In the FFTF Shutdown Program, sodium from the primary and secondary heat transport loops, Interim Decay Storage (IDS), and Fuel Storage Facility (FSF) will be transferred to four large storage tanks for temporary storage. Three of the storage tanks will be cylindrical vertical tanks having a diameter of 28 feet, height of 22 feet and fabricated from carbon steel. The fourth tank is a horizontal cylindrical tank but is not the subject of this report. The storage tanks will be located near the FFTF in the 400 Area and rest on a steel-lined concrete slab in an enclosed building. The purpose of this work is to document the thermal analyses that were performed to ensure that the vertical FFTF sodium storage tank design is feasible from a thermal standpoint. The key criterion for this analysis is the time to heat up the storage tank containing frozen sodium at ambient temperature to 400 F. Normal operating conditions include an ambient temperature range of 32 F to 120 F. A key parameter in the evaluation of the sodium storage tank is the type of insulation. The baseline case assumed six inches of calcium silicate insulation. An alternate case assumed refractory fiber (Cerablanket) …

This project covers four CRADAS (Cooperative Research and Development Agreements) which were initiated in 1991 and 1993. The two CRADAS with the state of Tennessee and the state of Florida were to provide technical assistance to small manufacturers in those states and the CRADA with the Tennessee Technology Foundation was to engage in joint economic development activities within the state. These three CRADAS do not fit the traditional definition of CRADAS and would be administered by other agreement mechanisms, today. But in these early days of technology transfer efforts, the CRADA mechanism was already developed and usable. The CRADA with Coors Ceramics is a good example of a CRADA and was used to develop nondestructive testing technology for ceramic component inspection. The report describes the background of this project, its economic impact, and its benefits to the U. S. Department of Energy.

In the FFTF Shutdown Program, sodium from the primary and secondary heat transport loops, Interim Decay Storage (IDS), and Fuel Storage Facility (FSF) will be transferred to four large storage tanks for temporary storage. Three of the drain tanks will be cylindrical vertical tanks having a diameter of 28 feet, height of 22 feet and fabricated from carbon steel. The vertical tanks were the subject of a previous report and are not the subject of this report. The fourth tank is a horizontal cylindrical tank 18 feet in diameter, having an overall length of 31 feet and fabricated from carbon steel. The purpose of this work is to document the thermal analyses that were performed to ensure that the FFTF horizontal sodium storage tank design is feasible from a thermal standpoint. The key criterion for this analysis is the time to heat up the storage tank containing frozen sodium at ambient temperature to 400 F. Normal operating conditions include an ambient temperature range of 32 F to 120 F. A key parameter in the evaluation of the sodium drain tank is the type of insulation. The baseline case assumed four inches of calcium silicate insulation. An alternate case assumed refractory …

In the Spring of 1996, Site Acceptance Tests were performed for the 2 Imaging Passive/Active Neutron (IPAN) assay systems installed in the WRAP I Facility. This report includes the test documentation and the completed test checklists, with comments and resolutions. All testing was completed, with comments resolved by August 1996.

This Criticality Safety Evaluation Report addendum extends the coverage of the original CSAR (90-006) about dismantling the ductwork in 232-Z to include cleanout of the Scrubber Glovebox, with an estimated residual Pu holdup of less than 200 grams. The procedures for keeping any materials inside or removed dry is retained as part of the qualification as a Limited Control Facility.

This paper reviews the designs and performance of tubular solid oxide fuel cells (SOFCs). A large number of tubular cells of the porous support tube type have been electrically tested, some to times over 50,000 hours; these cells have shown excellent performance and performance stability. Since 1984, successfully larger electrical generators utilizing these cells have been built and operated; a 20 kW integrated SOFC system operated for 7064 hours during 1993-1994. Results of development efforts to reduce cost and increase power output of tubular cells by eliminating porous support tube and increasing active length are described, and plans to utilize such air electrode supported cells in future SOFC systems are discussed.

