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Properties of radioactive wastes and waste containers. Quarterly progress report, April-June 1980

Description: A study was initiated to determine the effect of varying V/S (the ratio of the waste form volume to its surface area) on the leachability of radioisotopes incorported in cement forms. Cesium-137 and strontium-85 mixed with a simulated formulation of waste derived from forced recirculation evaporator bottoms of LWR's were solidified in portland II cement. The V/S ratios of the forms varied from 0.41 to 2.77. The resulting forms were leached using a modified IAEA procedure. Leaching data indicate an inverse relationship between the amount of leached radioactivity and V/S value. Experiments were undertaken to determine the degree of desorption of Cs-137 initially adsorbed on cation organic ion exchange resins upon mixing with cement paste and during the plastic phase of the curing process. Portland II and lumnite cements were used as the solidification agents. Twenty seven percent of the Cs-137 was removed from the ion exchange resins after two hours of contact with portland II cement, whereas, 43% of the activity was removed from the resins after the same contact period with lumnite cement. 15 refs., 12 figs., 4 tabs.
Date: August 1, 1980
Creator: Morcos, N. & Weiss, A.J.
Partner: UNT Libraries Government Documents Department

Improving in vivo calibration phantoms

Description: Anthropomorphic phantoms have been the basis for quantification of radioactive material in the body using in vivo measurements. The types of phantoms used and the degree of anthropomorphic detail vary depending on the counting application, the radioactive material to be measured, phantom availability and cost. Consequently, measurement results for the same types of radioactive material from different facilities are not always comparable. At a February 1990 meeting at the National Institute of Standards and Technology (NIST) the need to develop the gold standards'' or primary reference standards for in vivo phantoms was discussed in detail. The consensus of the attendees at the meeting was that the state of the art in phantoms was adequate as a starting point and that there was no need to start phantom development from scratch. In particular, the torso phantom developed at the Lawrence Livermore National Laboratory (LLNL) and its commercial progeny, the bottle manikin absorption (BOMAB) phantom and the American National Standards Institute (ANSI) Standard N44.3 thyroid phantom, were identified as the starting points for the development of the primary reference standards. Working groups at the meeting subsequently recommended design improvements for the existing phantom designs. The implementation of these recommendations is the subject of this paper.
Date: October 1, 1991
Creator: Lynch, T.P. & Olsen, P.C.
Partner: UNT Libraries Government Documents Department

Measurement of energy deposited by charged-particle beams in composite targets

Description: We have measured the energy deposited in two types of composite targets by a number of charged-particle beams: targets made of /sup 238/U, Lucite, and polyethylene were exposed to 0.26-GeV protons and 0.33-GeV deuterons, and aluminum-Lucite composites were exposed to 0.5-GeV electrons. In addition, we measured neutrons and gamma rays emitted from solid targets of various materials (including /sup 238/U and iron) exposed to 0.26-GeV protons and 0.33-GeV deuterons. We used passive detectors (thermoluminescence dosimeters, Lexan fission track recorders, and photographic emulsions) to measure the nonfission dose and the fission-fragment dose from the primary beam and its shower of products. Measurements were made at various depths and radial positions in the targets. Plots and numerical values of the measured doses are presented. The emission of neutrons and gamma rays was measured with a liquid-deuterated-benzene detector. In general, the dose profile with depth is similar for 0.26-GeV protons and 0.33-GeV deuterons. The ratio of return neutrons to gamma rays increases with increasing target mass number. Deuterons, however, produce from 1.7 to 5.8 times as many neutrons and gamma rays per particle as do protons.
Date: July 2, 1980
Creator: Farley, E.; Becker, J.; Crase, K.; Howe, R. & Selway, D.
Partner: UNT Libraries Government Documents Department

Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

Description: This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately.
Date: February 1, 1988
Creator: Weiss, A. J.
Partner: UNT Libraries Government Documents Department

Emissions of greenhouse gases from the use of transportation fuels and electricity

