Three low-pressure rocket motor propellant burn tests were performed in a large, sealed test chamber located at the X-tunnel complex on the Department of Energy's Nevada Test Site in the period May--June 1997. NIKE rocket motors containing double base propellant were used in two tests (two and four motors, respectively), and the third test used two improved HAWK rocket motors containing composite propellant. The preliminary containment safety calculations, the crack and burn procedures used in each test, and the results of various measurements made during and after each test are all summarized and collected in this document.

The following document describes the processing, testing and post-test analysis of two Be-Cu assemblies that have successfully met the heat load requirements for the first wall and dome sections for the ITER (International Thermonuclear Experimental Reactor) fusion reactor. Several different joint assemblies were evaluated in support of a manufacturing technology investigation aimed at diffusion bonding or brazing a beryllium armor tile to a copper alloy heat sink for fusion reactor applications. Judicious selection of materials and coatings for these assemblies was essential to eliminate or minimize interactions with the highly reactive beryllium armor material. A thin titanium layer was used as a diffusion barrier to isolate the copper heat sink from the beryllium armor. To reduce residual stresses produced by differences in the expansion coefficients between the beryllium and copper, a compliant layer of aluminum or aluminum-beryllium (AlBeMet-150) was used. Aluminum was chosen because it does not chemically react with, and exhibits limited volubility in, beryllium. Two bonding processes were used to produce the assemblies. The primary process was a diffusion bonding technique. In this case, undesirable metallurgical reactions were minimized by keeping the materials in a solid state throughout the fabrication cycle. The other process employed an aluminum-silicon layer …

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This specification section defines the welding, brazing, thermal treatment, examination and testing requirements for carbon steel, and stainless steel piping.

There were two main tasks in the Clean Cast Steel Technology - Machinability and Technology Transfer Project. These were (1) determine the processing facts that control the machinability of cast steel and (2) determine the ability of ladle stirring to homogenize ladle temperature, reduce the tap and pouring temperatures, and reduce casting scrap.

This NOC application is provided to update the description of amounts of material handled, and to update the calculation of potential for emissions and resultant calculation of offsite TEDE. This NOC also includes an updated description of the various emission units at WSCF, including use of portable tanks to receive and remove liquid waste contaminated with low levels of radioactive contamination. The resultant, adjusted estimate for TEDE to the hypothetical MEI due to all combined unabated emissions from WSCF is 1.4 E-02 millirem per year. The total adjusted estimate for all combined abated emissions is 2.8 E-03 millirem per year. No single emission unit at the WSCF Complex exceeds a potential (unabated) offsite dose of 2.7 E-03 millirem per year.

A Habitat Evaluation Procedure (HEP) study was conducted on lands acquired and/or managed (4,568 acres total) by the Hellsgate Big Game Winter Range Wildlife Mitigation Project (Hellsgate project) to mitigate some of the losses associated with the original construction and operation of Grand Coulee Dam and inundation of habitats behind the dams. Three separate properties, totaling 2,224 acres were purchased in 1998. One property composed of two separate parcels, mostly grassland lies southeast of the town of Nespelem in Okanogan County (770 acres) and was formerly called the Hinman property. The former Hinman property lies within an area the Tribes have set aside for the protection and preservation of the sharp-tailed grouse (Agency Butte unit). This special management area minus the Hinman acquisition contains 2,388 acres in a long-term lease with the Tribes. The second property lies just south of the Silver Creek turnoff (Ferry County) and is bisected by the Hellsgate Road (part of the Friedlander unit). This parcel contains 60 acres of riparian and conifer forest cover. The third property (now named the Sand Hills unit) acquired for mitigation (1,394 acres) lies within the Hellsgate Reserve in Ferry County. This new acquisition links two existing mitigation parcels (the …

Thermal imagery from commercial satellites is an interesting candidate technology for use as a verification tool for the purpose of monitoring certain types of fissile material production sites. Examples of its potential treaty applications include the Fissile Material Cutoff Treaty (FMCT) or a Fissile Material Production Moratorium. To help determine the capabilities and limitations of such imagery as a monitoring tool, the author has examined archived LANDSAT-5 images of the Portsmouth Gaseous Diffusion Plant, a large US uranium-enrichment facility in Ohio. This analysis indicates that large-scale gaseous diffusion plants can very likely be recognized as operational with thermal imagery throughout most of the year in clear weather conditions. It may also be possible to identify certain other large-scale qualitative changes in operations, such as the shut-down of a single process building in a plant, by a comparison of its temperature with the temperatures of neighboring operational process buildings. However, uncertainties in the current data set prevent a definitive conclusion regarding the latter capability. This study identifies intrinsic weaknesses, including vulnerability to countermeasures, that prevent thermal imagery from satellites from being a robust standalone verification tool, even for very large enrichment plants. Nonetheless, the imagery may be useful as a trigger …

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The NIF contains a large number of optics that also act as vacuum barriers. These are subject to brittle failures that may result in significant consequences. This Fracture Control Plan identifies the requirements, needed documentation, and required actions for minimizing the potential for brittle failures of these fracture critical components in the NIF laser system. The goal of this plan is to ensure that all fracture-critical systems present no more than a low level of risk. Risk considers both consequences (to workers, the environment, and public confidence) and probability of failure. This plan interprets and implements the guidance contained in the ME Design Safety Standard, Section 5.4, ''Design Safety Standards for Fracture Critical Components for High Power Laser Systems'' (LLNL, 2000).

