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High-Rate Biological Treatment of Wastewater at the Pantex Facility - Alternative to the Existing Aerate Lagoon-Pond System (ANRCP-1999-25)
J. F. Malina, Jr., September 1999 (195K)

The purpose of this research is to develop design criteria and operating parameters for high-rate biological treatment of the wastewater generated at the Pantex Plant, to alleviate the operation problems experienced by the existing facility and eliminate the need to provide flood protection.

Treatment of Lead-Contaminated Soil at the Pantex Site (ANRCP-1999-22)
D. F. Lawler, H. M. Liljestrand, D. Kobe, July 1999 (98K)

Lead is present in the soil at the Pantex site in the vicinity of several firing ranges. Oxidation of elemental lead may result in groundwater contamination. A proposed treatment plan includes removing bullet fragments and chemically treating the remaining soil.

Biodegradation of High Explosives on Granular Activated Carbon: Enhanced Desorption of High Explosives from GAC - Batch Studies (ANRCP-1999-11)
M. C. Morley, G. E. Speitel, Jr., March 1999 (135K)

Adsorption to GAC is an effective method for removing high explosives (HE) compounds from water, but no permanent treatment is achieved. Bioregeneration, which treats adsorbed contaminants by desorption and biodegradation, is being developed as a method for reducing GAC usage rates and permanently degrading RDX and HMX.

Bioremediation of RDX in the Vadose Zone Beneath the Pantex Plant (ANRCP-1999-1)
T. L. Shull, G. E. Speitel, Jr., D. C. McKinney, January 1999 (853K)

The presence of dissolved high explosives (HE), in particular RDX and HMX, is well documented in the perched aquifer beneath the Pantex Plant. This project examined the fate and transport of HE in the vadose zone through mathematical modeling and laboratory experimentation.

Kinetics of Chromium (VI) Reduction by Ferrous Iron (ANRCP-1998-13)
B. Batchelor, M. Schlautman, I. Hwang, R. Wang, September 1998 (157K)

In situ reduction of a mobile form of chromium, Cr(VI) to an immobile form, Cr(III), was examined as a viable option to reduce the amount of chromium that reaches the groundwater table.

Performance Evaluation of Granular Activated Carbon System at Pantex: Rapid Small-Scale Column Tests to Simulate Removal of High Explosives from Contaminated Groundwater (ANRCP-1998-10)
J. L. Henke, G. E. Speitel, Jr., August 1998 (542K)

This study estimates the effectiveness and service life of the granular activated carbon system now in use at Pantex to treat groundwater contaminated with high explosives.

Investigation of Groundwater Recirculation for the Removal of RDX from the Pantex Plant Perched Aquifer (ANRCP-1998-7)
K. M. Boles, R. J. Charbeneau, S. Black, K. Rainwater, D. L. Barnes, July 1998 (2121K)

A pilot dual-phase extraction treatment system has been installed at one location at the Pantex plant to test the effectiveness of such a system on the removal of high explosive (HE) compounds from the perched aquifer below the plant.

Literature Review: Phytoaccumulation of Chromium, Uranium, and Plutonium in Plant Systems (ANRCP-1998-3)
L. R. Hossner, R. H. Loeppert, R. J. Newton, P. J. Szaniszlo, Moses Attrep, Jr., May 1998 (197K)

Phytoremediation is an integrated multidisciplinary approach to the cleanup of contaminated soils, which combines the disciplines of plant physiology, soil chemistry, and soil microbiology. The emphasis of this review has been placed on chromium (Cr), plutonium (Pu), and uranium (U).

Treatment of HMX and RDX Contamination (ANRCP-1998-2)
Robert E. Card, Jr., Robin L. Autenrieth, March 1998 (269K)

HMX and RDX are often found in the soil, groundwater, and surface waters at facilities where they are manufactured as the result of negligent disposal methods. This report describes and evaluates technologies for treating soils and waters contaminated by HMX and RDX.

A Finite Difference Model for Soil Vapor Extraction: Mathematical Development
A. Armstrong, K. A. Rainwater, C. V. G. Vallabhan, January 1997 (974K)

Soil vapor extraction (SVE) is an in-situ remediation technique whereby soil gas within the unsaturated contaminated soil matrix is extracted using an applied vacuum at one or more extraction wells.

