This report describes the existing and proposed methodologies for performing measurements of contamination prior to releasing material for uncontrolled use at the Hanford Site. The technical basis for the proposed methodology, a modification to the existing contamination survey protocol, is also described. The modified methodology, which includes a large-area swipe followed by a statistical survey, can be used to survey material that is unlikely to be contaminated for release to controlled and uncontrolled areas. The material evaluation procedure that is used to determine the likelihood of contamination is also described.

Very dilute (10{sub 12} cm{sup {minus}3}) indium donors in CdTe and ZnSe powders and in CdTe single crystals were investigated using {sup 111}In Perturbed angular correlation spectroscopy. Most indium atoms are in uncomplexed sites but can form weakly-bound complexes with native defects in very defective material. The only complex observed in CdTe is an indium-Cd vacancy pair. The CdTe in which these pairs occur is apparently n-type, most Cd vacancies are free and doubly-charged, and the binding energy with indium is 0.15 eV. In ZnSe, indium can pair with a Zn vacancy or with some other presently unidentified defect. These complexes form in ZnSe containing large concentrations of both free Zn vacancies and complexes of Zn vacancies with other defects. In CdTe, the pair formation equilibration time constant is two days at 15C,an implication that Cd vacancies are mobile at room temperature. Lattice relaxation around a Cd vacancy in CdTe was probed by single crystal PAC experiments.

Tritium (Tr), when released as tritiated water at a point in a uniform and relatively dry soil, redistributes in both the liquid and vapor phases. The flux density of Tr in the liquid will exceed that in the vapor phase provided the water content is greater than approximately 15% of the total soil porosity. Thus Tr redistribution must be modeled recognizing transfer ``in parallel`` in both phases. The authors use the diffusion equation cast in spherical coordinates to analyze this problem in order to provide a basis for design of field experiments, and to offer observations on the long term behavior of such systems. The solution of the diffusion equation permits calculation of the evolution of profiles of Tr concentration, within and external to the sphere of released solution, assuming the initial concentration within this sphere to be uniform. The authors also predict the rate of advance of the maximum of Tr as it advances, and attenuates, in the soil. Calculations for the case of 1 million Curies of Tr diluted in 1 liter of water and released at a depth of 20 meters, and 200 meters above the water table, are demonstrated. If the soil has an initial water …

Observations of colloidal movement under natural conditions using the colloidal borescope were conducted at several sites in the vicinity of the Massachusetts Military Reservation (MM) located on Cape Cod. The purpose of the study was to assess the reliability of the colloidal borescope and provide additional hydrogeologic data for site-characterization work. Because of the variability observed in groundwater flow at other sites, a well-characterized site was needed to test the borescope. Results of this work indicate that existing hydrologic information specific to the various sites tested at the MM compares favorably with the borehole velocity data collected with the colloidal borescope. Direction measurements at the MM, however, appear to be less reliable than at other sites tested. Most significant among factors potentially affecting direction measurements is the relatively flat hydraulic gradient at the MM, which is an order of magnitude less than at other sites. This is due to the gentle topography and the relatively high permeability of the aquifer. Under these conditions, the geometric alignment of preferential flow paths could dominate flow direction. If the gradient is increased, flow will tend to parallel the hydraulic gradient. This report describes the field site and the colloidal borescope and discusses the …

Observations of colloidal movement under natural conditions using the colloidal borescope were conducted at several sites in the vicinity of the Massachusetts Military Reservation (MM) located on Cape Cod. The purpose of the study was to assess the reliability of the colloidal borescope and provide additional hydrogeologic data for site-characterization work. Because of the variability observed in groundwater flow at other sites, a well-characterized site was needed to test the borescope. Results of this work indicate that existing hydrologic information specific to the various sites tested at the MM compares favorably with the borehole velocity data collected with the colloidal borescope. Direction measurements at the MM, however, appear to be less reliable than at other sites tested. Most significant among factors potentially affecting direction measurements is the relatively flat hydraulic gradient at the MM, which is an order of magnitude less than at other sites. This is due to the gentle topography and the relatively high permeability of the aquifer. Under these conditions, the geometric alignment of preferential flow paths could dominate flow direction. If the gradient is increased, flow will tend to parallel the hydraulic gradient. This report describes the field site and the colloidal borescope and discusses the …

Various theoretical calculations of radionuclides in the reactions {sup 94}Mo(n,p){sup 94}Nb, {sup 109}Ag(n,2n){sup 108m}Ag, {sup 151}Eu(n,2n){sup 150m}Eu, {sup 153}Eu(n,2n){sup 152g+m2}Eu, {sup 159}Tb(n,2n){sup 158}Tb, {sup 187}Re(n,2n){sup 186m}Re, {sup 179}Hf(n,2n){sup l78m2}Hf, {sup 193}Ir(n,2n){sup 192m2}Ir are compared. We normalize the theoretical results to the evaluated experimental data at 14.5 MeV, and take their average. This yields averaged theoretical excitation functions for the production of the various radionuclides at neutron energies ranging from threshold to 14.5 MeV. We discuss differences between the various theoretical results, and between theory and data where they exist. Our theoretical results may be used in conjunction with experimental data to produce evaluated radionuclide production cross sections for neutron energies lower than 14.5 MeV.

