This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department with the objective of providing a comprehensive, conservative estimate of the consequences of the criticality which could possibly occur as the result of commercial spent nuclear fuel emplaced in the underground repository at Yucca Mountain. The consequences of criticality are measured principally in terms of the resulting changes in radionuclide inventory as a function of the power level and duration of the criticality. The purpose of this analysis is to extend the prior estimates of increased radionuclide inventory (Refs. 5.52 and 5.54), for both internal and external criticality. This analysis, and similar estimates and refinements to be completed before the end of fiscal year 1997, will be provided as input to Total System Performance Assessment-Viability Assessment (TSPA-VA) to demonstrate compliance with the repository performance objectives.

fThe safe and verifiable disposition, either by incineration or chemical neutralization of chemical warfare (CW) agents requires correct {ital a priori} identification of each munition or container to be processed. A variety of NDE techniques have been used or tested for the examination and characterization of munitions. In the U.S., three widely used techniques are X-ray radiography, acoustic resonance spectroscopy (ARS), and prompt gamma ray neutron activation analysis (PINS). The technical bases, instrumental implementations, and applications of the U.S. versions of these methods are briefly discussed. 10 refs., 2 figs., 1 tab.

This document defines the waste certification program being developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in U.S. Department of Energy (DOE) Order 5820.2A, Radioactive Waste Management, and ensures that 40 CFR documentation requirements for waste characterization are met for mixed (both radioactive and hazardous) and hazardous (including polychlorinated biphenyls) waste. Program activities will be conducted according to ORNL Level 1 document requirements.

To better ensure the reliability of the Defense Waste Processing Facility (DWPF) remote canyon process equipment, a materials evaluation program was performed as part of the overall startup test program. Specific test programs included FA-04 ('Process Vessels Erosion/Corrosion Studies') and FA-05 (melter inspection). At the conclusion of field testing, Test Results Reports were issued to cover the various test phases. While these reports completed the startup test requirements, DWPF-Engineering agreed to compile a more detailed report which would include essentially all of the materials testing programs performed at DWPF. The scope of the materials evaouation programs included selected equipment from the Salt Process Cell (SPC), Chemical Process Cell (CPC), Melt Cell, Canister Decon Cell (CDC), and supporting facilities. The program consisted of performing pre-service baseline inspections (work completed in 1992) and follow-up inspections after completion of the DWPF cold chemical runs. Process equipment inspected included: process vessels, pumps, agitators, coils, jumpers, and melter top head components. Various NDE (non-destructive examination) techniques were used during the inspection program, including: ultrasonic testing (UT), visual (direct or video probe), radiography, penetrant testing (PT), and dimensional analyses. Finally, coupon racks were placed in selected tanks in 1992 for subsequent removal and corrosion evaluation after …

The general physical layout is: (1) There are a total of 9 slots, designated 1 through 9, from left to right; (2) Each slot is associated with a 96 pin Class 2 DIN 41612 (VME type) connector; (3) All even numbered slots are right handed (Connectors to the right of the card)., as would be found on a normal VME J1 backplane, these slots utilize standard DIN connectors; (4) All odd numbered slots are left handed. These slots utilize standard 96 pin Class 2 DIN 41612 connectors orientated with 180 degrees of rotation. Thus, the connector's Al position is associated with the lower right pad of the backplane for that particular connector. Likewise, the connector's C32 position is associated with the upper left pad of the backplane for that particular connector; (5) 5 layers (comp, gnd, pwr, gnd, sold); (6) .125-inch thick; and (7) Mechanical layout presented in drawing number 3823.113-MD-330044. Electrical characteristics are: (1) The backplane is routed as though it were a standard 9 slot VME J1 backplane, with 11 as the mater slot, as dermed in ANSI/IEEE 1014-1987 standard; (2) The presence of odd slots has no effect on backplane routing. At each and every slot, Al …

This report contains summaries of current and recent experiments in Particle Physics. Included are experiments at BEPC (Beijing), BNL, CEBAF, CERN, CESR, DESY, FNAL, Frascati, ITEP (Moscow), JINR (Dubna), KEK, LAMPF, Novosibirsk, PNPI (St. Petersburg), PSI, Saclay, Serpukhov, SLAC, and TRIUMF, and also several proton decay and solar neutrino experiments. Excluded are experiments that finished taking data before 1991. Instructions are given for the World Wide Web (WWW) searching of the computer database (maintained under the SLAC-SPIRES system) that contains the summaries. This report contains full summaries of 180 approved current and recent experiments in elementary particle physics. The focus of the report is on selected experiments which directly contribute to our better understanding of elementary particles and their properties such as masses, widths or lifetimes, and branching fractions.

