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Metal waste forms from the electrometallurgical treatment of spent nuclear fuel
Stainless steel-zirconium alloys are being developed for the disposal of radioactive metal isotopes isolated using an electrometallurgical treatment technique to treat spent nuclear fuel. The nominal waste forms are stainless steel-15 wt% zirconium alloy and zirconium-8 wt% stainless steel alloy. These alloys are generated in yttria crucibles by melting the starting materials at 1,600 C under an argon atmosphere. This paper discusses the microstructures, corrosion and mechanical test results, and thermophysical properties of the metal waste form alloys.
Date:
May 1, 1996
Creator:
Abraham, D.P.; McDeavitt, S.M. & Park, J.
Object Type:
Report
System:
The UNT Digital Library
Health effects models for nuclear power plant accident consequence analysis. Modification of models resulting from addition of effects of exposure to alpha-emitting radionuclides: Revision 1, Part 2, Scientific bases for health effects models, Addendum 2
The Nuclear Regulatory Commission (NRC) has sponsored several studies to identify and quantify, through the use of models, the potential health effects of accidental releases of radionuclides from nuclear power plants. The Reactor Safety Study provided the basis for most of the earlier estimates related to these health effects. Subsequent efforts by NRC-supported groups resulted in improved health effects models that were published in the report entitled {open_quotes}Health Effects Models for Nuclear Power Plant Consequence Analysis{close_quotes}, NUREG/CR-4214, 1985 and revised further in the 1989 report NUREG/CR-4214, Rev. 1, Part 2. The health effects models presented in the 1989 NUREG/CR-4214 report were developed for exposure to low-linear energy transfer (LET) (beta and gamma) radiation based on the best scientific information available at that time. Since the 1989 report was published, two addenda to that report have been prepared to (1) incorporate other scientific information related to low-LET health effects models and (2) extend the models to consider the possible health consequences of the addition of alpha-emitting radionuclides to the exposure source term. The first addendum report, entitled {open_quotes}Health Effects Models for Nuclear Power Plant Accident Consequence Analysis, Modifications of Models Resulting from Recent Reports on Health Effects of Ionizing Radiation, Low …
Date:
May 1, 1993
Creator:
Abrahamson, S.; Bender, M. A.; Boecker, B. B.; Scott, B. R. & Gilbert, E. S.
Object Type:
Report
System:
The UNT Digital Library
Health effects models for nuclear power plant accident consequence analysis: Low LET radiation: Part 2, Scientific bases for health effects models
This report provides dose-response models intended to be used in estimating the radiological health effects of nuclear power plant accidents. Models of early and continuing effects, cancers and thyroid nodules, and genetic effects are provided. Two-parameter Weibull hazard functions are recommended for estimating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary and gastrointestinal syndromes -- are considered. Linear and linear-quadratic models are recommended for estimating cancer risks. Parameters are given for analyzing the risks of seven types of cancer in adults -- leukemia, bone, lung, breast, gastrointestinal, thyroid and ''other''. The category, ''other'' cancers, is intended to reflect the combined risks of multiple myeloma, lymphoma, and cancers of the bladder, kidney, brain, ovary, uterus and cervix. Models of childhood cancers due to in utero exposure are also provided. For most cancers, both incidence and mortality are addressed. Linear and linear-quadratic models are also recommended for assessing genetic risks. Five classes of genetic disease -- dominant, x-linked, aneuploidy, unbalanced translocation and multifactorial diseases --are considered. In addition, the impact of radiation-induced genetic damage on the incidence of peri-implantation embryo losses is discussed. The uncertainty in modeling radiological health risks is addressed by …
Date:
May 1, 1989
Creator:
Abrahamson, S.; Bender, M.; Book, S.; Buncher, C.; Denniston, C.; Gilbert, E. et al.