Description: This report presents estimates of full fuel-cycle emissions of greenhouse gases from using transportation fuels and electricity. The data cover emissions of carbon dioxide (CO{sub 2}), methane, carbon monoxide, nitrous oxide, nitrogen oxides, and nonmethane organic compounds resulting from the end use of fuels, compression or liquefaction of gaseous transportation fuels, fuel distribution, fuel production, feedstock transport, feedstock recovery, manufacture of motor vehicles, maintenance of transportation systems, manufacture of materials used in major energy facilities, and changes in land use that result from using biomass-derived fuels. The results for electricity use are in grams of CO{sub 2}-equivalent emissions per kilowatt-hour of electricity delivered to end users and cover generating plants powered by coal, oil, natural gas, methanol, biomass, and nuclear energy. The transportation analysis compares CO{sub 2}-equivalent emissions, in grams per mile, from base-case gasoline and diesel fuel cycles with emissions from these alternative- fuel cycles: methanol from coal, natural gas, or wood; compressed or liquefied natural gas; synthetic natural gas from wood; ethanol from corn or wood; liquefied petroleum gas from oil or natural gas; hydrogen from nuclear or solar power; electricity from coal, uranium, oil, natural gas, biomass, or solar energy, used in battery-powered electric vehicles; and hydrogen and methanol used in fuel-cell vehicles.
Date: November 1, 1991
Creator: DeLuchi, M.A. (California Univ., Davis, CA (United States))
Partner: UNT Libraries Government Documents Department

Resin bead methodology as applied to fuel burn-up and fissile inventories

Description: A new technique has been developed that allows acquisition of samples from matrices difficult to access. While the examples given in this paper are from the nuclear field, the technique is readily modified to address other areas. The technique involves obtaining samples on resin beads; each bead then comprises a sample for mass spectrometric analysis. Through the application of isotope dilution, concentrations of the target elements can be obtained in addition to their isotopic compositions. Examples of application of this technique are given for U, Pu, and Nd. 19 refs., 3 figs., 3 tabs.
Date: January 1, 1986
Creator: Smith, D.H.; Walker, R.L. & Carter, J.A.
Partner: UNT Libraries Government Documents Department

Comparison of detector materials for time-of-flight positron tomography

Description: Knowledge of detection efficiency and timing resolution is essential when comparing detector materials for time-of-flight positron tomography. We present results of Monte Carlo calculations of the detection efficiency of plastic, lead loaded plastic, NaI(T1), liquid xenon, bismuth germanate (BGO), CsF, BaF/sub 2/, Ge, and HgI/sub 2/ for 511 keV photons. We also use recently published values of timing resolution for these detector materials to tabulate the quantity (efficiency)/sup 2//(time resolution) which is a measure of the relative sensitivity for time of flight positron tomography.
Date: June 1, 1982
Creator: Derenzo, S.E.
Partner: UNT Libraries Government Documents Department

Radiogenic gas accumulation in TRU waste storage drums

Description: A field experiment was conducted over a four-year time span to determine the effect of high-activity transuranic (TRU) waste on the atmosphere within TRU waste storage drums typical of those generated in Savannah River Plant operation. Routine gas composition analyses showed that a significant amount of hydrogen can accumulate in drums that contain high alpha activity, and that flammable gas mixtures could form in such drums in spite of the radiolytic consumption of oxygen. According to this study, gas pressure accumulation does not pose a threat to the integrity of the TRU waste containers that are now being stored at the Savannah River Plant. Therefore, the 20-year storage criterion is still viable. However, the continued avoidance of a perfectly gas-tight drum seal (e.g., epoxy, metal welding) is recommended. The test drums will continue to be monitored.
Date: January 1, 1982
Creator: Ryan, J.P.
Partner: UNT Libraries Government Documents Department

Glass ceramics for explosive device headers

Description: The desired features of a header for our advanced explosive devices include small size; 700 Mpa static burst strength; corrosion resistant alloys for electrodes, bridgewire, and housing; integral charge holder; high thermal conductivity (approaching that of alumina ceramic); no braze around the electrodes; design flexibility and quick turnaround time for fabrication of development prototypes; and low cost.
Date: January 1, 1980
Creator: Ballard, C. P.; Eagan, R. J. & Kjeldgaard, E. A.
Partner: UNT Libraries Government Documents Department