We consider unusual events in the CDF and D0 dilepton+jets sample with very high ET(lepton) and ET(missing). It is possible, but very unlikely, that these events originate from top quark pair production; however, they have characteristics that are better accounted for by decays of supersymmetric quarks with mass in the region of 300 GeV.

In a recent set of measurements obtained by G. Kamin, W. Manning, A. Molvik, and J. Sullivan, the voltage waveform of the diode pulser had a ripple of approximately {+-} 1.3% of the 65 kV flattop voltage, and the beam current had a larger corresponding ripple of approximately {+-} 8.4% of the 1.5 mA average current at the location of the second Faraday cup, approximately 1.9 m downstream from the ion source. The period of the ripple was about 1 {micro}s. It was initially unclear whether this large current ripple was in fact a true measurement of the current or a spurious measurement of noise produced by the pulser electronics. The purpose of this note is to provide simulations which closely match the experimental results and thereby corroborate the physical nature of those measurements, and to provide predictions of the amplitude of the current ripples as they propagate to the end of linear transport section. Additionally analytic estimates are obtained which lend some insight into the nature of the current fluctuations and to provide an estimate of what the maximum amplitude of the current fluctuations are expected to be, and conversely what initial ripple in the voltage source is allowed, …

This is the Sandia National Laboratories Geothermal program plan. This is a DOE Geothermal Program planning and control document. Many of these reports were issued only in draft form. This one is of special interest for historical work because it contains what seems to be a complete list of Sandia geothermal program publications (citations / references) from about 1975 to late 1996. (DJE 2005)

The continuing objective of the Inertial Confinement Fusion (ICF) Program is the demonstration of thermonuclear fusion ignition and energy gain in the laboratory. The underlying theme of all ICF activities as a science research and development program is the Department of Energy's (DOE's) Defense Programs (DP) science-based Stockpile Stewardship and Management (SSM) Program. The extension of current program research capabilities in the National Ignition Facility (NIF) is necessary for the ICF Program to satisfy its stewardship responsibilities. ICF resources (people and facilities) are increasingly being redirected in support of the performance, schedule, and cost goals of the NIF. One of the more important aspects of ICF research is the national nature of the program. Lawrence Livermore National Laboratory's (LLNL's) ICF Program falls within DOE's national ICF Program, which includes the Nova and Beamlet laser facilities at LLNL and the OMEGA, Nike, and Trident laser facilities at the University of Rochester (Laboratory for Laser Energetics, UR/LLE), the Naval Research Laboratory (NRL), and Los Alamos National Laboratory (LANL), respectively. The Particle Beam Fusion Accelerator (PBFA) and Saturn pulsed-power facilities are at Sandia National Laboratories (SNL). General Atomics, Inc. (GA) develops and provides many of the targets for the above experimental facilities. LLNL's …

The U.S. Department of Energy (DOE) established the Tank Waste Remediation System (TWRS) Program to manage and immobilize for disposal the waste contained in underground storage tanks at the Hanford Site. The TWRS program was established as a DOE major system acquisition under an approved Justification of Mission Need (JMN) dated January 19, 1993. The JMN states that the purpose of the TWRS Program is to: Resolve the tank waste safety issues; Integrate the waste disposal mission with the ongoing waste management mission; Assess the technical bases for tank waste management and disposal; Determine the technology available and develop any needed technologies; and Establish a dedicated organization and provide the resources to meet the technical challenge. The principal objectives of management of existing and future tank wastes is to cost-effectively minimize the environmental, safety, and health risks associated with stored wastes, with reduction of safety risks given the highest priority. The potentials must be minimized for release of tank wastes to the air and to the ground (and subsequently to the groundwater) and for exposure of the operating personnel to tank wastes.