Observations of high intensity effects on the proton performance of the AGS Booster are presented, including present operational limits and correction methods. The transverse emittances, optimum tune working points, damping of coherent transverse oscillations and correction of stopband resonances through third-order are discussed in addition to the observed tune spread due to space charge forces. The initial longitudinal phase space distribution, capture and acceleration parameters and measurements are also given. Operational tools and strategies relevant to the high intensity setup are mentioned.

Observations of high intensity effects on the proton performance of the AGS Booster are presented, including present operational limits and correction methods. The transverse emittances, optimum tune working points, damping of coherent transverse oscillations and correction of stopband resonances through third-order are discussed in addition to the observed tune spread due to space charge forces. The initial longitudinal phase space distribution, capture and acceleration parameters and measurements are also given. Operational tools and strategies relevant to the high intensity setup are mentioned.

At the design intensity of 1.5 {times} 10{sup 13} ppp, the space charge tune shift in the AGS Booster at injection has been estimated to be about 0.35. Therefore, the beam is spread over may lower order resonance lines and the stopbands have to be corrected to minimize the amplitude growth by proper compensation of the driving harmonics resulting from random errors. The observation and correction of second and third order resonance stopbands in the AGS Booster, and the establishment of a favorable operating point at high intensity are discussed.

The origin of elevated water levels in emplacement boreholes at Pahute Mesa, Nevada Test Site, is uncertain. If the water is from naturally perched aquifers, then presumed ``above water table`` weapons tests may directly impact the groundwater quality. The purpose of this study is to determine the probable source of the elevated water in boreholes by comparing modeled seepage of infiltrated drilling fluids, and the seepage from a simulated naturally perched aquifer with the observed water level history. In the model, large volumes of water are infiltrated, yet return flow of fluids back into the hole stops within three days after the end of drilling and is insufficient to produce observed standing water. Return flow is limited for two reasons: (1) the volume of the saturated rock next to the borehole is small; (2) pressure head gradient direct unsaturated flow away from the borehole. Simulation of seepage from a naturally perched aquifer readily reproduces the observed water levels.

The US Department of Energy has required radiological sabotage vulnerability assessments to be conducted for years. However, the exact methodology to be used in this type of analysis still remains somewhat elusive. Therefore, there is tremendous variation in the methodologies and assumptions used to determine release levels and doses potentially affecting the health and safety of the public. In some cases, there are three orders of magnitude difference in results for dispersal of similar materials under similar meteorological conditions. To address this issue, the authors have developed an approach to standardizing radiological sabotage target analysis that starts by addressing basic assumptions and then directs the user to some recommended computerized analytical tools. Results from different dispersal codes are also compared in this analysis.

Today`s skills will be obsolete in the year 2000. That workforce will require a much higher degree of technical sophistication and adaptability. Enormous demands will be made of DOE contractor training departments even as federal deficit reduction actions increasingly restrict resources and as the emergence of electronic performance support systems appear to diminish the need for training. True training will still be required but they must, and can, train better, faster, and cheaper. These goals are attainable by implementing the implications of performance-based training and by focusing on learning instead of on teaching. (Indeed, ability to learn efficiently and rapidly will be the premier talent in the next century.) Training Departments must dedicate themselves to changing performance, not to teaching classes. The best training department of the future will have no {open_quotes}instructors{close_quotes}. Trainingforce 2000 will look and function much differently.

The CORCON-Mod3 computer code was developed to mechanistically model the important core-concrete interaction phenomena, including those phenomena relevant to the assessment of containment failure and radionuclide release. The code can be applied to a wide range of severe accident scenarios and reactor plants. The code represents the current state of the art for simulating core debris interactions with concrete. This document comprises the user`s manual and gives a brief description of the models and the assumptions and limitations in the code. Also discussed are the input parameters and the code output. Two sample problems are also given.

MIMD massively parallel computers promise unique power and flexibility for engineering and scientific simulations. In this paper we review the development of a number of software methods and algorithms for scientific and engineering problems which are helping to realize that promise. We discuss new domain decomposition, load balancing, data layout and communications methods applicable to simulations in a broad range of technical field including signal processing, multi-dimensional structural and fluid mechanics, materials science, and chemical and biological systems.

Comprehensive neutronic evaluated data files for the naturally-occurring isotopes of cadmium are deduced from experimental data and nuclear models, and presented in the ENDF/B-VI formats. Particular attention is given to those processes relevant to fuel-cycle and fission-product applications. Comparisons are made with prior evaluations of the cadmium isotopes, and discrepancies and consistencies cited. Some of the discrepancies are very large 9.9 as much as 100%), and the differences have the potential for a pronounced impact on applications usage. The present files are comprehensive, including may important processes that are not represented in the contemporary ENDF/B-VI system. Recommendations are made for future measurements where appropriate.

