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.

This report presents the results of sampling and chemical analyses at Hanford Reservation. The samples were analyzed by Thermo-Analytic Laboratories and Roy F. Weston Laboratories using US Environmental Protection Agency CLP protocols. Sample analyses included: volatile organics; semivolatile organics; inorganics; and general chemical parameters. The data from the chemical analyses were reviewed and validated to verify that reported sample results were of sufficient quality to support decisions regarding remedial actions performed at this site.

This report summarizes and documents the results of the radiological surveys conducted from February 11 through February 17 and March 30, 1993 over the 618-10 Burial Ground, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 618-10 Burial Ground radiological survey field task consisted of two activities: characterization of the specific background conditions and the radiological survey of the area. The radiological survey of the 618-10 Burial Ground, along with the background study, were conducted by Site Investigative Surveys Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology was based on utilization of the Ultrasonic Ranging and Data System (USRADS) for automated recording of the gross gamma radiation levels at or near six (6) inches and at three (3) feet from the surface soil.

This report summarizes and documents the results of the radiological surveys conducted from February 4 through February 10, 1993 over the 618-11 Burial Ground, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 618-11 Burial Ground radiological survey field task consisted of two activities: characterization of the specific background conditions and the radiological survey of the area. The radiological survey of the 618-11 Burial Ground, along with the background study, were conducted by Site Investigative Surveys Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology was based on utilization of the Ultrasonic Ranging and Data System (USRADS) for automated recording of the gross gamma radiation levels at or near six (6) inches and at three (3) feet from the surface soil.

On October 22, 1990 an agreement was entered into between the US DOE and the State of New Mexico. The agreement was designed to assure the citizens of New Mexico that the environment is protected and that public health, as related to the environment is also protected. The Agreement reflects the understanding and commitments between the parties regarding environmental oversight, monitoring, remediation and emergency response at the following DOE facilities: the Inhalation Toxicology Research Institute (ITRI); Los Alamos National Laboratory (LANL); Sandia National Laboratory (SNL); and the Waste Isolation Pilot Plant (WIPP). These provision are ongoing through a vigorous program of independent monitoring and oversight; prioritization of clean-up and compliance activities; and new commitments by DOE. While the initial assessment of the quality and effectiveness of the facilities` environmental monitoring and surveillance programs is not yet complete, preliminary findings are presented regarding air quality monitoring, environmental monitoring, and groundwater monitoring.

This report presents plans for environmental restoration and waste management activities at the Idaho National Engineering Laboratory for fiscal year 1994. This years`s plan focuses on issues affecting the Environmental Restoration and Waste Management Programs. The Environmental Restoration Program is concerned with all aspects of assessment and cleanup of inactive operations. It involves assessing and cleaning up (where necessary) inactive INEL waste areas that could release harmful substances into the environment, as well as safely managing surplus nuclear facilities. The Waste Management program involves treatment, storage, and disposal of radioactive, hazardous, mixed, and industrial waste by DOE activities. This program is designed to protect the safety of INEL employees, the public, and the environment in the design, construction, maintenance, and operation of INEL treatment, storage, and disposal facilities. It operates facilities in a cost-effective, environmentally sound, regulatory compliant, and publicly acceptable manner.

The septic 2607-W6 which supports the 222-S complex is operating at 200% capacity. The septic tank has been inspected and found to be sound. Test hole excavations of the existing drainfield indicate that it is disposing of the current waste water effluent load as opposed to treating it. The system is over 40 years old and has not been approved by the Washington State Department of Health. Under the existing operating conditions it is subject to imminent failure. No additional tie-ins or increases in personnel are allowed which will increase the flow to the 2607-W6 system.

The AC susceptibility (X{prime}, X{double_prime}) has bee measured in a single crystal of the organic superconductor K-(ET){sub 2}Cu(NCS){sub 2} ({Tc} = 9.5 K) as a function of the DC magnetic field, for several frequencies (10 {sup 2} Hz <f <10{sup 4} Hz) and different AC fields (l{mu}T <h{sub dc} <300{mu}T) at fixed temperatures.

