Department of Energy (DOE) may promulgate the final rule, 1 0 CFR 834, Radiation Protection of the Public and the Environment in FY 1999. This rule establishes controls for the release of radioactive material and limits for the amount of radiation exposure to the public and the environment. It will be applicable to activities of DOE contractors at the Hanford site. This rule is expected to replace the bulk of DOE Orders 5400.5, Radiation Protection of the Public and the Environment and 5400. 1, General Environmental Protection Program. In doing so, these Orders will be backed by the Price-Anderson enforcement procedures and carry penalties for non-compliance.

The purpose of this engineering study is to investigate the available technology related to dissolution of the K Basin sludge in nitric acid. The conclusion of this study along with laboratory and hot cell tests with actual sludge samples will provide the basis for beginning conceptual design of the sludge dissolver. The K Basin sludge contains uranium oxides, fragments of metallic U, and some U hydride as well as ferric oxyhydroxide, aluminum oxides and hydroxides, windblown sand that infiltrated the basin enclosure, ion exchange resin, and miscellaneous materials. The decision has been made to dispose of this sludge separate from the fuel elements stored in the basins. The sludge will be conditioned so that it meets Tank Waste Remediation System waste acceptance criteria and can be sent to one of the underground storage tanks. Sludge conditioning will be done by dissolving the fuel constituents in nitric acid, separating the insoluble material, adding neutron absorbers for criticality safety, and then reacting the solution with caustic to co-precipitate the uranium and plutonium. There will be five distinct feed streams to the sludge conditioning process two from the K East (KE) Basin and three from the K West (KW) Basin. The composition of …

This document provides estimates of the volume of sludge expected from Integrated Process Strategy (IPS) processing of the fuel elements and in the fuel storage canisters in K East Basin. The original estimates were based on visual observations of fuel element condition in the basin and laboratory measurements of canister sludge density. Revision 1 revised the volume estimates of sludge from processing of the fuel elements based on additional data from evaluations of material from the KE Basin fuel subsurface examinations. A nominal Working Estimate and an upper level Working Bound is developed for the canister sludge and the fuel wash sludge components in the KE Basin.

This engineering study looks at the solids/liquids separation unit operations after the acid dissolution of the K Basin sludge treatment. Unit operations considered were centrifugation, filtration (cartridge, cross flow, and high shear filtration) and gravity settling. The recommended unit operations for the solids/liquids separations are based upon the efficiency, complexity, and off-the-shelf availability and adaptability. The unit operations recommended were a Robatel DPC 900 centrifuge followed by a nuclearized 31WM cartridge filter. The Robatel DPC 900 has been successfully employed in the nuclear industry on a world wide scale. The 31WM cartridge filter has been employed for filtration campaigns in both the government and civilian nuclear arenas.

Aluminum hydroxide coatings on fuel elements stored in aluminum canisters in K West Basin were measured in July and August 1998. Good quality data was produced that enabled statistical analysis to determine a bounding value for aluminum hydroxide at a 99% confidence level. The updated bounding value is 10.6 kg per Multi-Canister Overpack (MCO), compared to the previously estimated bounding value of 8 kg/MCO. Thermal analysis using the updated bounding value, shows that the MCO generates oxygen concentrate that are below the lower flammability limits during the 40-year interim storage period and are, therefore, acceptable.

This engineering study evaluates the use of physical separation technologies to separate organic ion exchange resin from KE Basin sludge prior to nitric acid dissolution. This separation is necessitate to prevent nitration of the organics in the acid dissolver. The technologies under consideration are: screening, sedimentation, elutriation. The recommended approach is to first screen the Sludge and resin 300 microns then subject the 300 microns plus material to elutriation.

The Hanford Business Structure integrates the project`s technical, schedule, and cost baselines; implements the use of a standard code of accounts; and streamlines performance reporting and cost collection. Technical requirements drive the technical functions and come from the RDD 100 database. The functions will be identified in the P3 scheduling system and also in the PeopleSoft system. Projects will break their work down from the technical requirements in the P3 schedules. When the level at which they want to track cost via the code of accounts is reached, a Project ID will be generated in the PeopleSoft system. P3 may carry more detailed schedules below the Project ID level. The standard code of accounts will identify discrete work activities done across the site and various projects. They will include direct and overhead type work scopes. Activities in P3 will roll up to this standard code of accounts. The field that will be used to record this in PeopleSoft is ``Activity``. In Passport it is a user-defined field. It will have to be added to other feeder systems. Project ID and code of accounts are required fields on all cost records.

On September 9, 1992, the US Environmental Protection Agency (EPA) issued General Permit No. WA-R-00-OOOF, Authorization to Discharge Under the National Pollutant Discharge Elimination System (NPDES) for Storm Water Discharges Associated with Industrial Activity to the US Department of Energy, Richland Operations Office (DOE-RL). DOE-RL submitted a Notice of Intent to comply with this permit to the EPA in accordance with the General Permit requirements on October 1, 1992. On February 14, 1994, EPA issued a Storm Water General Permit Coverage Notice (WA-R-00-Al 7F). The Hanford Site Storm Water Pollution Prevention Plan (SWPPP) (WHC-SD-EN-EV-02 1) was certified by DOE-RL on September 24, 1996, in compliance with Part 4.B(i) of the General Permit. As required by General Permit, Section 4, Part D, Section 4.c, an annual report must be developed by DOE-RL and retained onsite to verify that the requirements listed in the General Permit are implemented. This document fulfills the requirement to prepare an annual report and contains the results of inspections of the storm water discharges listed in Appendix B. This report also describes the methods used to conduct the Storm Water Comprehensive Site Compliance Evaluation (SWCSCE) as required in the General Permit, Part 4, Section D.4.c; summarizes the …

Costing labor in the Financial Data System has traditionally been done using standard rates based on type of employee by organization. This methodology will change with the implementation of the PeopleSoft financial system. Labor in the new environment will be cost against actual dollars and marked up with an employee adder, to cover absences and fringe benefits.

This document defines requirements for an upgrade of the Sodium Removal System (SRS) control system. The upgrade is being performed to solve a number of maintainability and operability issues. The upgraded system will provide the same functions, controls and interlocks as the present system, and in addition provide enhanced functionality in areas discussed in this document.

Department of Energy (DOE) Policy (P) 450.4, Safety Management System Policy, commits to institutionalization of an Integrated Safety Management System (ISMS) throughout the DOE complex. The DOE Acquisition Regulations (DEAR, 48 CFR 970) requires contractors to manage and perform work in accordance with a documented Integrated Safety Management System (ISMS). Guidance and expectations have been provided to PNNL by incorporation into the operating contract (Contract DE-ACM-76FL0 1830) and by letter. The contract requires that the contractor submit a description of their ISMS for approval by DOE. PNNL submitted their proposed Safety Management System Description for approval on November 25,1997. RL tentatively approved acceptance of the description pursuant to a favorable recommendation from this review. The Integrated Safety Management System Verification is a review of the adequacy of the ISMS description in fulfilling the requirements of the DEAR and the DOE Policy. The purpose of this review is to provide the Richland Operations Office Manager with a recommendation for approval of the ISMS description of the Pacific Northwest Laboratory based upon compliance with the requirements of 49 CFR 970.5204(-2 and -78); and to verify the extent and maturity of ISMS implementation within the Laboratory. Further the review will provide a model …