Object Type:
Report
System:
The UNT Digital Library
Effect of gamma radiation on groundwater chemistry and glass leaching as related to the NNWSI repository site
To address the effect of ionizing radiation on groundwater chemistry and waste form durability, NNWSI is performing an extensive set of experiments as a function of dose rate (2 x 10{sup 5}, 1 x 10{sup 4}, 1 x 10{sup 3}, and 0 rad/h). The results of the tests done at 2 x 10{sup 5} rad/h have been reported, while the 1 x 10{sup 3} and 0 rad/h tests are in progress. This paper presents an overview of the results of the tests done at 1 x 10{sup 4} rad/h and discusses the relevance of these tests to repository conditions. An interpretation of the results relating to the manner by which the glass waste form corrodes is presented elsewhere. A complete discussion of the effect of gamma radiation on groundwater chemistry and waste form durability will be presented when the series of experiments are complete.
Date:
May 1986
Creator:
Abrajano, T.; Bates, J.; Ebert, W. & Gerding, T.
Object Type:
Report
System:
The UNT Digital Library
A METHODOLOGY FOR DETERMINING THE DOSE RATE FOR BOUNDING MASS LIMITS IN A 9977 PACKAGING
The Small Gram Quantity (SGQ) concept is based on the understanding that the hazards associated with the shipment of a radioactive material are directly proportional to its mass. This study describes a methodology that estimates the acceptable masses for several neutron and gamma emitting isotopes that can be shipped in a 9977 Package compliant with the Title 10 of the Code of Federal Regulations, Part 71 (10CFR71) external radiation level limits. 10CFR71.33 states that a shipping application identifies the radioactive and fissile materials at their maximum quantity and provides an evaluation demonstrating compliance with the external radiation standards. Since rather small amounts of some isotopes emit sufficiently strong radiation to produce a large external dose rate, quantifying of the dose rate for a proposed content is a challenging issue for the SGQ approach. It is essential to quantify external radiation levels from several common gamma and neutron sources that can be safely placed in a specific packaging, to ensure compliance with federal regulations. A methodology was established for determining the dose rate for bounding mass limits for a set of isotopes in the Model 9977 Shipping Package. Calculations were performed to estimate external radiation levels using the MCNP radiation transport …
Date:
May 24, 2012
Creator:
Abramczyk, G.; Bellamy, S.; Nathan, S. & Loftin, B.
Object Type:
Article
System:
The UNT Digital Library
MODEL 9977 B(M)F-96 SAFETY ANALYSIS REPORT FOR PACKAGING
This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on and for the 9977 Shipping Package, referred to as the General Purpose Fissile Package (GPFP). The performance evaluation presented in this SARP documents the compliance of the 9977 package with the regulatory safety requirements for Type B packages. Per 10 CFR 71.59, for the 9977 packages evaluated in this SARP, the value of ''N'' is 50, and the Transport Index based on nuclear criticality control is 1.0. The 9977 package is designed with a high degree of single containment. The 9977 complies with 10 CFR 71 (2002), Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10 CFR 20 (2003) for As Low As Reasonably Achievable (ALARA) principles. The 9977 also satisfies the requirements of the Regulations for the Safe Transport of Radioactive Material--1996 Edition (Revised)--Requirements. IAEA Safety Standards, Safety Series No. TS-R-1 (ST-1, Rev.), International Atomic Energy Agency, Vienna, Austria (2000). The 9977 package is designed, analyzed and fabricated in accordance with Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1992 edition.
Date:
May 18, 2006
Creator:
Abramczyk, G; Paul Blanton, P & Kurt Eberl, K
Object Type:
Report
System:
The UNT Digital Library
Engineering Report on the Drilling in the Lemhi Pass Area of Montana
"This report presents engineering details, statistics, individual borehole histories, and geophysical logs of the four holes drilled in the Lemhi Pass, Montana/Idaho area." (from Introduction)
Date:
May 1980
Creator:
Abramiuk, I. N.