Pulsed Neutron Generator Facility for Slowing Down Time Spectrometry (ANRCP-1999-29)
H. R. Radulescu, N. M. Abdurrahman, A. I. Hawari, B. W. Wehring, October 1999 (390K)

A 14 MeV neutron generator facility has been setup at the Nuclear Engineering Teaching Laboratory of the University of Texas at Austin. The current objective of this facility is to drive a graphite slowing-down-time spectrometer (GSDTS), which is used for studies in the non-destructive assay (NDA) of fissile nuclear materials.

Rugged Miniaturized Mass Sensors for Use in Plutonium Conversion Processes (ANRCP-1999-20)
E. A. Schweikert, W. D. James, May 1999 (121K)

This report covers the first year efforts of an anticipated three-year project devoted to the development of mass analyzers suitable for process and field applications.

Design, Construction, Establishment of Proof of Principle, and Testing of a Spectrometer to Permit Spectroelectrochemical Investigations of Actinides in a Confined System (ANRCP-1999-5)
P. K. Dasgupta, J. Li, February 1999 (333K)

This study examines the design, construction, and performance of a spectrometer that was designed and built for UV-visible absorption spectroscopic studies in molten salt media.

Basic Architecture and Design of Storage Simulation Construction Set (ANRCP-1999-4)
A. Sehgal, R. Volz, February 1999 (197K)

In a critical system such as a fissile material storage system, various issues such as safety, security, and automation of handling processes can be assessed through virtual environments. The concepts in this study can be applied for rapid virtual prototyping of other systems, as this type of system is not limited to the storage of nuclear materials.

Non-Destructive Control of the Plutonium Content of Spent Fuel Under Uncertainties on Irradiation History (ANRCP-1998-15)
V. Savander, V. Glebov, October 1998 (84K)

This research examined the problem of how to detect the possible substitution of a low-enriched uranium bundle for a bundle containing weapons-grade plutonium.

Automated System for Chemical Analysis of Airborne Particles Based on Corona-Free Electrostatic Collection (ANRCP-1997-2)
S. Liu, P. K. Dasgupta, October 1997
©American Chemical Society. First appeared in Analytical Chemistry, 1996, 68, pp. 3638-3644. Reprinted with permission.

This work describes an automated annular tubular aerosol collection system in an electrical field. The device permits the establishment of field strengths without causing discharges, thus allowing charged aerosol particles to be collected on electrode surfaces.

Modeling of Beryllium Corrosion (ANRCP-1999-30)
J. Sanchez, S. Landsberger, L. Zhao, October 1999 (142K)

This research examined whether experiments concerning beryllium corrosion can be conducted at room temperature with no adverse affects.

Heat Transfer Analysis of Calorimeter Design (ANRCP-1999-26)
N. Hossain, S. Aboagye, K. S. Ball, September 1999 (1612K)

FLUENT and FIDAP, two Computational Fluid Dynamics (CFD) codes, were used to investigate the possibility of using these codes in similar heat transfer studies.

Surface Analysis of Heat-Resistant Metals Exposed to Gallium Sub-Oxide (Ga₂0) (ANRCP-1999-24)
F. Landry, N. Byman, E. M. Taleff, August 1999 (441K)

Samples of three typical heat-resistant metallic alloys have been exposed at elevated temperatures to an environment containing solid gallium oxide and vapor-phase gallium sub-oxide. The three heat-resistant materials include Stellite-6, Inconel-625, and commercial tungsten.

The Effects of Alpha Particle Irradiation on Stainless Steel (ANRCP-1999-21)
J. D. Shipp, R. R. Hart, M. Saglam, K. Unlu, B. W. Wehring, June 1999 (266K)

Energetic alpha particles emitted from the decay of plutonium isotopes continually introduce helium into the metal cladding that surrounds the stored plutonium pits. The continuous introduction of helium into a metal leads to the degradation of its mechanical properties.

Characterization of Celotex and Thermodynamic Calculations of the Formation of Corrosion Precursors on Beryllium (ANRCP-1999-16)
A. Diaz-Ortiz, J. Stolk, J. Kim, J.M. Sanchez, A. Manthiram, April 1999 (161K)

A complete compositional and thermal characterization of celotex was carried out using energy dispersive spectroscopy, inductively coupled plasma-mass spectroscopic analysis, ion chromatography, and thermogravimetric analysis.