Experimentation validated a simple moisture conditioning scheme to prepare Gr/Ep composite parts for precision applications by measuring dimensional changes over 90 days. It was shown that an elevated temperature moisture conditioning scheme produced a dimensionally stable part from which precision structures could be built/machined without significant moisture induced dimensional changes after fabrication. Conversely, that unconditioned Gr/Ep composite panels exhibited unacceptably large dimensional changes (i.e., greater than 125 ppM). It was also shown that time required to produce stable parts was shorter, by more than an order of magnitude, employing the conditioning scheme than using no conditioning scheme (46 days versus 1000+ days). Two final use environments were chosen for the experiments: 50% RH/21C and 0% RH/21C. Fiberite 3034K was chosen for its widespread use in aerospace applications. Two typical lay-ups were chosen, one with low sensitivity to hygrothermal distortions and the other high sensitivity: [0, {plus_minus} 45, 90]s, [0, {plus_minus} 15, 0]s. By employing an elevated temperature, constant humidity conditioning scheme, test panels achieved an equilibrium moisture content in less time, by more than an order of magnitude, than panels exposed to the same humidity environment and ambient temperature. Dimensional changes, over 90 days, were up to 4 times lower …

In device structures with dimensions comparable to carrier inelastic scattering lengths, the quantum nature of carriers will cause interference effects that cannot be modeled by conventional techniques. The basic equations that govern these ``quantum`` circuit elements present significant numerical challenges. The authors describe the block recursion method, an accurate, efficient method for solving the quantum circuit problem. They demonstrate this method by modeling dirty inversion layers.

The primary of this project are the development of (1) a general stochastic model for DNA sequencing errors (2) algorithms to restore the original DNA sequence and (3) statistical methods to assess the accuracy of this restoration. A secondary objective is to develop new algorithms for fragment assembly. Initially a stochastic model that assumes errors are independent and uniformly distributed will be developed. Generalizations of the basic model will be developed to account for (1) decay of accuracy along fragments, (2) variable error rates among fragments, (3) sequence dependent errors (e.g. homopolymeric, runs), and (4) strand--specific systematic errors (e.g. compressions). The emphasis of this project will be the development of a theoretical basis for determining sequence accuracy. However, new algorithms are proposed and these will be implemented as software (in the C programming language). This software will be tested using real and simulated data. It will be modular in design and will be made available for distribution to the scientific community.

The Active Sites Environmental Monitoring Program (ASEMP), initiated in 1989, provides early detection and performance monitoring of active low-level-waste (LLW) and transuranic (TRU) waste facilities at Oak Ridge National Laboratory (ORNL). Several changes have recently occurred in regard to the sites that are currently used for waste storage and disposal. These changes require a second set of revisions to the ASEMP program plan. This document incorporates those revisions. This program plan presents the organization and procedures for monitoring the active sites. The program plan also provides internal reporting levels to guide the evaluation of monitoring results.

The ZGS people went off in every direction: to universities, to other laboratories, to universities and laboratories in other countries, and to other occupations in the private sector or federal agencies. Some people even cycled around through one or more of the above and eventually would up back to Argonne. As a good pupil of the David Manson school of weasel words. I recognize the need to insert a {open_quotes}to the best of my knowledge{close_quotes} disclaimer statement here. It became clear to me that I couldn`t vouch for the accuracy of all of the information shown below when, to my surprise and delight, I found on the official registration list for this conference the names of people I really, really, never expected to see again!

The Tenth International Symposium on ALCOHOL FUELS ``THE ROAD TO COMMERCIALIZATION`` was held at the Broadmoor Hotel, Colorado Springs, Colorado, USA November 7--10, 1993. Twenty-seven papers on the production of alcohol fuels, specifications, their use in automobiles, buses and trucks, emission control, and government policies were presented. Individual papers have been processed separately for entry into the data base.

Demonstration of a direct coal-fueled gas turbine system that is environmentally, technically, and economically viable depends on the satisfactory resolution of several key issues. Solar Turbines, Incorporates technical approach to these issues was to advance a complete direct coal-fueled gas turbine system that incorporated near-term technology solutions to both historically demonstrated problem areas such as deposition, erosion, and hot end corrosion, and to the emergent environmental constraints based on NO{sub x}, SO{sub x}, and particulates. Solar`s program approach was keyed to the full commercialization of the coal-fueled cogeneration gas turbine which would occur after extended field verification demonstrations conducted by the private sector. The program was structured in three phases plus an optional fourth phase: Phase 1 -- system description; Phase 2 -- component development; Phase 3 -- prototype system verification; and Phase 4 -- field evaluation.

