The North endcap calorimeter vessel was recieved on July 1, 1990. A cooldown of the pressure vessel with liquid nitrogen was performed on July 10-11 to check the vessel's integrity. With the pressure vessel cold, the insulating vacuum was monitored for leaks. Through out the testing, the insulating vacuum remained good and the vessel passed the test. The cold test was carried out per the procedures of D-Zero engineering note 3740.220-EN-250. The test was very similar to the cold test performed on the Central Calorimeter in October of 1987. Reference D-Zero engineering notes 3740.210-EN-122, 3740.000-EN107, and 3740.210-EN-110 for information about the CC cold test. The insulating vacuum space was pumped on while equipment was being connected to the pressure vessel. Two hours after starting to pump with the blower the vacuum space pressure was at about 210 microns. Pumping on the vacuum space for the next 15 hours showed no progress and a leak detector was connected to the pumping line. A leak check showed a leak in a thermocouple feedthru on the vacuum space relief plate. After fixing the leak, the pressure dropped to 16 microns in less than one hour. A rate of rise test was performed starting …

We have developed a fast, sensitive neutron detector for recording the fusion reaction-rate history of inertial-confinement fusion (ICF) experiments. The detector is based on the fast rise-time of a commercial plastic scintillator (BC-422) and has a response < 25 ps FWHM. A thin piece of scintillator material acts as a neutron-to-light converter. A zoom lens images scintillator light to a high-speed (15 ps) optical streak camera for recording. A retractable nose cone positions the scintillator between 1 and 50 cm from a target. A simultaneously recorded optical fiducial pulse allows the streak camera time base to be calibrated relative to the incident laser power. Burn histories have been measured for deuterium-tritium filled targets with yields ranging between 10{sup 8} and 2 {times} 10{sup 13} neutrons.

The purpose of this document is to outline the K Basins 30 ton crane qualification strategy for use in the Spent Nuclear Fuel Project fuel relocation campaign.

Leak testing is being performed in 105 KW to verify the performance of the isolation barriers which have been recently installed. When an 11 inch differential head is established between the main basin and the discharge chute, a leak-rate of approximately 30 - 35 gpm is observed. The leak-rate would be achieved by a 1.65`` - 2`` diameter hole (or equivalent). Analyses suggest that the flow is turbulent/laminar transitional (dominantly turbulent), which would be indicative of a single point leak, typical of a pipe or large opening. However, local vortex rotation is observed in the entry to the West transfer chute while no observable motion was seen in the East transfer chute: this may be an indication of seal leakage in the East isolation barrier. The potential for leakage had been considered during the design and field work planning stages. Review of potential leak detection technologies had been made; at the planning stage it was determined that location specific leak detection could be established relatively quickly, applying existing K Basins technology (dye or ultrasonics). The decision was made not to pre-stage leak detection since the equipment development is highly dependent on the nature and location of the leak, and the …

This document identifies the test specification and test requirements for the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These operational testing activities, when completed, demonstrate the functional, operational and design requirements of the 200 Area TEDF have been met.

This document formally demonstrates that the Acceptance for Beneficial USE (ABU) process for the SY tank farm Multiport Riser assembly has been properly completed in accordance with the ABU checklist. For each item required on the ABU checklist, a bibliography of the documentation prepared and released to satisfy the requirement is provided

This document formally demonstrates that the ABU process for the 241-SY-101 risers 17B and 17C Multi-functional Instrument Trees (MIT`s) has been properly completed in accordance with the approved ABU checklists. For each item required on the ABU Checklist, a bibliography of the documentation prepared and released to satisfy the requirements is provided. Release of this documentation signifies that the tank farm Operations, Engineering, and Maintenance organizations have accepted responsibility for the MIT`S in 241-SY-101 Risers 17B and 17C

The Safety Basis Criteria document describes the proposed format, content, and schedule for the preparation of an updated Safety Analysis Report (SAR) and Operational Safety Requirements document (OSR) for the 324 Building. These updated safety authorization basis documents are intended to cover stabilization and deactivation activities that will prepare the facility for turnover to the Environmental Restoration Contractor for final decommissioning. The purpose of this document is to establish the specific set of criteria needed for technical upgrades to the 324 Facility Safety Authorization Basis, as required by Project Hanford Procedure HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval.

Shallow groundwater beneath the TNX Area at the Savannah River Site has been contaminated with chlorinated volatile organic compounds such as trichloroethylene and carbon tetrachloride. The Interim Action T-1 Air Stripper System began operation on September 16, 1996. A comprehensive groundwater monitoring program was initiated to measure the effectiveness of the system. The Interim Action is meeting its objectives and is capable of continuing to do so until the final groundwater remedial action is in place.