Chemical Synthesis of Magnetic Fe-B and Fe-Co-B Particles and Chains (ANRCP-1999-15)
P. Fulmer, J. Kim, A. Manthiram, J. M. Sanchez, April 1999 (1385K)

The chemical synthesis of Fe-B and Fe-Co-B alloys by reducing iron and cobalt chloride solutions with potassium borohydride has been investigated systematically with an objective to develop magnetic materials with high saturation magnetization for the Magnetically Assisted Chemical Separation (MACS) process.

Shock Compression Synthesis of Hard Materials (ANRCP-1999-13)
C. G. Willson, March 1999 (708K)

The purpose of this research was to adapt the high explosives technology that was developed in conjunction with nuclear weapons programs to subjecting materials to ultra-high pressures and to explore the utility of this technique for the synthesis of hard materials.

Mechanisms of Formation of Trace Decomposition Products in Complex High Explosive Mixtures (ANRCP-1999-8)
J. D. Woodyard, C. E. Burgess, March 1999 (303K)

The principal goal of this project is to identify the mechanisms of decomposition of high explosives (HE), plasticizers, plastic polymer binders, and radical stabilizers resulting from exposures to ionizing radiation, heat, and humidity.

Gallium Interactions with Zircaloy (ANRCP-1999-2)
M. K. West, January 1999 (1311K)

High fluence ion implantation of Ga ions was conducted on heated Zircaloy-4 in the range of 10¹⁶-10¹⁸ Ga ions/cm². Surface effects were studied using SEM and electron microprobe analysis.

Literature Review of the Lifetime of DOE Materials: Aging of Plastic Bonded Explosives and the Explosives and Polymers Contained Therein (ANRCP-1998-12)
C. E. Burgess, J. D. Woodyard, K. A. Rainwater, J. M. Lightfoot, B. R. Richardson, September 1998 (379K)

The principal goal of this project is to identify the decomposition mechanisms of high explosives, plasticizers, and plastic polymer binders resulting from exposure to ionizing radiation, heat, and humidity.

Gallium Interactions with Zircaloy Cladding (ANRCP-1998-5)
R. R. Hart, J. Rennie, K. Aucoin, M. West, May 1998 (511K)

The effects of Ga from weapons-grade plutonium MOX fuel on zircaloy-IV cladding during power reactor operation have been simulated by implantations of 100 keV Ga-69 ions into a polished zircaloy-IV sample while the sample was maintained at a typical cladding temperature of 375^oC.

Sourcebook for Nuclear Technology Higher Education in the New Independent States (ANRCP-1999-31)
Amarillo National Research Center, December 1999 (348K)

A listing of the nuclear technology programs in higher education, and the associated faculty and other key people, within the countries that once comprised the former Soviet Union.

A Feasibility Study for the Storage of Plutonium Pits in Non-Partitioned Warehouse Facilities (ANRCP-1999-7)
D. James, S. Parameswaren, S. Nagendran, February 1999 (410K)

It is projected that up to 20,000 plutonium pits will be stored at Pantex for up to 50 years. The objective of this research is to develop and validate a numerical model to predict the temperature distribution within the plutonium storage container as a function of the ambient air temperature within the warehouse.

Development of Characterization of Plutonium Storage Containers (ANRCP-1999-6)
D. James, S. Stevkovski, February 1999 (634K)

At least 11,000 plutonium pits are projected to be stored at Pantex for up to fifty years. The current pit container, the ALR8, was not designed for this length of storage duration. The objective of this research is to to consider and analyze the safety features of the proposed ALR8(SI) container with regard to thermal performance.

Application of a New Time Scale Based Low K-e Model to Natural Convection from a Semi-Infinite Vertical Isothermal Plate (ANRCP-1999-3)
S. Senthooran, S. Parameswaran, January 1999 (116K)

The low k-e model proposed by Yang and Shih (1992) is applied to the calculation of the turbulent natural convective boundary layer over a semi-infinite, vertical, isothermal surface.

