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Withdrawal from the ABM Treaty: Legal Considerations
On December 13, 2001, President Bush gave formal notice to Russia, Belarus, Kazakhstan, and the Ukraine that the United States was withdrawing from the Anti-Ballistic Missile Treaty because of the constraints it imposes on the testing of missile defense systems; and six months later, on June 13, 2002, the treaty effectively terminated. The ABM Treaty has been in force since 1972. Pertinent legal questions that have been raised about U.S. withdrawal concern whether the treaty allows it; if so, the procedure to be followed; and, finally, the constitutionality of the President doing so unilaterally without the involvement of the Senate or Congress. This report briefly discusses these issues, as well as the recent federal district court decision in Kucinich v. Bush dismissing a suit by 32 members of the House challenging the constitutionality of the President’s action.
Date:
December 31, 2002
Creator:
Ackerman, David M.
Object Type:
Report
System:
The UNT Digital Library
Plutonium recovery from spent reactor fuel by uranium displacement
This report discusses a process for separating uranium values and transuranic values from fission products containing rare earth values when the values which are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is re-established.
Date:
December 31, 1991
Creator:
Ackerman, J. P.
Object Type:
Patent
System:
The UNT Digital Library
Magnesium transport extraction of transuranium elements from LWR fuel
This report discusses a process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl{sub 2} and a U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800{degrees}C to about 850{degrees}C to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein. The CaCl{sub 2} having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO{sub 2}. The Ca metal and CaCl{sub 2} is recycled to reduce additional oxide fuel. The U-Fe alloy having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with Mg metal which takes up the actinide and rare earth fission product metals. The U-Fe …
Date:
December 31, 1991
Creator:
Ackerman, J. P.; Battles, J. E.; Johnson, T. R.; Miller, W. E. & Pierce, R. D.
Object Type:
Patent
System:
The UNT Digital Library
Advanced waste forms from spent nuclear fuel
More than one hundred spent nuclear fuel types, having an aggregate mass of more than 5000 metric tons (2700 metric tons of heavy metal), are stored by the United States Department of Energy. This paper proposes a method for converting this wide variety of fuel types into two waste forms for geologic disposal. The method is based on a molten salt electrorefining technique that was developed for conditioning the sodium-bonded, metallic fuel from the Experimental Breeder Reactor-II (EBR-II) for geologic disposal. The electrorefining method produces two stable, optionally actinide-free, high-level waste forms: an alloy formed from stainless steel, zirconium, and noble metal fission products, and a ceramic waste form containing the reactive metal fission products. Electrorefining and its accompanying head-end process are briefly described, and methods for isolating fission products and fabricating waste forms are discussed.
Date:
December 31, 1995
Creator:
Ackerman, J.P. & McPheeters, C.C.
Object Type:
Report
System:
The UNT Digital Library
Atmospheric Radiation Measurement Program Science Plan
The Atmospheric Radiation Measurement (ARM) Program has matured into one of the key programs in the U.S. Climate Change Science Program. The ARM Program has achieved considerable scientific success in a broad range of activities, including site and instrument development, atmospheric radiative transfer, aerosol science, determination of cloud properties, cloud modeling, and cloud parameterization testing and development. The focus of ARM science has naturally shifted during the last few years to an increasing emphasis on modeling and parameterization studies to take advantage of the long time series of data now available. During the next 5 years, the principal focus of the ARM science program will be to: Maintain the data record at the fixed ARM sites for at least the next five years. Improve significantly our understanding of and ability to parameterize the 3-D cloud-radiation problem at scales from the local atmospheric column to the global climate model (GCM) grid square. Continue developing techniques to retrieve the properties of all clouds, with a special focus on ice clouds and mixed-phase clouds. Develop a focused research effort on the indirect aerosol problem that spans observations, physical models, and climate model parameterizations. Implement and evaluate an operational methodology to calculate broad-band heating …
Date:
October 31, 2004
Creator:
Ackerman, T
Object Type:
Report
System:
The UNT Digital Library
INEL BNCT Program: Volume 5, No. 9. Bulletin, September 1991
This Bulletin presents a summary of accomplishments and highlights of the Idaho National Engineering Laboratory`s (INEL) Boron Neutron Capture Therapy (BNCT) Program for September 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.
Date:
December 31, 1991
Creator:
Ackermann, A. L.
Object Type:
Report
System:
The UNT Digital Library
B physics: first evidence for b_s0 --> phi phi decay and measurements of branching ratio and a_cp for b+ --> phi k+
We present the first evidence of charmless decays of the B{sub s}{sup 0} meson, the decay B{sub s}{sup 0} {yields} {phi}{phi}, and a measurement of the Branching Ratio BR(B{sub s}{sup 0} {yields} {phi}{phi}) using 180 pb{sup -1} of data collected by the CDF II experiment at the Fermilab Tevatron collider. In addition, the BR and direct CP asymmetry for the B{sup +} {yields} {phi}K{sup +} decay are measured.