This Integrity Assessment Report (IAR) is prepared by Fluor Daniel Northwest (FDNW) under contract to Lockheed-Martin Hanford Company (LMHC) for Waste Management Hanford (WMH), the 242-A Evaporator (facility) operations contractor for Fluor Daniel Hanford, and the US Department of Energy, the system owner. The contract specifies that FDNW perform an interim (5 year) integrity assessment of the facility and prepare a written IAR in accordance with Washington Administrative Code (WAC) 173-303-640. The WAC 173-303 defines a treatment, storage, or disposal (TSD) facility tank system as the ``dangerous waste storage or treatment tank and its ancillary equipment and containment.`` This integrity assessment evaluates the two tank systems at the facility: the evaporator vessel, C-A-1 (also called the vapor-liquid separator), and the condensate collection tank, TK-C-100. This IAR evaluates the 242-A facility tank systems up to, but not including, the last valve or flanged connection inside the facility perimeter. The initial integrity assessment performed on the facility evaluated certain subsystems not directly in contact with dangerous waste, such as the steam condensate and used raw water subsystems, to provide technical information. These subsystems were not evaluated in this IAR. The last major upgrade to the facility was project B-534. The facility modifications, …

The Hanford Site covers approximately 1,450 square kilometers (560 square miles) of land that is owned by the U.S, Government and managed by the U.S. Department of Energy, Richland Operations Office (DOE-RL). The Hanford Site is located northwest of the city of Richland, Washington. The city of Richland adjoins the southeastern portion of the Hanford Site boundary and is the nearest population center. Activities on the Hanford Site are centralized in numerically designated areas. The 100 Areas, located along the Columbia River, contain deactivated reactors. The processing units are in the 200 Areas, which are on a plateau approximately 11 kilometers (7 miles) from the Columbia River. The 300 Area, located adjacent to and north of Richland, contains research and development laboratories. The 400 Area, 8 kilometers (5 miles) northwest of the 300 Area, contains the Fast Flux Test Facility previously used for testing liquid metal reactor systems. Adjacent to the north of Richland, the 1100 Area contains offices associated with administration, maintenance, transportation, and materials procurement and distribution. The 600 Area covers all locations not specifically given an area designation. This Tier Two Emergency and Hazardous Chemical Inventory report contains information pertaining to hazardous chemicals managed by DOE-RL and …

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The APS accelerator control system is a typical modern system based on the standard control system model, which consists of operator interfaces to a network and computer-controlled interfaces to hardware. The network provides a generalized communication path between the host computers, operator workstations, input/output crates, and other hardware that comprise the control system. The network is an integral part of all modern control systems and network performance will determine many characteristics of a control system. This paper describes the methods used to provide redundancy for various network system components as well as methods used to provide comprehensive monitoring of this network. The effect of archiving tens of thousands of data points on a regular basis and the effect on the controls network will be discussed. Metrics are provided on the performance of the system under various conditions.

This ATP/OTP provides procedures for testing to be performed to verify that newly procured neutron and gamma probes (reduced diameter design modifications) for operation in the Tank 241-SY-101 MlTs are compatible with existing LOW van instrumentation and hardware. A set of moisture data versus elevation will be obtained from the Tank 241-SY-101 MITs, and (optionally) from the Tank 241-AX-I01 LOW as part of this testing program.

This document outlines the steps required to properly document the acceptance testing of this prototypical device.

This acceptance Test Procedure (ATP) has been prepared to demonstrate that modifications to the Fir Protection systems function as required by project criteria. The ATP will test the Fire Alarm Control Panels, Flow Alarm Pressure Switch, Heat Detectors, Smoke Detectors, Flow Switches, Manual Pull Stations, and Gong/Door By Pass Switches.

A 1 mm square diamond photoconductive detector (PCD) has been installed on the LLNL Nova laser system, for use as a broad band soft x-ray power diagnostic. The PCD is installed behind an array of pinholes, which cast multiple, overlapping images of the source onto the diamond. This allows reduction of the x-ray intensity, to avoid saturation problems, while avoiding the spectral dependency of thin film filters. The diode current is read out on a 5 GHz bandwidth scope. The system is calibrated by comparison to an absolutely calibrated array of filtered vacuum x-ray photodiodes (XRD` s) (``dante``). The time response of the PCD and its bias electronics have been characterized using the 5th harmonic (210 nm) of a short pulse (< 1 ps) Ti:sapphire laser. The data show a fast rise, limited by the 5 GHz scope bandwidth, and a slower fall off, characterized by an RC time of order 200 ps.

