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Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options
The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with …
Date:
June 1, 1993
Creator:
Brownson, D. A.; Hanson, D. J. & Blackman, H. S.
Object Type:
Report
System:
The UNT Digital Library
Weapons-grade plutonium dispositioning. Volume 3: A new reactor concept without uranium or thorium for burning weapons-grade plutonium
The National Academy of Sciences (NAS) requested that the Idaho National Engineering Laboratory (INEL) examine concepts that focus only on the destruction of 50,000 kg of weapons-grade plutonium. A concept has been developed by the INEL for a low-temperature, low-pressure, low-power density, low-coolant-flow-rate light water reactor that destroys plutonium quickly without using uranium or thorium. This concept is very safe and could be designed, constructed, and operated in a reasonable time frame. This concept does not produce electricity. Not considering other missions frees the design from the paradigms and constraints used by proponents of other dispositioning concepts. The plutonium destruction design goal is most easily achievable with a large, moderate power reactor that operates at a significantly lower thermal power density than is appropriate for reactors with multiple design goals. This volume presents the assumptions and requirements, a reactor concept overview, and a list of recommendations. The appendices contain detailed discussions on plutonium dispositioning, self-protection, fuel types, neutronics, thermal hydraulics, off-site radiation releases, and economics.
Date:
June 1, 1993
Creator:
Ryskamp, J. M.; Schnitzler, B. G. & Fletcher, C. D.
Object Type:
Report
System:
The UNT Digital Library
Weapons-grade plutonium dispositioning. Volume 4. Plutonium dispositioning in light water reactors
This study is in response to a request by the Reactor Panel Subcommittee of the National Academy of Sciences (NAS) Committee on International Security and Arms Control (CISAC) to evaluate the feasibility of using plutonium fuels (without uranium) for disposal in existing conventional or advanced light water reactor (LWR) designs and in low temperature/pressure LWR designs that might be developed for plutonium disposal. Three plutonium-based fuel forms (oxides, aluminum metallics, and carbides) are evaluated for neutronic performance, fabrication technology, and material and compatibility issues. For the carbides, only the fabrication technologies are addressed. Viable plutonium oxide fuels for conventional or advanced LWRs include plutonium-zirconium-calcium oxide (PuO{sub 2}-ZrO{sub 2}-CaO) with the addition of thorium oxide (ThO{sub 2}) or a burnable poison such as erbium oxide (Er{sub 2}O{sub 3}) or europium oxide (Eu{sub 2}O{sub 3}) to achieve acceptable neutronic performance. Thorium will breed fissile uranium that may be unacceptable from a proliferation standpoint. Fabrication of uranium and mixed uranium-plutonium oxide fuels is well established; however, fabrication of plutonium-based oxide fuels will require further development. Viable aluminum-plutonium metallic fuels for a low temperature/pressure LWR include plutonium aluminide in an aluminum matrix (PuAl{sub 4}-Al) with the addition of a burnable poison such as erbium …
Date:
June 1, 1993
Creator:
Sterbentz, J. W.; Olsen, C. S. & Sinha, U. P.
Object Type:
Report
System:
The UNT Digital Library
Wear-mechanism modelling
Goals of the program are to calculate the surface temperatures in dry sliding, develop a soft wear tester for ceramics, survey the wear mechanisms in brittle solids, and couple the temperature calculations with models to give wear maps for brittle solids. (DLC)
Date:
March 1, 1993
Creator:
Ashby, M.F. (Cambridge Univ. (United Kingdom). Dept. of Engineering)
Object Type:
Report
System:
The UNT Digital Library
Wear-mechanism modelling. Final report
Goals of the program are to calculate the surface temperatures in dry sliding, develop a soft wear tester for ceramics, survey the wear mechanisms in brittle solids, and couple the temperature calculations with models to give wear maps for brittle solids. (DLC)
Date:
March 1, 1993
Creator:
Ashby, M. F.
Object Type:
Report
System:
The UNT Digital Library
Wear prediction in a fluidized bed
A procedure to model the wear of surfaces exposed to a fluidized bed is formulated. A stochastic methodology adapting the kinetic theory of gases to granular flows is used to develop an impact wear model. This uses a single-particle wear model to account for impact wear from all possible-particle collisions. An adaptation of a single-particle abrasion model to describe the effects of many abrading particles is used to account for abrasive wear. Parameters describing granular flow within the fluidized bed, necessary for evaluation of the wear expressions, are determined by numerical solution of the fluidized bed hydrodynamic equations. Additional parameters, describing the contact between fluidized particles and the wearing surface, are determined by optimization based on wear measurements. The modeling procedure was used to analyze several bubbling and turbulent fluidized bed experiments with single-tube and tube bundle configurations. Quantitative agreement between the measured and predicted wear rates was found, with some exceptions for local wear predictions. This work demonstrates a methodology for wear predictions in fluidized beds.
