This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping and Instrumentation Control (PIC) skid designed as ''L''. The ATP will be performed after the construction of the PIC skid in the shop.

Testimony issued by the General Accounting Office with an abstract that begins "Pursuant to a congressional request, GAO discussed the status of the Federal Aviation Administration's (FAA) implementation of the Display System Replacement (DSR) project, focusing on: (1) the status of FAA's overall modernization program; (2) FAA's progress in implementing DSR, with particular emphasis on events surrounding Boston's implementation; and (3) opportunities for continued success by FAA in completing its modernization projects."

We review published rapidity gap results on diffractive W and dijet production and discuss new results on diffractive b and J/{psi} production. The diffractive structure function of the proton obtained from Roman pot dijet data is presented and com- pared with expectations based on the diffractive parton densities extracted from DIS at HERA. Also presented are results on dijet production in double Pomeron exchange. Finally, we review hard double-diffractive results (rapidity gaps between jets) and present new results on soft double diffraction.

The authors present a novel miniature multi-axis driving structure that will allow positioning of two crystals with better than 50-nrad angular resolution and nanometer linear driving sensitivity.The precision and stability of this structure allow the user to align or adjust an assembly of crystals to achieve the same performance as does a single channel-cut crystal, so they call it an artificial channel-cut crystal. In this paper, the particular designs and specifications, as well as the test results,for a two-axis driving structure for a high-energy-resolution artificial channel-cut crystal monochromator are presented

In support of the x-ray synchrotrons radiation multidiffraction project of Los Alamos National Laboratory at the Advanced Photon Source (APS), we have designed and fabricated a miniature hydraulic compression load frame with 20000 N load capacity for metal specimen tests at the APS. The compact design allows the load frame to sit on the center of a 6-circle goniometer with six degrees of freedom and maximum solid angle accessibility for the incoming x-ray beam and diffraction beam detectors. A set of compact precision stages with submicron resolution has been designed for the load frame positioning to compensate the sample internal elastic and/or plastic deformation during the loading process. The system design, specifications, and test results are presented.

We use a combination of molecular dynamics and kinetic Monte Carlo simulations to explore the role of temperature and dose rate on damage accumulation in a model system with complex kinetics. We describe the accumulation of He-vacancy (HeV) complexes as well as vacancy and interstitial clusters as a function of irradiation temperature, dose, and dose rate. We show that nucleation of stable HeV complexes (voids and bubbles) at low temperature and flux takes place at extremely low doses. We also describe the effect of temperature on the HeV complex size distribution and show that growth beyond a critical nucleation size is not possible in this system at temperatures above 300 K for dose rates smaller than 10{sup -8} dpa/s. We further demonstrate that a temperature shift of 25 K per decade of flux scales the dose rate dependence of He-vacancy complex (voids and bubbles) accumulation when irradiation is carried out to low doses (0.03-0.06 dpa) at temperatures between 150 K and 300 K and dose rates of 10{sup -6}, 10{sup -7}, l0{sup -8}, and 10{sup -9} dpa/s. The results provide an atomistic description of microstructure evolution including void nucleation and the early stages of growth, and should be useful in …

Essential to today's modern refineries and the gasoline production process are fluidized catalytic cracking units. By using a computational fluid dynamics (CFD) code developed at Argonne National Laboratory to simulate the riser, parametric and sensitivity studies were performed to determine the effect of catalyst inlet conditions on the riser hydrodynamics and on the product yields. Simulations were created on the basis of a general riser configuration and operating conditions. The results of this work are indications of riser operating conditions that will maximize specific product yields. The CFD code is a three-dimensional, multiphase, turbulent, reacting flow code with phenomenological models for particle-solid interactions, droplet evaporation, and chemical kinetics. The code has been validated against pressure, particle loading, and product yield measurements. After validation of the code, parametric studies were performed on various parameters such as the injection velocity of the catalyst, the angle of injection, and the particle size distribution. The results indicate that good mixing of the catalyst particles with the oil droplets produces a high degree of cracking in the riser.