Date:
May 31, 2005
Creator:
Acosta, D.
Object Type:
Report
System:
The UNT Digital Library
Redefining design criteria for Pu-238 gloveboxes
Enclosures for confinement of special nuclear materials (SNM) have evolved into the design of gloveboxes. During the early stages of glovebox technology, established practices and process operation requirements defined design criteria. Proven boxes that performed and met or exceeded process requirements in one group or area, often could not be duplicated in other areas or processes, and till achieve the same success. Changes in materials, fabrication and installation methods often only met immediate design criteria. Standardization of design criteria took a big step during creation of ``Special-Nuclear Materials R and D Laboratory Project, Glovebox standards``. The standards defined design criteria for every type of process equipment in its most general form. Los Alamos National Laboratory (LANL) then and now has had great success with Pu-238 processing. However with ever changing Environment Safety and Health (ES and H) requirements and Ta-55 Facility Configuration Management, current design criteria are forced to explore alternative methods of glovebox design fabrication and installation. Pu-238 fuel processing operations in the Power Source Technologies Group have pushed the limitations of current design criteria. More than half of Pu-238 gloveboxes are being retrofitted or replaced to perform the specific fuel process operations. Pu-238 glovebox design criteria are headed …
Date:
December 31, 1998
Creator:
Acosta, S.V.
Object Type:
Article
System:
The UNT Digital Library
Construction features of the exploratory shaft at Yucca Mountain
The Exploratory Shaft (ES) at Yucca Mountain is planned to be constructed during 1985 and 1986 as part of the detailed site characterization for one of three sites which may be selected as candidates for location of a high-level radioactive waste repository. Conventional mining methods will be used for the shaft sinking phase of the ES project. The ES will be comprised of surface support facilities, a 1480-ft-deep circular shaft lined with concrete to a finished inside diameter of 12 ft, lateral excavations and test installations extending up to 200 ft from the shaft, and long lateral borings extending up to 2300 ft from the shaft. The estimated time for sinking the shaft to a total depth of about 1480 ft and completing the lateral excavations and borings is about two years. The major underground development planned for the primary test level at a depth of 1200 ft consists of the equivalent of 1150 ft of 15- by 15-ft drift. The total volume of rock to be removed from the shaft proper and the lateral excavations totals about 1/2 million cubic feet. Construction equipment for the shaft and underground excavation phases consists of conventional mine hoisting equipment, shot hole and …
Date:
December 31, 1984
Creator:
Adair, G.W. & Fiore, J.N.
Object Type:
Article
System:
The UNT Digital Library
ORGANIC RANKINE CYCLE TECHNOLOGY PROGRAM. Quarterly Progress Report No. 2, July 1-October 1, 1966.
None
Date:
October 31, 1967
Creator:
Adam, A.W.
Object Type:
Report
System:
The UNT Digital Library
INSPIRE and SPIRES Log File Analysis
SPIRES, an aging high-energy physics publication data base, is in the process of being replaced by INSPIRE. In order to ease the transition from SPIRES to INSPIRE it is important to understand user behavior and the drivers for adoption. The goal of this project was to address some questions in regards to the presumed two-thirds of the users still using SPIRES. These questions are answered through analysis of the log files from both websites. A series of scripts were developed to collect and interpret the data contained in the log files. The common search patterns and usage comparisons are made between INSPIRE and SPIRES, and a method for detecting user frustration is presented. The analysis reveals a more even split than originally thought as well as the expected trend of user transition to INSPIRE.
Date:
August 31, 2012
Creator:
Adams, Cole & /SLAC, /Wheaton Coll.
Object Type:
Report
System:
The UNT Digital Library
High efficiency shale oil recovery. Fourth quarterly report, October 1, 1992--December 31, 1992
The overall project objective is to demonstrate the high efficiency of the Adams Counter-Current shale oil recovery process. The efficiency will first be demonstrated on a small scale, in the current phase, after which the demonstration will be extended to the operation of a small pilot plant. Thus the immediate project objective is to obtain data on oil shale retorting operations in a small batch rotary kiln that will be representative of operations in the proposed continuous process pilot plant. Although an oil shale batch sample is sealed in the batch kiln from the start until the end of the run, the process conditions for the batch are the same as the conditions that an element of oil shale would encounter in a continuous process kiln. Similar chemical and physical (heating, mixing) conditions exist in both systems. The two most important data objectives in this phase of the project are to demonstrate (1) that the heat recovery projected for this project is reasonable and (2) that an oil shale kiln will run well and not plug up due to sticking and agglomeration. The following was completed and is reported on this quarter: (1) A software routine was written to eliminate …
Date:
December 31, 1992
Creator:
Adams, D. C.