Object Type:
Report
System:
The UNT Digital Library
First results from Mark II at SPEAR
First results from the SLAC-LBL Mark II magnetic detector at SPEAR are presented. The performance of the detector is discussed and preliminary results are given on inclusive baryon production R/sub p + anti p/, R/sub ..lambda.. + anti ..lambda../, on decay modes of the D mesons and on two-photon production of eta' mesons.
Date:
May 1, 1979
Creator:
Abrams, G. S.; Alam, M. S. & Blocker, C. A.
Object Type:
Article
System:
The UNT Digital Library
PERFORMANCE OF THE LEAD/LIQUID ARGON SHOWER COUNTER SYSTEM OF THE MARK II DETECTOR AT SPEAR
The shower counter system of the SLAC-LBL Mark II detector is a large lead/liquid argon system of the type pioneered by Willis and Radekal; however, it differs in most details and is much larger than other such detectors currently in operation, It contains, for example, 8000 liters of liquid argon and 3000 channels of low noise electronics, which is about eight times the size of the system of Willis et al. in the CERN ISR. This paper reports, with little reference to design, on the operation and performance of the Mark II system during approximately a year and a half of operation at the Stanford Linear Accelerator Center's e{sup +}-e{sup -} facility, SPEAR. The design and construction of the system have previously been described and a detailed discussion of all aspects -- design, construction, operation, and performance -- is in preparation.
Date:
May 1, 1980
Creator:
Abrams, G. S.; Blocker, C. A.; Briggs, D. D.; Carithers, W. C.; Dieterle, W. E.; Eaton, M. W. et al.
Object Type:
Article
System:
The UNT Digital Library
MEASUREMENTS OF THE PROPERTIES OF D MESON DECAYS
We present a study of the decay properties of charmed D mesons produced near the peak of the {psi}" (3770) resonance in e{sup +}e{sup -} annihilation. Branching fractions for nine Cabibbo-favored and three Cabibbo-suppressed decay modes are presented along with upper limits on one additional Cabibbo-favored and four additional Cabibbo-suppressed decay modes. A study of K{pi}{pi} decay mode Dalitz plots reveals a large quasi-two-body pseudoscalar-vector component for the D{sup 0} decays and an apparent nonuniform population an the Dalitz plot for the D{sup +} decay into K{sup -}{pi}{sup +}{pi}{sup +}. Using tagged events, we measure the charged particle multiplicity and strange particle content of D decays. A measurement of the D{sup +} and D{sup 0} semileptonic decay fractions indicates that the D{sup +} has a significantly longer lifetime than the D{sup 0}.
Date:
May 1, 1980
Creator:
Abrams, G.; Blocker, C. A.; Blondel, A.; Carithers, W. C.; Chinowsky, W.; Coles, M. W. et al.
Object Type:
Article
System:
The UNT Digital Library
Drying behavior of K-East canister sludge
A series of tests were conducted by Pacific Northwest National Laboratory to evaluate the drying behavior of sludge taken from the Hanford K-East Basin storage canisters. Some of the components of K-Basin sludge, such as oxides of uranium and its hydrates, could be associated with the spent nuclear fuel that will ultimately be loaded into Multi-Canister Overpacks (MCOs) and transferred to interim dry storage on the Hanford Site. The materials sealed in the MCOs must be compatible with the storage facility safety basis and the design accident analyses. Understanding the drying behavior of hydrates that may be formed by the reaction of uranium oxides (corrosion products) and water will help ensure these criteria are addressed. Drying measurements of sludge samples collected from K-East Basin canisters showed the water content (physically plus chemically bound) to range between 5 wt% and 75 wt%. Uranium oxide hydrates, the main source of gaseous products that can pressurize the MCOs during storage, constituted about 3 wt% to 15 wt% of the total water content of the initial weight. Most of the physically bound water was assumed to be released from the samples at ambient temperature when the system was pumped down to vacuum conditions of …
Date:
May 1, 1998
Creator:
Abrefah, J.; Buchanan, H. C. & Marschman, S. C.
