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Shale fracturing injections at Oak Ridge National Laboratory: 1977-1979 series

Description: Intermediate-level waste solution generated at ORNL is periodically mixed with a cement-base blend of dry solids and injected into an impermeable shale formation at an approximate depth of 240 m (800 ft). The grout mix sets shortly after the injection, permanently fixing the radionuclides in the shale formation. A series of four injections of intermediate-level waste solution was made between 1977 and 1979. A total of 1.2 million l (314,000 gal) of waste solution containing 81,780 Ci of radionu… more
Date: September 1, 1980
Creator: Weeren, H.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Volatilities of ruthenium, iodine, and technetium on calcining fission product nitrate wastes

Description: Various high-level nitrate wastes were subjected to formic acid denitration. Formic acid reacts with the nitrate anion to yield noncondensable, inert gases according to the following equation: 4 HCOOH + 2 HNO/sub 3/ ..-->.. N/sub 2/O + 4 CO/sub 2/ + 5 H/sub 2/O. These gases can be scrubbed free of /sup 106/Ru, /sup 131/I, and /sup 99/Tc radioactivities prior to elimination from the plant by passage through HEPA filters. The formation of deleterious NO/sub x/ is avoided. Moreover, formic acid re… more
Date: January 1, 1980
Creator: Rimshaw, S. J. & Case, F. N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Safety assessment of the liquid-fed ceramic melter process

Description: As part of its development program for the solidification of high-level nuclear waste, Pacific Northwest Laboratory assessed the safety issues for a complete liquid-fed ceramic melter (LFCM) process. The LFCM process, an adaption of commercial glass-making technology, is being developed to convert high-level liquid waste from the nuclear fuel cycle into glass. This safety assessment uncovered no unresolved or significant safety problems with the LFCM process. Although in this assessment the LFC… more
Date: August 1, 1980
Creator: Buelt, J.L. & Partain, W.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-level nuclear waste immobilization program

Description: Existing high-level nuclear wastes in the United States are described along with current management techniques and long-term disposal options. All of the disposal options involve some type of immobilization operation to restrict radio-nuclide dispersion; the primary option is disposal of immobilized waste packages in deep (500-1000 meter) geological formations. Several immobilized waste forms currently under development are discussed, and form selection factors and regulatory criteria are ident… more
Date: January 1, 1980
Creator: Gordon, D E
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Significance of radiation effects in solid radioactive waste

Description: Proposed NRC criteria for disposal of high-level nuclear waste require development of waste packages to contain radionuclide for at least 1000 years, and design of repositories to prevent radionuclide release at an annual rate greater than 1 part in 100,000 of the total activity. The high-level wastes that are now temporarily stored as aqueous salts, sludges, and calcines must be converted to high-integrity solid forms that resist deterioration from radiation and other effects of long-term stor… more
Date: January 1, 1980
Creator: Permar, P H & McDonell, W R
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of tailored ceramics for geologic storage of nuclear wastes. Quarterly progress report, January 1-March 31, 1980

Description: In the second quarter of activities on developing Tailored Ceramic waste forms for SRP waste compositions, emphasis was on the chemistry controlling the incorporation of the waste elements into the crystalline phases of the high-alumina content ceramic and the major factors affecting the consolidation process. Research on the design and synthesis of oxide and phosphate ceramic waste forms has continued with emphasis on fluorite-structure oxides and on rare earth phosphates with the monazite str… more
Date: May 15, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Assessment of molten debris freezing in a severe RIA in-pile test. [PWR; BWR]

Description: An understanding of the freezing of molten debris on cold core structures following a hypothetical core meltdown accident in a light water reactor (LWR) is of importance to reactor safety analysis. The purpose of the present investigation was to analyze the transient freezing of the molten debris produced in a severe reactivity initiated accident (RIA) scoping test, designated RIA-ST-4, which was performed in the Power Burst Facility and simulated a BWR control rod drop accident. In the RIA-ST-… more
Date: January 1, 1980
Creator: El-Genk, Mohamed S. & Moore, Richard L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Design features of the laboratory-scale radiochemical immobilization system