Energy technologies at Sandia National Laboratories: Past, Present, Future

Description: We at Sandia first became involved with developing energy technology when the nation initiated its push toward energy independence in the early 1970s. That involvement continues to be strong. In shaping Sandia's energy programs for the 1990s, we will build on our track record from the 70s and 80s, a record outlined in this publication. It contains reprints of three issues of Sandia's Lab News that were devoted to our non-nuclear energy programs. Together, they summarize the history, current activities, and future of Sandia's diverse energy concerns; hence my desire to see them in one volume. Written in the fall of 1988, the articles cover Sandia's extremely broad range of energy technologies -- coal, oil and gas, geothermal, solar thermal, photovoltaics, wind, rechargeable batteries, and combustion.
Date: August 1, 1989
Partner: UNT Libraries Government Documents Department

Radioactive material package seal tests

Description: General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 {times} 10{sup {minus}7} std cm{sup 3}/s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab.
Date: January 1, 1990
Creator: Madsen, M.M.; Humphreys, D.L. & Edwards, K.R.
Partner: UNT Libraries Government Documents Department

Testing a new cesium-specific ion exchange resin for decontamination of alkaline high-activity waste

Description: Radioactive Cs-137 is a fission produce found in wastes produced by reprocessing fuels from nuclear reactors. The highest concentrations of this isotope in wastes from the reprocessing of defense production reactors are found in the alkaline high-activity waste, a mixture primarily of sodium nitrate and sodium hydroxide called the supernate. In recent years, much research has been directed at methods for the selective removal and concentration of Cs-137 during waste processing. The approach to the ultimate management of high-activity waste at the Savannah River Site (SRS) is to remove cesium from the supernate, combine it with insoluble sludge formed on neutralization of acidic waste, and convert them both to glass by vitrification in a joule heater melter. A cesium-specific ion exchange resin that will adequately decontaminate the supernate but will not introduce excessive amounts of organic material into the melter has been developed at SRS. The resin has been tested with simulated, both at SRS and at Battelle's Pacific Northwest Lab, and with actual supernate at SRS. It has consistently shown reliable performance and high selectivity than other organic ion exchangers for cesium ion in those solutions. Repeated cycles on 200 mL. columns using simulated supernate feed and formic acid eluent have established operation parameters for the resin.
Date: January 1, 1989
Creator: Bibler, J.P.; Wallace, R.M. (Westinghouse Savannah River Co., Aiken, SC (United States)) & Bray, L.A. (Battelle Pacific Northwest Lab., Richland, WA (United States))
Partner: UNT Libraries Government Documents Department

Conservation and renewable energy technologies for transportation

Description: The Office of Transportation Technologies (OTT) is charged with long-term, high-risk, and potentially high-payoff research and development of promising transportation technologies that are unlikely to be undertaken by the private sector alone. OTT activities are designed to develop an advanced technology base within the US transportation industry for future manufacture of more energy-efficient, fuel-flexible, and environmentally sound transportation systems. OTT operations are focused on three areas: advanced automotive propulsion systems including gas turbines, low heat rejection diesel, and electric vehicle technologies; advanced materials development and tribology research; and research, development, demonstration, test, and evaluation (including field testing in fleet operations) of alternative fuels. Five papers describing the transportation technologies program have been indexed separately for inclusion on the data base.
Date: November 1, 1990
Partner: UNT Libraries Government Documents Department

Tri-State Synfuels Project Review: Volume 8. Commercial status of licensed process units. [Proposed Henderson, Kentucky coal to gasoline plant; licensed commercial processes]

Description: This document demonstrates the commercial status of the process units to be used in the Tri-State Synfuels Project at Henderson, Kentucky. The basic design philosophy as established in October, 1979, was to use the commercial SASOL II/III plants as a basis. This was changed in January 1982 to a plant configuration to produce gasoline via a methanol and methanol to gasoline process. To accomplish this change the Synthol, Oil workup and Chemical Workup Units were eliminated and replaced by Methanol Synthesis and Methanol to Gasoline Units. Certain other changes to optimize the Lurgi liquids processing eliminated the Tar Distillation and Naphtha Hydrotreater Units which were replaced by the Partial Oxidation Unit. The coals to be gasified are moderately caking which necessitates the installation of stirring mechanism in the Lurgi Dry Bottom gasifier. This work is in the demonstration phase. Process licenses either have been obtained or must be obtained for a number of processes to be used in the plant. The commercial nature of these processes is discussed in detail in the tabbed sections of this document. In many cases there is a list of commercial installations at which the licensed equipment is used.
Date: June 1, 1982
Partner: UNT Libraries Government Documents Department