Object Type:
Report
System:
The UNT Digital Library
Environmental impacts of ocean disposal of CO{sub 2}
This project has examined the impacts from the marine disposal of carbon dioxide based on the current state of knowledge.
Date:
December 31, 1995
Creator:
Adams, E.; Herzog, H.; Auerbach, D. & Caulfield, J.
Object Type:
Article
System:
The UNT Digital Library
Comparison between S/1 and R/1 tests and damage density vs. fluence (rho(phi)) results for unconditioned and sub-nanosecond laser-conditioned KD2PO4 crystals
We present S/1 and R/1 test results on unconditioned and 355 nm (3{omega}), 500 ps laser conditioned DKDP. We find up to {approx}2.5X improvement in fluence in the S/1 performance after 3{omega}, 500 ps conditioning to 5 J/cm{sup 2}. For the first time, we observe a shift to higher fluences in the R/1 results for DKDP at 3{omega}, 7 ns due to 500 ps laser conditioning. The S/1 results are compared to {rho}({phi}) results previously measured on the same DKDP crystal [1]. A consistent behavior in fluence was found between the S/1 and {rho}({phi}) results for unconditioned and 500 ps conditioned DKDP. We were successful at using Poisson statistics to derive a connection between the S/1 and {rho}({phi}) results that could be tested with our data sets by trying to predict the shape of the {rho}({phi}) curve. The value for the power dependence on fluence of {rho}({phi}) derived from the S/1 data was {approx}11 {+-} 50%. The results presented and discussed here imply a strong correlation between the damage probability (S/1) test and {rho}({phi}). We find a consistent description of the two test types in terms of a power law {rho}({phi}) and that this basic shape held for all cases, …
Date:
October 31, 2007
Creator:
Adams, J. J.; Jarboe, J.; Feit, M. & Hackel, R.
Object Type:
Article
System:
The UNT Digital Library
An analytical assessment of the chemical form of fission products during postulated severe accidents in the SRS production reactors
An analysis has been performed to determine the principal chemical forms for the structural and fission product elements during a postulated severe core damage accident in tritium powered core in the Savannah River Site (SRS) reactors. These reactors are powered with UAl{sub x} fuel and are used for the production of weapons materials. Six core elements, cesium, iodine, tellurium, strontium, barium, and lithium, were emphasized in this analysis. Other elements also included were aluminum, hydrogen, oxygen, uranium, molybdenum, silicon, zirconium, magnesium, iron, chromium, nickel, cadmium, zinc, cooper, manganese, nitrogen, and argon. The masses of each of the constituents used in the analyses were based on end-or-core life masses for the structural and fission product elements and on core gas volume for steam, N, and Ar. A chemical equilibrium analysis was performed using the Facility for Analysis of Chemical Thermodynamics (FACT) computer code at three temperatures (800, 1100, 1400 K) and two pressures (1 and 10 atmospheres). These temperatures and pressures are typical for postulated severe core accidents in the ATR.
Date:
December 31, 1991
Creator:
Adams, J. P.
Object Type:
Article
System:
The UNT Digital Library
Fission product transport and behavior during two postulated loss of flow transients in the air
This document discusses fission product behavior during two postulated loss-of-flow accidents (leading to high- and low-pressure core degradation, respectively) in the Advanced Test Reactor (ATR). These transients are designated ATR Transient LCPI5 (high-pressure) and LPP9 (low-pressure). Normally, transients of this nature would be easily mitigated using existing safety systems and procedures. In these analyses, failure of these safety systems was assumed so that core degradation and fission product release could be analyzed. A probabilistic risk assessment indicated that the probability of occurrence for these two transients is of the order of 10{sup {minus}5 }and 10{sup {minus}7} per reactor year for LCP15 and LPP9, respectively.
Date:
December 31, 1991
Creator:
Adams, J. P. & Carboneau, M. L.
Object Type:
Article
System:
The UNT Digital Library
Performance of CVR coatings for PBR fuels
As part of the component development process for the particle bed reactor (PBR), it is necessary to develop coatings for fuel particles which will be time and temperature stable. These coatings must not only protect the particle from attack by the hydrogen coolant, but must also help to maintain the bed in a coolable geometry and mitigate against fission product release. In order to develop these advanced coatings, a process to produce chemical vapor reaction (CVR) coatings on fuel for PBRs has been developed. The initial screening tests for these coatings consisted of testing in flowing hot hydrogen at one atmosphere. Surrogate fuel particles consisting of pyrolytic graphite coated graphite particles have been heated in flowing hydrogen at constant temperature. The carbon loss from these particles was measured as a function of time. Exposure temperatures ranging from 2,500 to 3,000 K were used and samples were exposed for up to 14 minutes in a cyclical fashion, cooling to room temperature between exposures. The rate of weight loss measured as a function of time is compared to that from other tests of coated materials under similar conditions. Microscopic examination of the coatings before and after exposure was also conducted and these …
Date:
December 31, 1993
Creator:
Adams, J. W.; Barletta, R. E.; Svandrlik, J. & Vanier, P. E.