Date:
June 1, 1993
Creator:
Boyle, E. J. & Rogers, W. A.
Object Type:
Report
System:
The UNT Digital Library
A weatherization manual for LIHEAP policy makers and program administrators
This manual is designed to provide Low-Income Home Energy Assistance Program (LIHEAP) directors with information about weatherization and innovative ways they can utilize LIHEAP funds for weatherization activities. It contains a description of innovative weatherization programs which demonstrate creative uses of LIHEAP funds in weatherization activities. In many of the innovative examples, state and local administrators are coordinating their LIHEAP funds with the US Department of Energy (DOE) Low-Income Weatherization Assistance Program`s funding and with a variety of other federal, state and utility company resources. The innovative programs demonstrate how LIHEAP funds can be used in client education, targeting high energy users, staff training, assessment and audits for weatherization services. The reader will find in the appendices lists of contact persons and further descriptions of the programs highlighted. Although designed with LIHEAP directors in mind, the practices and programs highlighted in this manual are of practical use to any state, local or utility weatherization program administrator. The glossary at the end of the descriptive chapters will assist readers with the terminology used throughout the manual. This manual and the many resource entities cited in its appendices provide ready access to a wealth of state-of-the-art information which could lead to a …
Date:
September 1, 1993
Creator:
Witherspoon, M. J.; Marabate, R.; Weinhaus, M. & Eisenberg, J. F.
Object Type:
Report
System:
The UNT Digital Library
Weatherization Works: An interim report of the National Weatherization Evaluation
The National Weatherization Evaluation is the first comprehensive evaluation of the Weatherization Assistance Program since 1984. The evaluation was designed to accomplish the following goals: Estimate energy savings and cost effectiveness; Assess nonenergy impacts; Describe the weatherization network; Characterize the eligible population and resources; and Identify factors influencing outcomes and opportunities for the future. As a national program, weatherization incorporates considerable diversity due to regional differences. Therefore, evaluation results are presented both in aggregate and for three climate regions: cold, moderate and hot.
Date:
November 1, 1993
Creator:
Brown, M. A.; Berry, L. G. & Kinney, L. F.
Object Type:
Report
System:
The UNT Digital Library
Wedge scattering by the method of iteration
We have investigated scattering from the classic wedge and have shown that the method of iteration of the surface current integral equation predicts currents and backscattered fields that are good approximations to the Sommerfeld solution. The method of iteration has also been applied to truncated wedges on flat surfaces with the result that the scattering from this wedge is been to be very much different from the Sommerfeld solution. These results and their implications for ocean backscatter are reported herein.
Date:
July 1, 1993
Creator:
Holliday, D.; DeRaad, L. L. Jr. & St-Cyr, G. J.
Object Type:
Report
System:
The UNT Digital Library
A weighted least-squares lump correction algorithm for transmission-corrected gamma-ray nondestructive assay
With transmission-corrected gamma-ray nondestructive assay instruments such as the Segmented Gamma Scanner (SGS) and the Tomographic Gamma Scanner (TGS) that is currently under development at Los Alamos National Laboratory, the amount of gamma-ray emitting material can be underestimated for samples in which the emitting material consists of particles or lumps of highly attenuating material. This problem is encountered in the assay of uranium and plutonium-bearing samples. To correct for this source of bias, we have developed a least-squares algorithm that uses transmission-corrected assay results for several emitted energies and a weighting function to account for statistical uncertainties in the assay results. The variation of effective lump size in the fitted model is parameterized; this allows the correction to be performed for a wide range of lump-size distributions. It may be possible to use the reduced chi-squared value obtained in the fit to identify samples in which assay assumptions have been violated. We found that the algorithm significantly reduced bias in simulated assays and improved SGS assay results for plutonium-bearing samples. Further testing will be conducted with the TGS, which is expected to be less susceptible than the SGS to systematic source of bias.
Date:
August 1, 1993
Creator:
Prettyman, T. H.; Sprinkle, J. K. Jr. & Sheppard, G. A.
Object Type:
Article
System:
The UNT Digital Library
Weld overlay coatings for erosion control
A literature review was made. In spite of similarities between abrasive wear and solid particle erosion, weld overlay hardfacing alloys that exhibit high abrasion resistance may not necessarily have good erosion resistance. The performance of weld overlay hardfacing alloys in erosive environments has not been studied in detail. It is believed that primary-solidified hard phases such as carbides and intermetallic compounds have a strong influence on erosion resistance of weld overlay hardfacing alloys. However, relationships between size, shape, and volume fraction of hard phases in a hardfacing alloys and erosion resistance were not established. Almost all hardfacing alloys can be separated into two major groups based upon chemical compositions of the primary solidified hard phases: (a) carbide hardening alloys (Co-base/carbide, WC-Co and some Fe base superalloys); and (b) intermetallic hardening alloys (Ni-base alloys, austenitic steels, iron-aluminides).