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An analysis of the reaction chemistry and operational factors associated with processing uranium and uranium hydride powders is presented, focusing on a specific operation in the Development Division which was subjected to the Job Hazard Analysis (JHA) process. Primary emphasis is on the thermodynamic factors leading to pyrophoricity in common atmospheres. The discussion covers feed powders, cold-pressed and hot-pressed materials, and stray material resulting from the operations. The sensitivity of the various forms of material to pyrophoricity in common atmospheres is discussed. Operational recommendations for performing the work described are given.

Because polyethylene-moderated {sup 3}He counters are rugged and reliable, they are generally the instruments of choice for field detection of fast neutrons in gamma-ray backgrounds. Their main drawback is the bulky, massive moderator needed to reduce the incident neutron energies to the sensitive range of the {sup 3}He+n capture reaction. This report discusses an optimization approach that provides a detector with uniform angular response and the maximum detection efficiency per unit mass. The key assumption is that each parameter has a geometrical interpretation and its effect on the response can be evaluated independently from that of the others. Specifically, the detection efficiency can be written as a product of separate functions for the moderator mass, gas pressure, tube position, etc., and the uniformity of the angular response is determined by the symmetry of the moderator dimensions. This analytical model was tested by compiling a comprehensive database of detector efficiencies as functions of the different parameters, including one- versus two-tube detectors, moderator masses from 1 to 6 kg, gas pressures from 1 to 20 atm, etc. In general, the model reproduced both the magnitude and angular dependence of the efficiency to within about 10%. To a high degree, the most important …

This document represents the development of a protection profile (PP) for the IEC (International Electrotechnical Commission) protocol TASE.2 (Tele-control Application Service Element.2). A protection profile states assumptions about the TOE (Target of Evaluation), identifies threats to the TOE based on the assumptions, gives security goals to counter the threats, and finally identifies security functions to satisfy the security goals. Developing protection profiles for each protocol is a significant step towards developing measurable security for electric power automation systems. As an extension of the PP, the authors offer a generalization to any protocol at the evaluation assurance level (EAL) 2.

Heterogeneous chemical reactions occurring at a gas/surface interface are fundamental in a variety of important applications, such as combustion, catalysis, chemical vapor deposition and plasma processing. Detailed simulation of these processes may involve complex, coupled fluid flow, heat transfer, gas-phase chemistry, in addition to heterogeneous reaction chemistry. This report documents the Surfkin program, which simulates the kinetics of heterogeneous chemical reactions. The program is designed for use with the Chemkin and Surface Chemkin (heterogeneous chemistry) programs. It calculates time-dependent or steady state surface site fractions and bulk-species production/destruction rates. The surface temperature may be specified as a function of time to simulate a temperature-programmed desorption experiment, for example. This report serves as a user's manual for the program, explaining the required input and format of the output. Two detailed example problems are included to further illustrate the use of this program.

NATIONAL SYNCHROTRON LIGHT SOURCE ACTIVITY REPORT FOR PERIOD, OCTOBER 1, 1998 THROUGH SEPTEMBER 30, 1999.

This report documents radionuclide air emissions from the Hanford Site in 1998 and the resulting effective dose equivalent to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (40 CFR 61), Subpart H: ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities,'' and with the Washington Administrative Code Chapter 246247, Radiation Protection - Air Emissions. The federal regulations in 40 CFR 61, Subpart H, require the measurement and reporting of radionuclides emitted from Department of Energy facilities and the resulting offsite dose from those emissions. A standard of 10 mrem/yr effective dose equivalent (EDE) is imposed on them. The EDE to the MEI due to routine emissions in 1998 from Hanford Site point sources was 1.3 E-02 mrem (1.3 E-04 mSv). which is 0.13 percent of the federal standard. Chapter 246-247 of the Washington Administrative Code (WAC) requires the reporting of radionuclide emissions from all Department of Energy Hanford Site sources. The state has adopted into these regulations the 40 CFR 61 standard of 10 mrem/yr …

Specifically this report: 1. Compares requirements of the WAP that are pertinent from a technical viewpoint with the WIPP pre-Permit waste characterization program, 2. Presents the results of a risk analysis of the currently emplaced wastes. Expected and bounding risks from routine operations and possible accidents are evaluated; and 3. Provides conclusions and recommendations.

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Because of concern over global climate change, new systems are needed that produce electricity from fossil fuels and emit less CO{sub 2}. The fundamental problem with current systems which recover and concentrate CO{sub 2} from flue gases is the need to separate dilute CO{sub 2} and pressurize it to roughly 35 atm for storage or sequestration. This is an energy intensive process that can reduce plant efficiency by 9-37% and double the cost of electricity. There are two fundamental reasons for the current high costs of power consumption, CO{sub 2} removal, and concentration systems: (1) most disposal, storage and sequestering systems require high pressure CO{sub 2} (at roughly 35 atm). Thus, assuming 90% removal of the CO{sub 2} from a typical atmospheric pressure flue gas that contains 10% CO{sub 2}, the CO{sub 2} is essentially being compressed from 0.01 atm to 35 atm (a pressure ratio of 3,500). This is a very energy intensive process. (2) The absorption-based (amine) separation processes that are used to remove the CO{sub 2} from the flue gas and compress it to 1 atm consume approximately 10 times as much energy as the theoretical work of compression because they are heat driven cycles working over …

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Long Length Contaminated Equipment Removal System Receiver Trailer and Transport Trailer require a configuration management plan for design, requirements and operations baseline documents. This report serves as the plan for the Trailers.

A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O & M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085.