Use of Sulfur Hexafluoride and Perfluorocarbon Tracers in Plutonium Storage Containers for Leak Detection (ANRCP-1998-4)
J. K. Kung, May 1998 (623K)

A protocol has been developed based on the use of inert tracers with varying concentrations in order to "fingerprint" or "tag" long-term interim plutonium storage containers.

Technical Summary: Feasibility Study of Conductivity Monitoring for Leak Detection in Double-Walled Plutonium Containers (ANRCP-1997-4)
J.-X. Lu, W. H. Marlow, November 1997 (336K)

Report of initial feasibility study for an innovative approach to monitoring leakages of radioactive materials from the pit and tracking the intrusion of outside air into the drum by monitoring the electrical conductivity of the fill-gas.

Cross Section Libraries for Studies of Plutonium Disposition in Light Water Reactors (UTXS) (ANRCP-1999-28)
M. S. Abdelrahman and N. M. Abdurrahman, October 1999 (540K)

The need for cross section libraries for various materials at different temperatures arose during the benchmark activities related to mixed oxide fuel (MOX) utilization in existing light water reactors. The University of Texas Cross Section Library (UTXS), was developed to address this need.

A Methodology for the Analysis and Selection of Alternatives for the Disposition of Surplus Plutonium (ANRCP-1999-23)
J. Dyer, August 1999 (208K)

The DOE Office of Fissile Materials Disposition has announced a Record of Decision selecting alternatives for disposition of surplus plutonium. A team of analysts from the Amarillo National Research Center provided an independent evaluation of the alternatives for plutonium that were considered during the evaluation effort. This report outlines the methodology used by the ANRC team.

Modeling of the Performance of Weapons MOX Fuel in Light Water Reactors (ANRCP-1999-19)
J. Alvis, P. Bellanger, P. G. Medvedev, K. L. Peddicord, G. I. Gellene, May 1999 (863K)

The objective of this project is to perform the analysis of the thermal, mechanical, and chemical behavior of mixed uranium-plutonium oxide (MOX) fuel pins in light water reactors (LWRs) using performance models which describe the behavior of MOX fuel during irradiation under typical power reactor conditions.

Remote Inspection System for Hazardous Sites (ANRCP-1999-18)
J. Redd, C. Borst, R. A. Volz, L. J. Everett, April 1999 (453K)

This paper describes research to provide a remote inspection capability for nuclear material storage facilities, which could eliminate the need for humans to enter the facilities and risk exposure to radioactive materials.

User Manual for Storage Simulation Construction Set (ANRCP-1999-17)
A. Sehgal, R. A. Volz, April 1999 (206K)

The Storage Simulation Set (SSCS) is a tool for composing storage system models using Telegrip. With this system, the models of a storage system can be composed rapidly and accurately.

MOX Use in Reactors: Benchmarking of Neutronic Codes Analyses of Selected Saxton Plutonium Program Experiments Using WIMS7a (ANRCP-1999-12)
G. F. Cuevas Vivas, T. A. Parish, March 1999 (222K)

The deterministic code WIMS7a was employed to calculationally model a selected group of the SAXTON experiments. The selection of the experimental configurations to be modeled was performed so as to fully exploit the neutronic variety of the SAXTON plutonium program experiments.

Generalized Recognition of Single-Ended Contact Formations for Use in Automated Assembly Operations (ANRCP-1999-10)
R. Ravuri, March 1999 (244K)

The need for robots which can adapt their teaching and programming to new situations is strongly felt, especially in tasks such as assembly operations, which involve the robot making frequent contacts with its environment. This research addresses the problems that arise due to small changes in the work settings after the system has been programmed or trained.

Studies of Flexible MOX/LEU Fuel Cycles (ANRCP-1999-9)
G. Alonso-Vargas, M. L. Adams, March 1999 (220K)

The United States is planning to use some of its excess weapons plutonium to make mixed-oxide (MOX) fuel for existing light-water reactors. Designs for the transition from uranium cores to MOX cores assume that any time a reactor needs MOX assemblies, these assemblies will be supplied. In reality there are many possible scenarios under which this supply could be disrupted.

Experimental Study of Highly Viscous Impinging Jets (ANRCP-1998-22)
M. Gomon, December 1998 (1054K)

The objective of this research is to study the behavior of highly viscous gravity-driven jets filling a container.