Properties of radioactive wastes and waste containers. Quarterly progress report, April-June 1981

Description: An empirical relationship has been developed to estimate the cumulative fractional releases of /sup 137/Cs from simulated waste forms as a function of leaching time and the geometric surface-to-volume ratios. Data from an ongoing leaching study were used. The simulated waste forms consisted of organic cation exchange resins solidified in Portland I cement at a waste-to-cement ratio of 0.6 and water-to-cement ratio of 0.4. The nominal specimen dimensions were: 1-inch diameter x 1-inch high, 2-inch diameter x 2-inch high, 2-inch diameter x 4-inch high, 3-inch diameter x 3-inch high, 6-inch diameter x 6-inch high, 6-inch diameter x 12-inch high, and 12-inch diameter x 12-inch high. The waste forms were leached in deionized water using a modified IAEA leaching procedure. A study designed to evalate the leachability of /sup 137/Cs, /sup 85/Sr, and /sup 60/Co from simulated boric acid waste solidified in Portland III cement and to measure the compressive strength of the ensuing waste forms before and after leaching was concluded. Leaching data extending over 229 days are presented. The simulated waste forms were leached in deionized water using a modified IAEA leaching procedure. The compressive strength of the specimens was measured initially and after their exposure to a leaching environment for 352 days.
Date: November 1, 1981
Creator: Morcos, N. & Weiss, A.J.
Partner: UNT Libraries Government Documents Department

Model of penetration of coal boilers and cogeneration in the paper industry

Description: A model has been developed to forecast the penetration of coal boilers and cogeneration of electricity in the paper industry. Given the demand for energy services (process steam and electricity) by the paper industry, the Penetration Model forecasts the demand for purchased fuel and electricity. The model splits the demand for energy service between energy carriers (coal, fuel oil/natural gas, bark, and spent liquor) on the basis of the installed capacity of 16 types of boilers (combinations of four types of energy carriers and four types of throttle conditions). Investment in new boilers is allocated by an empirical distribution function among the 16 types of boilers on the basis of life cycle cost. In the short run (5 years), the Penetration Model has a small price response. The model has a large price response in the long run (30 years). For constant fuel prices, the model forecasts a 19-percent share for coal and a 65-percent share for residual oil in the year 2000. If the real price of oil and gas doubles by the year 2000, the model forecasts a 68-percent share for coal and a 26-percent share for residual oil.
Date: January 1, 1982
Creator: Reister, D.B.
Partner: UNT Libraries Government Documents Department

Synthetic crude oils carcinogenicity screening tests. Quarterly report, October 16, 1978--February 15, 1979

Description: Four crude oils (Southern Louisiana Crude Petroleum, H. Coal Syncrude, Paraho Crude Shale Oil, and Geokinetics in situ Shale Oil) have been distilled into four fractions (naphtha, mid-distillate, gas oil, and residue) for analysis and biological (mutagenicity and carcinogenicity) screening testing. Results of selected analytical tests have been obtained on the original crude oils and the fractions. Ames tests and initiation/promotion tests have been started on the original crude oils and the fractions. Four additional synthetic crude oils (Exxon EDS, SRC II, H Coal Fuel Oil, and Occidental In Situ Shale Oil) are being obtained for a second similar series of tests to be started in approximately four months.
Date: January 1, 1979
Creator: Calkins, W.H.; Deye, J.F.; King, C.F.; Hartgrove, R.W. & Krahn, D.F.
Partner: UNT Libraries Government Documents Department