Object Type:
Report
System:
The UNT Digital Library
Polycube oxidation and factors affecting the concentrations of gaseous products
The polycubes stored at the Hanford Plutonium Finishing Plant (PFP) have been identified in a Vulnerability Assessment as material that requires a stabilization process in support of the Defense Nuclear Facility Safety Board Recommendation 94-1. The baseline plan involves a pyrolysis process to separate out the plutonium and uranium oxides before the remaining material is packaged for interim storage, in accordance with the Record of Decision (ROD), issued June 25, 1996, for the Plutonium Finishing Plant Stabilization Final Environmental Impact Statement, DOE/EIS-0244-F. The polycubes were manufactured at Hanford in the 1960s for use in criticality studies to determine the hydrogen-to-fissile atom ratios for neutron moderation. A mixture of plutonium and/or uranium oxides and a polystyrene (vinyl benzene) matrix, cast into the shape of cubes, the polycubes simulated solutions containing high concentrations of fissile materials. The polycubes varied in size, typically 1/2 x 2 x 2 in. up to 2 x 2 x 2 in., and were sealed with a coating of aluminum paint and/or tape (PVC or Shurtape). The estimated 1,600 polycubes (calculated 179,165 grams net weight) stored at PFP were packed in vented food cans with five to eight cubes per can to accommodate gas generation by radiolysis. Some …
Date:
May 4, 2000
Creator:
Abrefah, J.; MacFarlan, P. J. & Sell, R. L.
Object Type:
Report
System:
The UNT Digital Library
Examination of the surface coating removed from K-East Basin fuel elements
This report provides the results of studies conducted on coatings discovered on the surfaces of some N-Reactor spent nuclear fuel (SNF) elements stored at the Hanford K-East Basin. These elements had been removed from the canisters and visually examined in-basin during FY 1996 as part of a series of characterization tests. The characterization tests are being performed to support the Integrated Process Strategy developed to package, dry, transport, and store the SNF in an interim storage facility on the Hanford site. Samples of coating materials were removed from K-East canister elements 2350E and 2540E, which had been sent, along with nine other elements, to the Postirradiation Testing Laboratory (327 Building) for further characterization following the in-basin examinations. These coating samples were evaluated by Pacific Northwest National Laboratory using various analytical methods. This report is part of the overall studies to determine the drying behavior of corrosion products associated with the K-Basin fuel elements. Altogether, five samples of coating materials were analyzed. These analyses suggest that hydration of the coating materials could be an additional source of moisture in the Multi-Canister Overpacks being used to contain the fuel for storage.
Date:
May 1, 1998
Creator:
Abrefah, J.; Marschman, S.C. & Jenson, E.D.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CO ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr gram iron (NL/hr/gFe) using a synthesis gas with 0.5--1.0 H{sub 2}:Co ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CO ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CO ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CP ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CO ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability. Technical progress report No. 5, September 16, 1988--December 16, 1988
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CO ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability. Technical progress report No. 6, December 16, 1988--March 16, 1989
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CO ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability. Technical progress report No. 7, March 16, 1989--June 16, 1989
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CP ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability. Technical progress report No. 8, June 16, 1989--September 16, 1989
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CO ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
The development of precipitated iron catalysts with improved stability. Technical progress report No. 9, September 16, 1989--December 16, 1989
The objective of this program is to identify the chemical principles governing the deactivation of precipitated iron catalysts during Fischer-Tropsch synthesis and to use these chemical principles in the design of catalysts suitable for slurry reactors. The performance targets are 88% CO+H{sub 2} conversion with less than 1% deactivation/day for 1 month and a methane and ethane selectivity of no more than 7% (based on hydrocarbons and oxygenates only) at a space velocity of at least 2 normal liters per hr per gram iron (NL/hr/gFe) using a synthesis gas with 0.5-1.0 H{sub 2}:CO ratio in a slurry reactor.
Date:
May 6, 1992
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library