In support of the Motorola CRADA, the capabilities of the computational fluid dynamics code FIDAP (Fluid Dynamics International) for simulating problems involving fluid flow, heat transport, and chemical reactions have been assessed and enhanced as needed for semiconductor-processing applications (e.g. chemical vapor deposition). A novel method of treating surface chemical species that uses only pre-existing FIDAP commands is described and illustrated with test problems. A full-Jacobian treatment of the chemical reaction rate expressions during formation of the stiffness matrix has been implemented in FIDAP for both the Arrhenius-parameter and user-subroutine methods of specifying chemical reactions, where the Jacobian terms can be calculated analytically or numerically. This formulation is needed to obtain convergence when reaction rates become large compared to transport rates (stiff chemistry). Several test problems are analyzed, and in all cases this approach yields good convergence behavior, even for extremely stiff fluid-phase and surface reactions. A stiff segregated algorithm has been developed and implemented in FIDAP. Analysis of test problems indicates that this algorithm yields improved convergence behavior compared with the original segregated algorithm. This improved behavior enables segregated techniques to be applied to problems with stiff chemistry, as required for large three-dimensional multi-species problems.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241 BY-106. This report supports the requirements of the Tri Party Agreement Milestone M-44-09.

The Hanford Site has 149 single-shell tanks (SSTs) containing radioactive wastes that are complex mixes of radioactive and chemical products. Some of these wastes are known to generate mixtures of flammable gases, including hydrogen, nitrous oxide, and ammonia. Nineteen of these SSTs have been placed on the Flammable Gas Watch List (FGWL) because they are known or suspected, in all but one case, to retain these flammable gases. Salt well pumping to remove the interstitial liquid from SSTs is expected to cause the release of much of the retained gas, posing a number of safety concerns. Research at the Pacific Northwest National Laboratory (PNNL) has sought to quantify the release of flammable gases during salt well pumping operations. This study is being conducted for Westinghouse Hanford Company as part of the PNNL Flammable Gas Project. Understanding and quantifying the physical mechanisms and waste properties that govern gas release during salt well pumping will help to resolve the associated safety issues.

Neutron detectors are commonly used by the nuclear materials processing industry to monitor fissile materials in process vessels and tanks. The proper functioning of these neutron monitors must be periodically evaluated. We have developed and placed in routine use a PC-based multichannel analyzer (MCA) system for on-line BF3 and He-3 gas-filled detector function testing. The automated system: 1) acquires spectral data from the monitor system, 2) analyzes the spectrum to determine the detector`s functionality, 3) makes suggestions for maintenance or repair, as required, and 4) saves the spectrum and results to disk for review. The operator interface has been designed to be user-friendly and to minimize the training requirements of the user. The system may also be easily customized for various applications

Studies are underway at Yucca Mountain to characterize physical and hydrologic conditions for a potential high-level radioactive waste repository. Site characterization requires the development of three- dimensional models describing hydrogeologic units in terms of inputs for numerical models. It is also important to understand the spatial distribution of these properties, vertical and horizontally, in order to estimate values at unmeasured points. Deterministic processes of volcanism caused the initial formation of the rock units, and it is useful to be able to correlate rock properties with the more qualitative descriptions of rock lithology that occur on a larger scale. Preliminary data were collected to develop methods and evaluate spatial relations to determine sampling frequency. In addition, a data base was developed to provide some of the parameters needed for preliminary flow-modeling exercises. Surface transects of rock outcrops facilitated rapid collection of closely spaced samples of all units exposed at and around Yucca Mountain. This report presents the data collected, descriptive statistics for various units, preliminary hydrogeologic units, and analyses of porosity compared with flow properties.

A dc proton injector is being developed for a 6.7 MeV CW RFQ at Los Alamos. The RFQ input beam requirements are 75 keV energy, 110 mA dc proton current, and 0.20 {pi}mm-mrad rms normalized emittance. The injector has now produced a 75-keV, 117-mA dc proton beam (130 mA total current) with the required emittance. The emittance has been measured after a 2.1 m long two-solenoid beam transport system. The measured emittance can be explained in terms of the ion source emittance and beam transport through the focusing elements. Measured proton fractions are 90-92% of the beam current. Engineering of the accelerating column high-voltage design is being improved to increase the injector reliability. Injector design details and status are presented.