A Los Alamos perspective on metallurgical research on neptunium, plutonium, americium, curium, and californium is presented. Alloying behaviors of these metals are discussed. Metal fabrication technologies, principally for plutonium, are emphasized.

The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated.

This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose reduction activities, with a focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and aocelerators. Information on improved shielding design, decontamination, containments, robotics, source prevention and control, job planning, improved operational and design techniques, as well as on other topics, has been included. In addition, DOE/EH reports not included in previous volumes of the bibliography are in this volume (abstracts 611 to 684). This volume (Volume 5 of the series) contains 217 abstracts. An author index and a subject index are provided to facilitate use. Both indices contain the abstract numbers from previous volumes, as well as the current volume. …

A-prototype explosives detection system that was developed for experimental evaluation of a nuclear resonance absorption techniques is described. The major subsystems are a proton accelerator and beam transport, high-temperature proton target, an airline-luggage tomographic inspection station, and an image-processing/detection- alarm subsystem. The detection system performance, based on a limited experimental test, is reported.

This study concerned an investigation of ecosystem dynamics in several small study sites in the North Slope region of Alaska. The scope of the proposed research is to quantitatively determine spatial interrelationships between landform geometry within these study areas and such ecologically important factors as vegetation type, depth-to-permafrost, hydraulic conductivity and incoming solar radiation. Extrapolation techniques developed and terrain-related data generated as a result of this research will augment R4D Phase II goals which relate to running the General Arctic Simulac (GAS) model (and associated ecosystem models) at different locations on the North Slope. In particular, Penn State has contributed significantly to extrapolation efforts by developing techniques which can be used to initialize conditions for model input either through direct measurement (e.g., slope and aspect) and GIS-based simulation models (e.g., drainage basin characterization). As stated in the R4D Phase II Research Plan, the long-term objectives of this program are: (1) to determine effects and to develop models based on ecosystem disturbances commonly created by energy development so that appropriate, cost-effective measures can be utilized to minimize deleterious disturbances; and (2) to extend the results to other arctic and alpine areas which are important because of likely impact from energy development. …

The Booster requires highly variable magnet cycles. When B is large, eddy current induced sextupole, etc., in the dipole vacuum chamber (VC) is large, with a much smaller contribution from magnet ends. Simple passive coils excited automatically by transformer action cancel the B induced sextupole. A self correction coil is not required for the quadrupoles, since g induced aberrations are very small (< 1.0 {times} 10{sup {minus}4} at full aperture). Iron magnetization does not produce dipole or quadrupole magnet multipole aberrations, so these magnets have been effectively made independent of unwanted multipoles for all cycles. However, variations in the transfer functions and thus the Booster tune have not been automatically eliminated. Iron magnetization contributions are almost matched, but the B induced field retardation in the dipoles VC is larger than in the quadrupoles. Results of measurements will be presented, plus a simple system to overcome the mismatch and make the tune independent of B. Properties of special lattice magnets and their corrections will also be described.

It has been recognized for many year`s that the most significant limitation of ICF is the Rayleigh-Taylor (R-T) instability. It limits the distance an ablatively driven shell can be moved to several times its initial thickness. Fortunately material flow through the unstable region at velocity v{sub A} reduces the growth rate to {radical}{sub 1+kL}/{sup kg} {minus}{beta}kv{sub A} with {beta} from 2-3. In recent years experiments using both x-ray drive and smoothed laser drive to accelerate foils have confirmed our understanding of the ablative R-T instability in planar geometry. The growth of small initial modulations on the foils is measured for growth factors up to 60 for direct drive and 80 for indirect drive. For x-ray drive large stabilization is evident. After some growth, the instability enters the non-linear phase when mode coupling and saturation are also seen and compare well with modeling. Normalized growth rates for direct drive are measured to be higher, but strategies for reduction by raising the isentrope are being investigated. For direct drive, high spatial frequencies are imprinted from the laser beam and amplified by the R-T instability. Modeling shows an understanding of this ``laser imprinting.``

Oxygen sparge is a process for treating salt residues at Los Alamos National Laboratory by sparging oxygen through molten salts. Oxygen reacts with the plutonium trichloride in these salts to form plutonium dioxide. There is further reaction of the plutonium dioxide with plutonium metal and the molten salt to form plutonium oxychloride. Both of the oxide plutonium species are insoluble in the salt and collect atthe bottom of the crucible. This results in a decrease of a factor of 2--3 in the amount of salt that must be treated, and the amount of waste generated by aqueous treatment methods.

Oxygen sparge is a process for treating salt residues at Los Alamos National Laboratory by sparging oxygen through molten salts. Oxygen reacts with the plutonium trichloride in these salts to form plutonium dioxide. There is further reaction of the plutonium dioxide with plutonium metal and the molten salt to form plutonium oxychloride. Both of the oxide plutonium species are insoluble in the salt and collect atthe bottom of the crucible. This results in a decrease of a factor of 2--3 in the amount of salt that must be treated, and the amount of waste generated by aqueous treatment methods.