A Stability Tool for Use Within TELEGRIP (ANRCP-1998-19)
W. H. Son, J. C. Trinkle, December 1998 (144K)

This paper describes StabTool (developed within a commercial software package, TELEGRIP), a graphical tool which allows functions that can determine the various types of stabilities of an arbitrarily shaped object held by a fixture, robotic gripper, or of a set of objects piled randomly together.

A Computational Study of Highly Viscous Impinging Jets (ANRCP-1998-18)
M. W. Silva, December 1998 (1575K)

Two commercially-available computational fluid dynamics codes, FIDAP and FLOW-3D, were used to simulate the landing region of jets of highly viscous fluids impinging on flat surfaces. Several computational models were developed and the results were compared with experimental observations.

Process Modeling of Plutonium Conversion and MOX Fabrication for Plutonium Disposition (ANRCP-1998-17)
K. L. Schwartz, October 1998 (727K)

This study was undertaken to determine the optimal size for facilities for the ARIES process, by which plutonium metal is converted into a powdered oxide form, and MOX fuel fabrication, where the oxide powder is combined with uranium oxide powder to form ceramic fuel.

U.S. Weapons-Useable Plutonium Disposition Policy: Implementation of the MOX Fuel Option (ANRCP-1998-16)
V. L. Gonzalez, October 1998 (205K)

This study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities.

Collector for Recovering Gallium from Weapons Plutonium (ANRCP-1998-14)
C. V. Philip, R. G. Anthony, S. Chokkaram, September 1998 (331K)

The separation of gallium from weapons plutonium involves aqueous processing using solvent extraction or ion exchange, which generates liquid radioactive wastes. A Thermally Induced Gallium Removal (TIGR) process is a simpler alternative.

Criticality Analysis of Selected Saxton Plutonium Program Experiments Using WIMS-D4M and DIF3D (ANRCP-1998-9)
G. F. Cuevas Vivas, T. A. Parish, August 1998 (232K)

The criticality experiments performed under the SAXTON Plutonium Program have been simulated with the diffusion code DIF3D and homogenized region, multigroup cross sections from the WIMS-D4M lattice physics code.

Disposition of Weapons-Grade Plutonium
Center for Strategic and International Studies, March 1998 (431K)

The United States has undertaken a series of measures to monitor, protect, safeguard, cap, and ultimately reduce the global stocks of excess weapons-grade materials that are now being created.

Disposition of Weapons-Grade Plutonium in Westinghouse Reactors (ANRCP-1998-1)
A. A. Alsaed, M. Adams, March 1998 (431K)

Report of a feasibility study of using weapons-grade plutonium in the form of mixed-oxide (MOX) fuel in existing reactors, which found that four-loop Westinghouse reactors such as the Vogtle power plant are capable of handling up to 45 percent weapons-grade MOX loading without any modifications.

Investigations in Gallium Removal (ANRCP-1997-3)
C. V. Philip, W. W. Pitt, C. Beard, November 1997 (37K)

Simple experiments were performed on gallium oxide, and cerium-oxide/gallium-oxide mixtures, heated to temperatures ranging from 700 - 900 °C in a reducing environment, and a method for collecting the gallium vapors under these conditions was demonstrated.

Evaluation of Alternatives for the Disposition of Surplus Weapons-Usable Plutonium (ANRCP-1997-1)
J. S. Dyer, T. Edmunds, J. C. Butler, J. Jia, April 1997 (847K)

In 1994 and 1995, the Department of Energy Office of Fissile Materials Disposition (OFMD) conducted a screening study of a large number of technologies that could be used for the disposition of surplus plutonium [DOE-SCR 95].

A Review of Alternative Siting of Nuclear Complex Missions
The Perryman Group, October 1996 (135K)

Any decision as to the future of the nuclear weapons complex should fully consider risks, costs, environmental factors, and the scientific research and production conditions which have been vital to past success.

A Proposed Methodology for the Analysis and Selection of Alternatives for the Disposition of Surplus Plutonium
J. S. Dyer, T. Edmunds, J. C. Butler, J. Jia, March 1996 (73K)

The nuclear states are currently involved in the development of comprehensive approaches to the long-term storage and management of fissile materials. The evaluation should include non-proliferation, economic, technical, institutional, schedule, environmental, and health and safety issues.