The Hall process has always suffered from important problems, among which is the use of consumable carbon anodes, hence, attempts had been made in the past to find an inert anode. A different approach was taken in the present research: a metal anode covered by a protective oxide film is operated so that the film is thick enough to prevent chemical attack of underlying metal, yet thin enough to allow electric current to pass without increase in cell voltage. Specimens of various candidate alloy compositions (Cu-Al, Ni-Al, Cr-Al, Fe-Cr-Al) were electrolyzed; results are promising. Areas for further research on nonconsumable anode for Hall cell are outlined.

Fast neutrons have been used to treat over 15,000 cancer patients worldwide and proton therapy is rapidly emerging as a treatment of choice for tumors around critical anatomical structures. Neutron therapy requires evaluated data to {approximately}70 MeV while proton therapy requires data to {approximately}250 MeV. Collaboration between Lawrence Livermore National Laboratory (LLNL) and the medical physics community has revealed limitations in nuclear cross section evaluations and radiation transport capabilities that have prevented neutron and proton radiation therapy centers from using Monte Carlo calculations to accurately predict dose in patients. These evaluations require energy- and angle-dependent cross sections for secondary neutrons, charged-particles and recoil nuclei. We are expanding the LLNL nuclear databases to higher energies for biologically important elements and have developed a three-dimensional, all-particle Monte Carlo radiation transport code that uses computer-assisted-tomography (CT) images as the input mesh. This code, called PEREGRINE calculates dose distributions in the human body and can be used as a tool to determine the dependence of dose on details of the evaluated nuclear data. In this paper, we will review the status of the nuclear data required for neutron and proton therapy, describe the capabilities of the PEREGRINE package, and show the effects of tissue …

We review the development of the ultrafast scanning tunneling microscope. Experimental results on the tunneling gap response to a short voltage pulse excitation are presented.

An aerial radiological survey was conducted over the Fort Calhoun Nuclear Power Plant in Fort Calhoun, Nebraska, during the period June 19 through June 28, 1993. The survey was conducted at an altitude of 150 feet (46 meters) over a 25-square-mile (65-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Fort Calhoun Nuclear Power Plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 12 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and potassium. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey was conducted on August 9 and 10, 1972, before the plant began operation. Exposure rates measured in both surveys were consistent with normal terrestrial background.

An aerial radiological survey was conducted over the Oyster Creek Nuclear Power Plant in Forked River, New Jersey, during the period September 18 through September 24, 1992. The survey was conducted at an altitude of 150 feet (46 meters) over a 26-square-mile (67-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Oyster Creek Nuclear Power plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 4 and 10 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey of the power plant was conducted in August 1969 during its initial startup phase. Exposure rates and radioactive isotopes revealed in both surveys were consistent and within normal terrestrial …

Puncturing of aerosol cans is performed in the Waste Receiving and Processing Facility Module 1 (WRAP 1) process as a requirement of the waste disposal acceptance criteria for both transuranic (TRU) waste and low-level waste (LLW). These cans have contained such things as paints, lubricating oils, paint removers, insecticides, and cleaning supplies which were used in radioactive facilities. Due to Westinghouse Hanford Company (WHC) Fire Protection concerns of the baseline system`s fire/explosion proof characteristics, a study was undertaken to compare the baseline system`s design to commercially available puncturing devices. While the study found no areas which might indicate a risk of fire or explosion, WHC Fire Protection determined that the puncturing system must have a demonstrated record of safe operation. This could be obtained either by testing the baseline design by an independent laboratory, or by substituting a commercially available device. As a result of these efforts, the commercially available Aerosolv can puncturing device was chosen to replace the baseline design. Two concerns were raised with the system. Premature blinding of the coalescing/carbon filter, due to its proximity to the puncture and draining operation; and overpressurization of the collection bottle due to its small volume and by blinding of the …

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in power and distribution transformers important to license renewal in commercial nuclear power plants. The intent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

This report addresses the application codes of the AGS to RHIC beam line

This OTA assessment reviews the status of federal government efforts to provide safe sanitation to Alaskan Natives and the technologies that have been used or proposed for this purpose. Finally, the report examines the legislative and institutional setting for the waste sanitation problems, and the criteria that need to be applied in selecting and implementing new technologies.