Kilogram-scale purification of americium by ion exchange

Description: Sequential anion and cation exchange processes have been used for the final purification of /sup 241/Am recovered during the reprocessing of aged plutonium metallurgical scrap. Plutonium was removed by absorption of Dowex 1, X-3.5 (30 to 50 mesh) anion exchange resin from 6.5 to 7.5 M HNO/sub 3/ feed solution. Following a water dilution to 0.75 to 1.0 M HNO/sub 3/, americium was absorbed on Dowex 50W, X-8 (50 to 100 mesh) cation exchange resion. Final purification was accomplished by elution of the absorbed band down 3 to 4 successive beds of the same resin, preloaded with Zn/sup 2 +/, with an NH/sub 4/OH buffered chelating agent. The recovery of mixed /sup 241/Am-/sup 243/Am from power reactor reprocessing waste has been demonstrated. Solvent extraction was used to recover a HNO/sub 3/ solution of mixed lanthanides and actinides from waste generated by the reprocessng of 13.5 tons of Shippingport Power Reactor blanket fuel. Sequential cation exchange band-displacement processes were then used to separate americium and curium from the lanthanides and then to separate approx. 60 g of /sup 244/Cm from 1000 g of mixed /sup 241/Am-/sup 243/Am.
Date: January 1, 1979
Creator: Wheelwright, E. J.
Partner: UNT Libraries Government Documents Department

Measurement and characterization of filtration efficiencies for prefilter materials used in aerosol filtration

Description: In applications where the filtration of large quantities of mixed (liquid and solid) aerosols is desired, a multistage filtration system is often employed. This system consists of a prefilter, a High Efficiency Particulate Air (HEPA) filter, and any number of specialized filters particular to the filtration application. The prefilter removes liquids and any large particles from the air stream, keeping them from prematurely loading the HEPA filter downstream. The HEPA filter eliminates 99.97% of all particulates in the aerosol. The specialized filters downstream of the HEPA filter can be used to remove organic volatiles or other vapors. While the properties of HEPA filters have been extensively investigated, literature characterizing the prefilter is scarce. The purpose of this report is to characterize the efficiency of the prefilter as a function of particle size, nature of the particle (solid or liquid), and the gas flow rate across the face of the prefilter. 1 ref., 4 figs.
Date: January 1, 1991
Creator: Sciortino, J. (State Univ. Coll., Fredonia, NY (USA))
Partner: UNT Libraries Government Documents Department

US energy conversion and use characteristics

Description: The long-range goal of the Energy Conversion and Utilization Technology (ECUT) Program is to enhance energy productivity in all energy-use sectors by supporting research on improved efficiency and fuel switching capability in the conversion and utilization of energy. Regardless of the deficiencies of current information, a summary of the best available energy-use information is needed now to support current ECUT program planning. This document is the initial draft of this type of summary and serves as a data book that will present current and periodically updated descriptions of the following aspects of energy use: gross US energy consumption in each major energy-use sector; energy consumption by fuel type in each sector; energy efficiency of major equipment/processes; and inventories, replacement rates, and use patterns for major energy-using capital stocks. These data will help the ECUT program staff perform two vital planning functions: determine areas in which research to improve energy productivity might provide significant energy savings or fuel switching and estimate the actual effect that specific research projects may have on energy productivity and conservation. Descriptions of the data sources and examples of the uses of the different types of data are provided in Section 2. The energy-use information is presented in the last four sections; Section 3 contains general, national consumption data; and Sections 4 through 6 contain residential/commercial, industrial, and transportation consumption data, respectively. (MCW)
Date: February 1, 1982
Creator: Imhoff, C.H.; Liberman, A. & Ashton, W.B.
Partner: UNT Libraries Government Documents Department

Effects of coal rank on the chemical composition and toxicological activity of coal liquefaction materials