The Energy Policy Act of 1992 (Act) requires the Department of Energy to retain ownership and responsibility for the costs of environmental cleanup resulting from the Government`s operation of the three gaseous diffusion facilities located at the K-25 site in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. The Act transferred the uranium enrichment enterprise to the United States Enrichment Corporation (USEC) as of July 1, 1993, and established the Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) to: Pay for the costs of decontamination and decommissioning at the diffusion facilities; pay the annual costs for remedial action at the diffusion facilities to the extent that the amount in the Fund is sufficient; and reimburse uranium/thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government.

This document estimates the temperature of the sludge inventory projected to be stored in the K East Basin Weasel Pit during the Spent Nuclear Fuel Project. Hydrogen generation rates are also estimated. Since many of the needed sludge properties are not well known, the analysis considered a range values to show the sensitivity of the results.

Project W-320 Acceptance Test Report for Cathodic Protection Rectifier 47, C-Farm Electrical

This document provides a record closed out System Change Request No. 101-200 used during the development of the 241-SY-101 Hydrogen Mitigation Project Data Acquisition Control System.

The charge and mass of the projectile-like fragments produced in the 12-MeV/nucleon {sup 56}Fe + {sup 165}Ho reaction were measured at a laboratory scattering angle of 16 degrees. The mass and charge distributions of the projectile-like fragments were generated as a function of total kinetic energy loss (TKEL), and characterized by their neutron and proton centroids and variances, and correlation factors. A weak drift of the system towards mass asymmetry, opposite to the direction which minimizes the potential energy of the composite system, was observed. The increase in the variances with energy loss is consistent with a nucleon exchange mechanism as a means for energy dissipation. Predictions of two nucleon exchange models, Randrup`s and, Tassan-Got`s models, are compared to the experimental results of the 672-MeV {sup 56}Fe + {sup 165}Ho reaction and to other Fe-induced reactions. The proton and neutron centroids were found to be generally better reproduced by Tassan-Got`s model than by Randrup`s model. The variances and correlation factor are well reproduced for asymmetric systems by both models.

Modicon Compact Programmable Logic Controller (PLC). The device configuration integrates the isolation and current- carrying capacities of mechanical relays with the logic and programming sophistication of the PLC. This revised document provides descriptions of components and tasks involved in the PLC system for controlling and monitoring the FGTEI. All control functions required by the PLC, and how they are implemented, are described in detail.

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 22-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-201.

Test procedures and data are presented for automatic guided vehicles

The air balance documents the attained air flows, air pressure differences and transient responses to simulated glovebox breach and power loss conditions.

This report summarizes the sampling activities undertaken and the analytical results obtained in a concrete sampling and analyses study performed for the 300 Area Solvent Evaporator (300 ASE) closure site. The 300 ASE is identified as a Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) unit that will be closed in accordance with the applicable laws and regulations. No constituents of concern were found in concentrations indicating contamination of the concrete by 300 ASE operations.

This document describes the permitting plan for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). A comprehensive review of environmental regulations have indicated that several environmental reviews [e.g. National Environmental Policy Act (NEPA), State Environmental Policy Act (SEPA)], permits, and approvals are required prior to construction or operation of the facility. The environmental reviews, permits and approvals, as well the regulatory authority, potentially applicable to the Tank 241-C-106 WRSS include the following: for NEPA - U.S. Department of Energy-Headquarters: Action Description Memorandum, Environmental Assessment, Categorical Exclusion, and Environmental Impact Statement; and for SEPA - State of Washington Department of Ecology (Ecology) Determination of Nonsignificance, Mitigated Determination of Nonsignificance, Determination of Significance, and SEPA Environmental Checklist.