Recent advances in microfabrication techniques in conjunction with the precise growth of layers of single crystalline materials by epitaxial growth techniques allow the creation of new electro-optic microstructures. We have selectively etched compositionally modulated 111-v heterostructures to produce quantum wells (QW's) which are confined on both sides by air or vacuum. The material is patterned so to have the QW's suspended horizontally between vertical support posts. This structure is ideal for probing the local properties of solids, e.g., the interaction of quantum confined states with surface or interface states.

The LHC Interaction Region Quadrupoles (IRQ) will be shipped from Fermilab to CERN. The IRQ magnets are supported by glass fiber supports. A prototype cryostat support has been tested under various mechanical forces in order to check its mechanical behavior. These measurements have been made in order to validate a numerical model. A large range of mechanical loads simulates loads due to the shipment of the device, the weight of the cold mass as well as the cool down conditions. Its mechanical properties are measured by means of a dedicated arrangement operating at room temperature. This study appears to be essential to optimize the design of the support. The purpose of this note is to summarize the first measurements related to mechanical tests performed with the support.

The LHC Interaction Region Quadrupoles (IRQ) will be shipped from Fermilab to CERN. The IRQ magnets are supported by glass fiber supports. A prototype cryostat support has been tested under various mechanical forces in order to check its mechanical behavior. These measurements have been made in order to validate a numerical model. A large range of mechanical loads simulates loads due to the shipment of the device, the weight of the cold mass as well as the cool down conditions. Its mechanical properties are measured by means of a dedicated arrangement operating at room temperature. This study appears to be essential to optimize the design of the support. The purpose of this note is to summarize the first measurements related to mechanical tests performed with the support.

The electrometallurgical treatment of the Experimental Breeder Reactor-II (EBR-II) spent fuel has reached the end of its demonstration phase at the Fuel Conditioning Facility (FCF). During this phase sampling from the different material streams within the facility was important for both operational and safeguards activities. Compositions of samples are used in closeout of the different operational steps. In addition, sampling is an element of the MC and A measurement control program at the facility. It is used for inventory verification and confirmation. Errors associated with sampling are used in estimating the overall facility inventory difference uncertainty. This paper describes the MC and A sampling activities at FCF. The MC and A sampling program is described, which include sampling at the fuel element chopper, the electrorefiner, the casting furnace and waste sampling. Also, related sampling experiments are described. Those experiments were conducted in order to determine the sampling errors associated with the estimates of fissile material in certain material streams such as the electrorefiner's Cd pool and the metal waste ingots. Implementation of sampling procedures that led to reduction in the sampling errors are also described.

The author's assignment was to report on how I{sup 3} relates to professional societies and journals he has known, a not unreasonable request given past associations with the Materials Research Society (MRS) and its journal, JMR, particularly in their more formative years. Some recollections and some comments on current postures of MRS and JMR will be found in the section following. There are manifold anecdotes one might relate about overcoming (or not) barriers raised by disciplinary preconception and much revered institutional norms. But to what end? On recalling his own involvements and on trying to discern the common elements, the author concludes that lessons learned from such accounts are, at the detail level, too situation-specific to be generally useful while at the same time being easily generalized to a few tenets that most of us by now find obvious in principle but that provide no actionable roadmap for implementing I{sup 3} in a specific new arena. How can that be? Other contributors are submitting the I{sup 3}R challenge to scholarly analysis and reporting on significant impediments and enviable achievements. He notes that the common themes permeating the entire discussion reduce to a few fundamental aspects of human nature well known …