Date:
March 3, 1993
Creator:
Levin, B.; DuPont, J.N. & Marder, A.R.
Object Type:
Report
System:
The UNT Digital Library
Weld overlay coatings for erosion control. Task A: Literature review, progress report
A literature review was made. In spite of similarities between abrasive wear and solid particle erosion, weld overlay hardfacing alloys that exhibit high abrasion resistance may not necessarily have good erosion resistance. The performance of weld overlay hardfacing alloys in erosive environments has not been studied in detail. It is believed that primary-solidified hard phases such as carbides and intermetallic compounds have a strong influence on erosion resistance of weld overlay hardfacing alloys. However, relationships between size, shape, and volume fraction of hard phases in a hardfacing alloys and erosion resistance were not established. Almost all hardfacing alloys can be separated into two major groups based upon chemical compositions of the primary solidified hard phases: (a) carbide hardening alloys (Co-base/carbide, WC-Co and some Fe base superalloys); and (b) intermetallic hardening alloys (Ni-base alloys, austenitic steels, iron-aluminides).
Date:
March 3, 1993
Creator:
Levin, B.; DuPont, J. N. & Marder, A. R.
Object Type:
Report
System:
The UNT Digital Library
Welding irradiated stainless steel
Conventional welding processes produced severe underbead cracking in irradiated stainless steel containing 1 to 33 appm helium from n,a reactions. A shallow penetration overlay technique was successfully demonstrated for welding irradiated stainless steel. The technique was applied to irradiated 304 stainless steel that contained 10 appm helium. Surface cracking, present in conventional welds made on the same steel at the same and lower helium concentrations, was eliminated. Underbead cracking was minimal compared to conventional welding methods. However, cracking in the irradiated material was greater than in tritium charged and aged material at the same helium concentrations. The overlay technique provides a potential method for repair or modification of irradiated reactor materials.
Date:
December 31, 1993
Creator:
Kanne, W. R., Jr.; Chandler, G. T.; Nelson, D. Z. & Franco-Ferreira, E. A.
Object Type:
Article
System:
The UNT Digital Library
Welding of niobium to stainless
Experiences are reported of welding niobium to stainless steel for the TESLA accelerator superconducting cavities.
Date:
November 2, 1993
Creator:
Kuchnir, M. & Hiller, R. E.
Object Type:
Report
System:
The UNT Digital Library
Welding tritium aged stainless steel
Stainless steels exposed to tritium become unweldable by conventional methods due to He buildup within the metal matrix. With longer service lives expected for new weapon systems, and service life extensions of older systems, methods for welding/repair on tritium-exposed material will become important. Results are reported that indicate that both solid-state resistance welding and low-heat gas metal arc overlay welding are promising methods for repair or modification of tritium-aged stainless steel.
Date:
January 1, 1993
Creator:
Kanne, W. R., Jr.
Object Type:
Article
System:
The UNT Digital Library
Welding tritium aged stainless steel
Stainless steels exposed to tritium become unweldable by conventional methods due to He buildup within the metal matrix. With longer service lives expected for new weapon systems, and service life extensions of older systems, methods for welding/repair on tritium-exposed material will become important. Results are reported that indicate that both solid-state resistance welding and low-heat gas metal arc overlay welding are promising methods for repair or modification of tritium-aged stainless steel.
Date:
April 1, 1993
Creator:
Kanne, W. R., Jr.
Object Type:
Article
System:
The UNT Digital Library
Well test analysis and reservoir modeling of geopressured-geothermal systems (includes topical reports on analyses for: Pleasant Bayou Well No. 2, Gladys McCall Well No.1). Final report
Automated inversion of pressure transient data from the Pleasant Bayou and Gladys McCall geopressured test wells has allowed the resolution of several outstanding questions concerning the two reservoirs. The added accuracy of the interpretation of the various data sets from each well provides convincing evidence that the formation response of each of the reservoirs behaved in an essentially linear fashion throughout its multi-year depletion/recovery test history. The only exception was in the immediate vicinity of the sandface; the skin factor in each of the wells varies during the course of its test history (see Appendices for detailed discussions of the variations and the likely causes of the variations for each well). (a) The six bottomhole pressure transient tests of Pleasant Bayou Well No.2 over a twelve year period (1980-1992) yield estimates for the permeability-thickness product that are in excellent agreement (kh = 3.665 D-m). Inversion of the 45-day buildup portion of the 1980 RLT yields an estimate of X{sub a} = 869 m as the distance from the well to the nearest boundary. The inversion of the data from the other five tests, of much shorter duration, yield estimates in the range X{sub a} = 427-503 m. The RLT estimate …
Date:
February 1, 1993
Creator:
Riney, T. D. & Owusu, L. A.