Object Type:
Report
System:
The UNT Digital Library
Multi-strange baryon production in Au-Au collisions at sqrt(sNN) = 130 GeV
The transverse mass spectra and mid-rapidity yields for {Xi}s and {Omega}s plus their anti-particles are presented. The 10% most central collision yields suggest that the amount of multi-strange particles produced per produced charged hadron increases from SPS to RHIC energies. A hydrodynamically inspired model fit to the spectra, which assumes a thermalized source, seems to indicate that these multi-strange particles experience a significant transverse flow effect, but are emitted when the system is hotter and the flow is smaller than values obtained from a combined fit to {pi}, K, p and {Lambda}s.
Date:
July 31, 2003
Creator:
Adams, J.; Adler, C.; Aggarwal, M. M.; Ahammed, Z.; Amonett, J.; Anderson, B. D. et al.
Object Type:
Article
System:
The UNT Digital Library
Pion-Kaon correlations in central Au+Au collisions at {radical}(s{sub NN}) = 130 GeV
No abstract prepared.
Date:
July 31, 2003
Creator:
Adams, J.; Adler, C.; Aggarwal, M. M.; Ahammed, Z.; Amonett, J.; Anderson, B. D. et al.
Object Type:
Article
System:
The UNT Digital Library
Isostatic pressing development. Quarterly report, October--December, 1971
About 150 process-development pressings were made in prototype tooling. Problems arose which include stress cracking caused by difficult stripping of the part from the mandrel. Pressings made of PBX 9404 presented none of these problems. The primary effort is being directed toward developing a process for LX-09 and LX-04 pressings which at present are the problem areas.
Date:
December 31, 1972
Creator:
Adams, J.C. & Sheeran, R.E.
Object Type:
Report
System:
The UNT Digital Library
Provably Optimal Parallel Transport Sweeps on Regular Grids
None
Date:
January 31, 2013
Creator:
Adams, M. P.; Adams, M. L.; Hawkins, W. D.; Smith, T.; Rauchwerger, L.; Amato, N. M. et al.
Object Type:
Article
System:
The UNT Digital Library
Metallurgical Examination of Hrt Leak Detector Tubing and Flanges
None
Date:
January 31, 1957
Creator:
Adamson, G. M.; Hammond, J. P.; Kegley, T. M. & White, J. K.
Object Type:
Report
System:
The UNT Digital Library
Metallurgical Examination of HRT Leak Detector Tubing and Flanges
After several failures had occurred in the HRT leak detector system, several lengths of this tubing were removed for metallurgical examination. The tubing was of type 304 stainless steel and was 1/4" in diameter with a 0.065 wall. The tubing had been purchased as three different lots, the first in 45 ft. lengths and the other two as standards lengths. Tubing from the first lot was used primarily for the shield penetration and, therefore, sections of it are present in all lines of the system. It appears that chloride contamination entered the system in a portion of the first lot of tubing used for the shield penetration. The exact source of the chloride cannot be determined, but after considering the results and visiting the manufacturer's plant, it appears most likely the contamination was during the manufacturing process.
Date:
January 31, 1957
Creator:
Adamson, G. M; Hammond, T. M.; Kegley, T. M. & White, J. K.
Object Type:
Report
System:
The UNT Digital Library
Advanced Processing Technology semiannual report, March--December 1991. Volume 1, Number 1
This first issue of the APT Semiannual Report focuses on APT`s defense-related technologies. These technologies are a continuation of the research, development, and engineering work performed by LLNLs Special Isotope Separation (SIS) Program. SIS was the first large-scale DOE venture that had environmentally conscious manufacturing processes and facilities as its deliverables. The objectives were to create a facility where the only outputs were either usable products or disposable wastes, and to comply with existing and anticipated federal, state, and local regulations related to safeguards, security, health and safety. To meet these objectives, revolutionary changes were needed in plutonium processing operations, chemistry, and equipment. New processes had to be developed that enhanced worker safety, minimized operator radiation dose, minimized waste at the point of generation, and provided for built-in recycling of residues. The SIS Program developed and demonstrated the technology (both chemistry and physics) necessary to provide plutonium with individual isotopic tailoring. This process made it possible to transform fuel-grade plutonium into weapon-grade material. However, due to the changing world political climate, the country`s need for plutonium to make new weapons has decreased dramatically. As a result, the planned SIS plutonium-separation plant will not be built. After the SIS Program was …
Date:
December 31, 1991
Creator:
Adamson, M. & Kline-Simon, K.
Object Type:
Report
System:
The UNT Digital Library