The Plutonium-Uranium Extraction (PUREX) Plant Storage Tunnel Number 2 (hereafter referred to as the PUREX Tunnel) was built in 1964. Since that time, the PUREX Tunnel has been used for storage of radioactive and mixed waste. In 1991, the PUREX Plant ceased operations and was transitioned to deactivation. The PUREX Tunnel continued to receive PUREX Plant waste material for storage during transition activities. Before 1995, a decision was made to store radioactive and mixed waste in the PUREX Tunnel generated from other onsite sources, on a case-by-case basis. This notice of construction (NOC) describes the activities associated with the reactivation of the PUREX Tunnel ventilation system and the transfer of up to 3.5 million curies (MCi) of radioactive waste to the PUREX Tunnel from any location on the Hanford Site. The unabated total effective dose equivalent (TEDE) estimated for the hypothetical offsite maximally exposed individual (MEI) is 5.6 E-2 millirem (mrem). The abated TEDE conservatively is estimated to account for 1.9 E-5 mrem to the MEI. The following text provides information requirements of Appendix A of Washington Administrative Code (WAC) 246-247 (requirements 1 through 18).

Research misconduct includes the fabrication, falsification, and plagiarism (FFP) of concepts or ideas; some institutions have expanded this concept to include ''other serious deviations (OSD) from accepted research practice.'' An action can be evaluated as research misconduct if it involves activities unique to the practice of science and could negatively affect the scientific record. Although the number of cases of research misconduct is uncertain (formal records are kept only by the NIH and the NSF), the costs are high in integrity of the scientific record, diversions from research to investigate allegations, ruined careers of those eventually exonerated, and erosion of public confidence in science. Currently, research misconduct policies vary from institution to institution and from government agency to government agency; some have highly developed guidelines that include OSD, others have no guidelines at ail. One result has been that the federal False Claims Act has been used to pursue allegations of research misconduct and have them adjudicated in the federal court, rather than being judged by scientific peers. The federal government will soon establish a first-ever research misconduct policy that would apply to all research funded by the federal government regardless of what agency funded the research or whether the …

A new breeding material, Sn-Li has been proposed for the APEX and ALPS programs. The key reason for proposing this material is that it has very low vapor pressure. Since both APEX and ALPS are investigating free surface flow for the blanket and divertor, respectively, low vapor pressure is a big advantage. This paper summarizes the results from a preliminary investigation. The early conclusion is that Sn-Li can be used as the coolant/breeding material for the APEX and ALPS applications. It has several attractive features, such as low vapor pressure and high thermal conductivity, but it also has some potential issues, such as material compatibility and activation. Further investigation will be required to assess the potential advantages of this material compared to other breeding materials.

This report with the attached tables provide supporting documentation for completing Performance Agreement TWR 1.2.2, C-106 Sluicing, Performance Expectation. The calculations summarized in the tables were performed using process control procedures and strategies as documented in engineering procedure HFN-SD-WM-PROC-021, Section 23.0, Rev. 2C, subsection 4.4, ''Calculation of Sludge Transferred.'' Four methods are described including: (1) Mass transfer based on Mass Flow Meter; (2) Mass transfer based on ENRAF{trademark} Densitometer density profiles; (3) Mass transfer based on ENRAF{trademark} Densitometer sediment levels; (4) Mass transfer based on dissolved solids.

The material control and accountancy system for the Fuel Conditioning Facility (FCF) initially uses calculated values for the mass flows of irradiated EBR-11 driver fuel to be processed in the electrorefiner. These calculated values are continually verified by measurements performed by the Analytical Laboratory (AL) on samples from the fuel element chopper retained for each chopper batch. Measured values include U and Pu masses, U and Pu isotopic fractions, and burnup (via La and Tc). When the measured data become available, it is necessary to determine if the measured and calculated data are consistent. This verification involves accessing two databases and performing standard statistical analyses to produce control charts for these measurements. These procedures can now be invoked via a Web interface providing: a timely and efficient control of these measurements, a user-friendly interface, off-site remote access to the data, and a convenient means of studying correlations among the data. This paper will present the architecture of the interface and a description of the control procedures, as well as examples of the control charts and correlations.