Recharge Monitoring in an Interplaya Setting (ANRCP-1999-14)
B. R. Scanlon, R. C. Reedy, J. Liang, March 1999 (195K)

The objective of this investigation is to monitor infiltration in response to precipitation events in an interplaya setting by evaluating data gathered from the interplaya recharge monitoring installation at the Pantex Plant from March through December 1998.

Accident Analysis for Aircraft Crash into Hazardous Facilities: A Statistical Primer (ANRCP-1998-20)
J. C. Rock, December 1998 (474K)

The DOE Standard 3014-96, Accident Analysis for Aircraft Crash into Hazardous Facilities, provides formulae and instructions for calculating screening quantities and frequencies, which are consistent with an unstated underlying six-term expression for estimating the annual number of aircraft-impact-related releases. The statistical concepts underlying this formula are explained.

Routing of Radioactive Shipments in Networks With Time-Varying Costs and Curfews (ANRCP-1998-11)
L. A. Bowler, H. S. Mahmassani, September 1998 (486K)

This research examines routing of radioactive shipments in highway networks with time-dependent travel times and population densities.

Optimal Routing of Hazardous Substances in Time-Varying, Stochastic Transportation Networks (ANRCP-1998-8)
E. Miller-Hooks, H. S. Mahmassani, July 1998 (278K)

This report is concerned with the selection of routes in a network along which to transport hazardous substances, taking into consideration several key factors pertaining to the cost of transport and the risk of population exposure in the event of an accident.

Improving Aircraft Accident Forecasting for an Integrated Plutonium Storage Facility (ANRCP-1998-6)
J. C. Rock, J. Kiffe, M. T. McNerney, T. A. Turen, June 1998 (189K)

This document establishes a hierarchy of procedures for estimating the small annual frequency for aircraft accidents that impact Pantex facilities and the even smaller frequency of hazardous material released to the environment.

Characterization of the Risks Associated with Producing Mixed-Oxide Fuel at Pantex
I. S. Hamilton, R. J. Charbeneau, D. L. Barnes, July 1998

The Amarillo National Research Center initiated a study to determine the impact that plutonium conversion and mixed-oxide fuel fabrication could have on the environment and public health in the Panhandle region of Texas.

Recommendations for Government/Industry Cooperation to Disable Weapons Plutonium in Nuclear Power Plants
September 1996

Comments Submitted in Conjunction with the Draft Outline for the Nonproliferation Policy Review as it Relates to Weapons Materials Disposition and Arms Control Assessment
August 1996

Comments on the Predecisional Draft of the Joint U.S.-Russian Study of Plutonium Disposition - Options Steering Committee Summary Report
July 1996

Review of the DOE Office of Fissile Materials Disposition's Plans for Interim Storage of Plutonium Inventories
May 1996

Review of the Storage and Disposition of Weapons-Useable Fissile Materials Draft Programmatic Environmental Impact Statement, and the Reactor-Based Plutonium Disposition Options
March 1996

Comments on the Overall Fissile Materials Disposition Program, and Three Elements of that Program: Immobilization Alternatives, Joint U.S./Russian Programs, and Deep Borehole Disposition
February 1996

Review of a Methodology for the Analysis and Selection of Alternatives for the Disposition of Surplus Plutonium
September 1995

Review of the Long-Range Research and Development Plan: Fissile Materials Disposition Program
July 1995

Review of the Draft Summary Report of the Screening Process to Determine Reasonable Alternatives for Storage and Disposition of Weapons-Usable Fissile Materials
March 1995

A Decision-Making Model for Materials Management of End-of-Life Products in the Pantex Plant (ANRCP-1999-27)
H.-C. Zhang, F. Ling, September 1999 (278K)

This report is concerned with a proposed system architecture for decision-making model for material management of non-nuclear dismantled components - PMM (Proactive Material Management) model.

Activities for Teaching Fundamental Concepts of Nuclear Energy and Related Topics
G. Skoog, T. Brasher, 1996 (2100K)

This resource manual was developed in response to an identified need for resource materials and teacher training in mathematics and science. To meet this need, the development group identified interesting hands-on activities that would involve students and increase their understanding of nuclear power and related issues.