The water vapor content for air in drier ducts, ovens, furnaces and the like is determined by a measurement of sound speed which is done by measuring the time difference between sound pulses reflected by two reflectors spaced a known distance apart in a guide tube. The transmitter-receiver is located at one end of the tube. The tube has enough number of holes to allow the hot moist air to get into the probe tube. A non-porous tube containing dry air placed in the same duct provides a similar measurement of dry-sound speed. The ratio of the two speeds of sound or the two measured time intervals is a simple function of the water vapor content practically independent of temperature thereby providing a very accurate measurement of water vapor content over an extremely wide range of temperatures. The sensor is accurate, immune to harsh environments, has an extremely low time constant, has absolutely no hysteresis and needs no calibration.

Adaptive Optics used for correcting low-order wavefront aberrations were tested and compared using interferometry, beam propagation, and a far-field test. Results confirm that the design and manufacturing specifications were met. Experimental data also confirms theoretical performance expectations, indicating the usefulness of these optics (especially in a laser-beam processing system), and identifying the resulting differences between the two fabrication methods used to make the optics.

Molecular level liquid phase separation was explored using modified microporous ceramic membranes with pore size reduced from 40{Angstrom} via chemical vapor deposition. At room temperature, membranes with pore sizes <30{Angstrom} were sufficient to achieve >97% rejection of naphthyl-bibenzyl-methane (NBBM) in toluene, likely attributed to the hindrance effect of NBBM through the porous avenue of the membrane. The rejection diminished dramatically as the temperature was increased. The permeance of the mixture was substantially lower than that of the solvent resulted from the interference by the solute through the transport avenue. Also, it was found that the rejection increases along with the transmembrane pressure increase, probably attributed to the pore size distribution of the membrane. The smaller pore sizes become accessible to the solvent while rejecting the solute at the higher pressure. In addition to size-based separation, active transport of molecules through an appropriate pore size at 300-400{degrees}C was observed, as a result of interaction with the surface. Decomposition of NBBM took place at 400{degrees}C in a modified membrane packed with the catalyst synthesized using the similar protocol as membranes. The separation property of this membrane at 400{degrees}C was analyzed indirectly based upon the reaction product distribution.

The Advanced Recovery and Integrated Extraction System (ARIES) demonstration combines various technologies, some of which were/are being developed under previous/other Department of Energy (DOE) funded programs. ARIES is an overall processing system for the dismantlement of nuclear weapon primaries. The program will demonstrate dismantlement of nuclear weapons and retrieval of the plutonium into a form that is compatible with long term storage and that is inspectable in an unclassified form appropriate for the application of traditional international safeguards. The success of the ARIES demonstration would lead to the development of a transportable modular or other facility type systems for weapons dismantlement to be used at other DOE sites as well as in other countries.

The goal for advanced steady-state operation in ITER should be to demonstrate the operation of the plasma core for a steady-state fusion reactor. To accomplish this the authors must develop steady-state operating scenarios at high beta for high fusion power density, low auxiliary power requirements (Q{sub CD} {ge} 25, where Q{sub CD} {triple_bond}P fusion/P{sub CD} and P{sub DC} is the power required for sustaining the plasma current) for low recirculating power requirements, and at moderate safety factor (q{sub {psi}} {le} 4.5) to minimize the cost for the tokamak core of a steady-state demonstration power reactor based on the operating modes demonstrated in ITER. The key to achieving steady-state operation at high fusion power in ITER will be the development of operating scenarios with very high bootstrap current fractions (f{sub BS} {ge} 90%) in which the radial profile of the bootstrap current density is well aligned with that of the total plasma current density, and for which the MHD {beta}-limit exceeds {beta}{sub n}{sup *} = 0.05 T{minus}m/MA. They are in the process of developing such operating modes for ITER. In {section}1 they propose two advanced steady-state operating points; a preliminary operating point that was the basis for the MHD studies reported …

This paper discusses the technical progress of a US Department of Energy Innovative Clean Coal Technology project demonstrating advanced wall-fired combustion techniques for the reduction of nitrogen oxide(NO{sub x}) emissions from coal-fired boilers. The primary objective of the demonstration is to determine the performance of two low NO{sub x} combustion technologies applied in a stepwise fashion to a 500 MW boiler. A target of achieving 50 percent NO{sub x} reductions has been established for the project. The main focus of this paper is the presentation of the low NO{sub x} burner (LNB) short and long-term tests results.

The project covered was an endeavor to (1) compare a group of laboratory instruments as airborne detectors of radioactivity and (2) simultaneously obtain data relative to the diffusion rate of radioactive contamination emitted into the atmosphere from off-gas stacks of production runs. Research was conducted in the Oak Ridge, Tennessee and Hanford, Washington areas. Detection was accomplished at a maximum distance of seventeen miles from the plant. Very little information of a conclusive nature was gained concerning the diffusion. Further research with the nuclear instruments, using a stronger source, is recommended. To obtain conclusive information concerning the meteorological aspects of the project, a larger observational program will be needed.