Object Type:
Report
System:
The UNT Digital Library
Well venting and application of passive soil vapor extraction at Hanford and Savannah River
At the Hanford and Savannah River Sites, wells with open intervals in the unsaturated zone have been observed to {open_quotes}breathe{close_quotes}, i.e., to inhale ambient air from the surface and to exhale soil gas to the atmosphere. This breathing results primarily from the difference in pressure that develops between the soil pressure near the open interval of a well and the barometric pressure. Volatile organic compounds (VOC) have been identified at both Hanford (carbon tetrachloride) and Savannah River (trichloroethylene and tetrachloroethylene). Passive vapor extraction (PVE) refers to the enhancement and application of this natural breathing phenomenon as a remediation method for increased VOC removal rates from the unsaturated zone. Passive vapor extraction is proposed as a complementary technology to be used with active vapor extraction (AVE). The AVE system would be used to extract soil gas from the high VOC concentration, highly permeable zones. The enhanced PVE would be used to address those zones of lower VOC concentration and those zones where extraction is limited by mass transfer and diffusion. The primary advantages of PVE application are low capital costs and minimal operating costs. This combination allows for many small PVE systems to be placed on individual wells and for the …
Date:
September 1, 1993
Creator:
Rohay, V. J.; Rossabi, J.; Looney, B.; Cameron, R. & Peters, B.
Object Type:
Article
System:
The UNT Digital Library
Wellbore simulation - case studies
The use of a wellbore simulator, WELLSIM, to characterise the effects of multi-feed inflow on wellbore pressure-temperature characteristics, and diameter changes to a well on the deliverability curve, is discussed. Matching analyses are performed with the simulator on a well which has a number of two-phase and liquid infeeds, and it is demonstrated that good matches to both pressure and temperature profiles can be achieved. The significance of the reservoir/feed response curve for a steam well is illustrated, and the optimisation of wellbore diameter is shown to be related to whether the discharge is wellbore or reservoir controlled.
Date:
January 28, 1993
Creator:
Freeston, Derek & Gunn, Calum
Object Type:
Article
System:
The UNT Digital Library
West Hackberry Tertiary Project. Quarterly technical progress report, September 3, 1993--December 3, 1993
The goal of the West Hackberry Tertiary Project is to demonstrate the technical and economic feasibility combining air injection with the Double Displacement Process for tertiary oil recovery. The Double Displacement Process is the gas displacement of a water invaded oil column for the purpose of recovering oil through gravity drainage. The novel aspect of this project is the use of air as the injection fluid. The target reservoirs for the project are the Camerina C- 1,2,3 Sands located on the west flank of West Hackberry Field in Cameron Parish, Louisiana. If successful, this project win demonstrate that the use of air injection in the Double Displacement Process can economically recover oil in reservoirs where tertiary oil recovery is presently uneconomical.
Date:
November 30, 1993
Creator:
Fassihi, M. R. & Gillham, T. H.
Object Type:
Report
System:
The UNT Digital Library
West of Greens Bayou Quadrangle
Topographic map of a portion of Texas from the United States Geological Survey (USGS) project. The map includes towns, historic or notable sites, bodies of water, and other geologic features. Scale 1:24000
Date:
1993
Creator:
Geological Survey (U.S.)
Object Type:
Map
System:
The Portal to Texas History
West of Johnson Bayou Quadrangle
Topographic map of a portion of Texas from the United States Geological Survey (USGS) project. The map includes towns, historic or notable sites, bodies of water, and other geologic features. Scale 1:24000
Date:
1993
Creator:
Geological Survey (U.S.)
Object Type:
Map
System:
The Portal to Texas History
West Valley transfer cart control system design description
Detail design of the control system for the West Valley Nuclear Services Vitrification Facility transfer cart has been completed by Oak Ridge National Laboratory. This report documents the requirements and describes the detail design of that equipment and control software. Copies of significant design documents including analysis and testing reports and design drawings are included in the Appendixes.
Date:
January 1, 1993
Creator:
Bradley, E. C.; Crutcher, R. I.; Halliwell, J. W.; Hileman, M. S.; Moore, M. R.; Nodine, R. N. et al.
Object Type:
Report
System:
The UNT Digital Library
West Valley transfer cart control system design description. Environmental Restoration and Waste Management Program
Detail design of the control system for the West Valley Nuclear Services Vitrification Facility transfer cart has been completed by Oak Ridge National Laboratory. This report documents the requirements and describes the detail design of that equipment and control software. Copies of significant design documents including analysis and testing reports and design drawings are included in the Appendixes.
Date:
January 1, 1993
Creator:
Bradley, E. C.; Crutcher, R. I.; Halliwell, J. W.; Hileman, M. S.; Moore, M. R.; Nodine, R. N. et al.
Object Type:
Report
System:
The UNT Digital Library