The search reaches for new gauge bosons at future hadron and lepton colliders are summarized for a variety of extended gauge models. Experiments at these energies will vastly improve over present limits and will easily discover a Z` and/or W` in the multi-TeV range.

The search reaches for both scalar(S) and vector(V) leptoquarks at future hadron colliders are summarized. In particular the authors evaluate the production cross sections of both leptoquark types at TeV33 and LHC as well as the proposed 60 and 200 TeV colliders through both quark-antiquark annihilation and gluon-gluon fusion: q{anti q},gg {r_arrow} SS,VV. Experiments at these machines should easily discover such particles if their masses are not in excess of the few TeV range.

Available experimental data on deformation and fracture behavior of polysynthetically twinned (PST) TiAl crystals are analyzed on the basis of the calculated results of bulk and defect properties and shear fault, cleavage and interfacial energies of TiAl and Ti{sub 3}Al. The extent of dissociation width of and ordinary dislocation is calculated to be larger at {alpha}{sub 2}/{gamma} and {gamma}/{gamma} interfaces by about two-fold as compared to the bulk of {gamma}-phase, suggesting the enhances slip along the interfaces when the crystal is a soft orientation. Propagation of (111) cleavage cracks is influenced by the mixed mode (II and III) of external loading applied to the coplanar deformation twinning and ordinary slip, leading to translamellar fracture. According to the calculated interfacial fracture energies, cleavage cracking si to occur on {alpha}{sub 2}/{gamma} boundaries and least likely on true-twin boundaries. Discussion is given on the roles of misfit dislocations, kinetics of dislocation-interface interactions and hydrogen embrittlement in deformation and fracture processes.

The south end cap calorimeter (ECS) will need to be moved off of the detector platform to allow for the installation of new central tracking components. This engineering note documents the cryogenic and safety issues associated with the planned move. Because of the difficulty involved in building a temporary vent line out of the building, we plan to vent the ECS condenser flow, 6 scfm N2 into the assembly hall atmosphere. Information contained herein proves that this is safe even for failure/relief conditions. The details regarding the cryogenic and safety aspects of the ECS move have been thought out and planned. The cryogenic operation of the ECS calorimeter will be limited to maintaining it's pressure by keeping it cold and isolated while it is in it's temporary position off the platform. The 4 gph liquid nitrogen flow required for this operation is easily absorbed into the DZero assembly building atmosphere without any safety concerns. Emergency or failure scenarios have been addressed on a conservative basis and also pose little threat. Other safety features built into the system such as the liquid nitrogen excess flow switch, vent line liquid sensor, and monitored ODH heads provide additional assurance that an unexpected hazard …

In April 1996, the Federal Regulatory Commission (PERC) approved Orders 888 and 889 and released a draft rule for public comment on capacity reservation tariffs (CRTs). Order No. 888 requires electric utilities to file transmission tariffs that would allow transmission access to third parties who want to conduct wholesale transactions, and Order No. 889 requires transmission-owning utilities to set up open access, same-time information systems (OASIS), using commercial software and Internet protocols. This paper discusses these Orders in detail, as well as some of the issues before FERC with implications for renewables, which include: transmission pricing; transmission terms and conditions; reassignment of transmission capacity; defining state and FERC jurisdiction over transmission and distribution; the pricing of ancillary services; and the adoption and implementation of independent system operators.

A study was done to understand the beam line optics from the beginning of Switchyard all the way to the end of Neutrino beam line. All available SWIC data were taken to get the beam centroid and width to be used in the analysis. The beam emittance and lattice function at the beginning of beam line can also be inferred from the study. The result indicated that the normalized 95% emittance to be around 15 {pi}-mm-mr for the vertical plane and about 28 {pi}-mm-mr for the horizontal plane.

Throughout history, the development of stronger materials has enabled the realization of countless technological advances. Unfortunately, any increase in strength is rarely achieved without concomitant decreases in toughness and ductility: a fact which severely limits the utility of materials such as ultrahigh-strength alloy steels. Typical precipitation-strengthened stainless steels have very little toughness at high strength levels. In the last decade, however, several investigators have reported exceptionally large fracture toughness values in high-strength precipitation-hardened metastable austenitic steels. This remarkable achievement is directly attributable to the process of transformation toughening. This report describes studies on tranformations and enhancement of plane-strain ductility in high strength steels.