SciTech, an interactive science and technology center located 45 miles west of Chicago, is dedicated to providing hands-on and minds-on experiences that explore the spectrum of science and mathematics. SciTech opened at its present location during the summer of 1990 in Aurora, a changing community with a large minority population. Since then, SciTech has received over 331,000 visitors from the entire Chicago metropolitan area. There are now more than 250 exhibits housed in the museum. SciTech has grown quickly in part due to the strong volunteer support from the research and development corridor population it serves, as well as through international ties. SciTech has become known as an innovative force in the science museum community for its original exhibits and unique youth and school programs. SciTech`s traveling outreach program, ``Museum in a School,`` has served over 391 public and private schools in 111 districts in the Chicago metropolitan area, and has reached over 3,099 teachers and 98,837 students throughout its history. This program serves a wide variety of students, including bilingual, economically depressed, and learning impaired. SciTech is concerned with every American`s need for increasing basic science literacy.

This is the acceptance test report for pressure decay tests performed on newly-installed 241-AW Tank Farm primary ventilation system air inlet filter stations.

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Vectra GSI, Inc. was one of seven vendors selected for Phase 1 of the melter demonstration tests using simulated LLW that were completed during fiscal year 1995. The attached report prepared by Vectra GSI, Inc. describes results of melter testing using slurry feed and dried feeds. Results of feed drying and prereaction tests using a fluid bed calciner and rotary dryer also are described.

The purpose of this guide is to describe the documents and record series at the K-25 plant that pertain to the handling of waste containing cesium-137 produced as a result of processes to enrich uranium and separate plutonium at the Department of Energy`s (DOE) Oak Ridge National Laboratory (ORNL) and Oak Ride Gaseous Diffusion Plant (ORGDP, called K-25) in Oak Ridge, Tennessee. History Associates Incorporated (HAI) prepared this guide as part of DOE`s Epidemiologic Records Inventory Project, the purpose of which is to verify and conduct inventories of epidemiologic and health-related records at various DOE and DOE contractor sites. This introduction briefly describes the Epidemiologic Records Inventory Project and HAI`s role in it. Specific attention is given to the history of the DOE-Oak Ridge Reservation, the history and development of the K-25 plant, the creation and handling of cesium-contaminated waste, and environmental monitoring efforts at ORNL and K-25 from the late 1940s to the present. This introduction also presents the methodology used to identify the documents and series pertaining to cesium, a discussion of the inventory of these documents, information concerning access to the site and the records, and a description of the arrangement of the chapters.

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-202.

This laser is a tunable source designed for applications where a shorter pulse will be chopped from a long Q-switched pulse by electrooptic modulators, then amplified in Nd:phosphate glass. The laser employs ytterbium-doped silica fiber as the gain medium, pumped by a laser diode at 980nm. Gain in Yb:silica is distributed over an 90nm range, making it suitable for operation at many wavelengths. Our previous experiments with this medium demonstrated oscillation over a 50nm wide band. In addition, pumping at 980nm allows the use of stable pump diodes used in erbium-doped fiber amplifiers (EDFA`s). We designed the laser to take advantage of this wideband gain medium, and yet operate on a single cavity mode. A circulator causes unidirectional operation, and allows use of a fiber grating in reflection. This grating has a 0.2 Angstrom bandwidth, and defines the coarse tuning of the laser. It is piezoelectrically stretch tuned to the desired wavelength band. A single mode of the cavity is selected by a piezoelectrically tuned fiber grating Fabry-Perot etalon with 64MHz bandwidth. The laser is Q-switched by a bulk acousto-optic device at lkhz reprate. The loss is controlled to allow the oscillator to lase close to threshold for 500{micro}s before …

Highly enriched uranium (HEU) at the Oak Ridge Y-12 Plant was the initial US excess fissile material to be placed under International Atomic Energy Agency (IAEA) safeguards. This presentation describes the setting in which the US offer was made and five lessons learned from that experience which are: Lesson 1--Things may happen quickly; Lesson 2--Facility and supporting areas must provide for need of the IAEA to perform their inspection activities; Lesson 3--Familiarize site personnel with IAEA safeguards; Lesson 4--Prepare for the initial inventory verification; and Lesson 5--Prepare for inspections.