Description: This report presents data from the chemical analysis and toxicological testing of coal liquefaction materials from the EDS and H-Coal processes operated using different ranks of coal. Samples of recycle solvent from the bottoms recycle mode of the EDS direct coal liquefaction process derived from bituminous, sub-bituminous, and lignite coals were analyzed. In addition, the H-Coal heavy fuel oils derived from bituminous and sub-bituminous coals were analyzed. Chemical methods of analysis included adsoprtion column chromatography, high-resolution gas chromatography, gas chromatography/mass spectrometry, and low-voltage probe-inlet mass spectrometry. The toxicological activity of selected samples was evaluated using the standard microbial mutagenicity assay, an initiation/promotion assay for mouse-skin tumorigenicity, and a static bioassy with Daphnia magna for aquatic toxicity of the water-soluble fractions. 22 refs., 16 figs., 14 tabs.
Date: May 1, 1986
Creator: Wright, C.W. & Dauble, D.D.
Partner: UNT Libraries Government Documents Department

Characteristics of attached radon-222 daughters under both laboratory and underground uranium-mine environments

Description: The organic, inorganic, and radiological characteristics of airborne aerosols have been measured as a function of particle size in controlled atmosphere test chambers and operating uranium mines. Concentrations of benzo(a)pyrene in two mines ranged from 26 to 57 ng/m/sup 3/ of air. The carbon chain length of adsorbed n-alkanes was correlated with particle size. Normal mining activities produced an ore dust aerosol with mass median aerodynamic diameter (MMAD) greater than 2 ..mu..m. The elements Na, Al, Si, K, Ca, Ti, V, Fe, and U exhibited elemental ratios similar to bulk ore and had comparable MMAD's. The S, Zn, and Pb were higher in aerosols than bulk ore and were associated with smaller MMAD particulates. Radon daughter particle size distributions were influenced by the kinds of particulates generated in mining activity.
Date: September 1, 1981
Creator: Jackson, P.O.; Cooper, J.A.; Langford, J.C. & Petersen, M.R.
Partner: UNT Libraries Government Documents Department

Evaluation of the near-term commercial potential of technologies being developed by the Office of Building Technologies Volune II - Survey Results

Description: This report consists of the results from each Equipment and Practice Form completed by the program managers and principal investigators. Information collected from the Equipment and Practice Form include the following: name and description of the technology; energy characteristics; when the technology will be ready for commercialization; estimated payback period; market sectors that would benefit; important commercialization barriers to overcome; energy-related benefits; and non-energy benefits of the technology to customers. Some of these technologies include: heat pumps, heat exchangers, insulation lighting systems; cooling systems, ventilation systems, burners, leak detection systems, retrofit procedure, operating and maintenance procedures, wall systems, windows, sampling equipment, measuring methods and instruments, thermal analysis methods, and computer codes.
Date: March 1, 1991
Creator: Weijo, R.O. (Portland General Electric Co., OR (USA)); Nicholls, A.K.; Weakley, S.A.; Eckert, R.L.; Shankle, D.L.; Anderson, M.R. et al.
Partner: UNT Libraries Government Documents Department

Extended storage of low-level radioactive waste: potential problem areas

Description: If a state or state compact does not have adequate disposal capacity for low-level radioactive waste (LLRW) by 1986 as required by the Low-Level Waste Policy Act, then extended storage of certain LLRW may be necessary. The issue of extended storage of LLRW is addressed in order to determine for the Nuclear Regulatory Commission the areas of concern and the actions recommended to resolve these concerns. The focus is on the properties and behavior of the waste form and waste container. Storage alternatives are considered in order to characterize the likely storage environments for these wastes. The areas of concern about extended storage of LLRW are grouped into two categories: 1. Behavior of the waste form and/or container during storage, e.g., radiolytic gas generation, radiation-enhanced degradation of polymeric materials, and corrosion. 2. Effects of extended storage on the properties of the waste form and/or container that are important after storage (e.g., radiation-induced oxidative embrittlement of high-density polyethylene and the weakening of steel containers resulting from corrosion by the waste). The additional information and actions required to address these concerns are discussed and, in particular, it is concluded that further information is needed on the rates of corrosion of container material by Class A wastes and on the apparent dose-rate dependence of radiolytic processes in Class B and C waste packages. Modifications to the guidance for solidified wastes and high-integrity containers in NRC's Technical Position on Waste Form are recommended. 27 references.
Date: January 1, 1985
Creator: Siskind, B.; Dougherty, D.R. & MacKenzie, D.R.
Partner: UNT Libraries Government Documents Department