Description: Under the High-Level Waste Immobilization Program, the Pacific Northwest Laboratory (PNL) is studying various ways to solidify high-level nuclear wastes. A variety of waste forms and processes are being investigated, with the most highly developed process being spray calcination coupled with in-can melting. This report describes a remote laboratory-scale system that was designed for the purpose of investigating the effects of different operating conditions and waste compositions on the product … more
Date: May 1, 1980
Creator: Hanson, M.S.; Knox, C.A. & Berger, D.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary technical data summary No. 3 for the Defense Waste Processing Facility

Description: This document presents an update on the best information presently available for the purpose of establishing the basis for the design of a Defense Waste Processing Facility. Objective of this project is to provide a facility to fix the radionuclides present in Savannah River Plant (SRP) high-level liquid waste in a high-integrity form (glass). Flowsheets and material balances reflect the alternate CAB case including the incorporation of low-level supernate in concrete. (DLC)
Date: May 1, 1980
Creator: Landon, L.F. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Small-scale demonstration of high-level radioactive waste processing and solidification using actual SRP waste

Description: A small-scale demonstration of the high-level radioactive waste solidification process by vitrification in borosilicate glass is being conducted using 5-6 liter batches of actual waste. Equipment performance and processing characteristics of the various unit operations in the process are reported and, where appropriate, are compared to large-scale results obtained with synthetic waste.
Date: January 1, 1980
Creator: Okeson, J K; Galloway, R M; Wilhite, E L; Woolsey, G B & B, Ferguson R
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nuclear waste management. Quarterly progress report, January-March 1980

Description: Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, cr… more
Date: June 1, 1980
Creator: Platt, A.M. & Powell, J.A. (comps.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Feasibility of methods and systems for reducng LNG tanker fire hazards

Description: In this program concepts for reducing fire hazards that may result from LNG tanker collisions are identified and their technical feasibility evaluated. Concepts considered include modifications to the shipborne LNG containers so that in the event of a container rupture less of the contents would spill and/or the contents would spill at a reduced rate. Changes in the cargo itself, including making the LNG into a gel, solidifying it, converting it to methanol, and adding flame suppressants are al… more
Date: August 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

State-of-the-art report on low-level radioactive waste treatment

Description: An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type… more
Date: September 1, 1980
Creator: Kibbey, A. H. & Godbee, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Unit operations used to treat process and/or waste streams at nuclear power plants. [R]

Description: Estimates are given of the annual amounts of each generic type of LLW (i.e., Government and commerical (fuel cycle and non-fuel cycle)) that is generated at LWR plants. Many different chemical engineering unit operations used to treat process and/or waste streams at LWR plants include adsorption, evaporation, calcination, centrifugation, compaction, crystallization, drying, filtration, incineration, reverse osmosis, and solidification of waste residues. The treatment of these various streams an… more
Date: January 1, 1980
Creator: Godbee, H. W. & Kibbey, A. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

High level nuclear waste

Description: The DOE Division of Waste Products through a lead office at Savannah River is developing a program to immobilize all US high-level nuclear waste for terminal disposal. DOE high-level wastes include those at the Hanford Plant, the Idaho Chemical Processing Plant, and the Savannah River Plant. Commercial high-level wastes, for which DOE is also developing immobilization technology, include those at the Nuclear Fuel Services Plant and any future commercial fuels reprocessing plants. The first immo… more
Date: January 1, 1980
Creator: Crandall, J L
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

High-power laser and arc welding of thorium-doped iridium alloys

Description: The arc and laser weldabilities of two Ir-0.3% W alloys containing 60 and 200 wt ppM Th have been investigated. The Ir-.03% W alloy containing 200 wt ppM Th is severely prone to hot cracking during gas tungsten-arc welding. Weld metal cracking results from the combined effects of heat-affected zone liquation cracking and solidification cracking. Scanning electron microscopic analysis of the fractured surface revealed patches of low-melting eutectic. The cracking is influenced to a great extent … more
Date: May 1, 1980
Creator: David, S.A. & Liu, C.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of molten debris freezing and wall erosion during a severe RIA test. [PWR; BWR]

Description: A one-dimensional physical model was developed to study the transient freezing of the molten debris layer (a mixture of UO/sub 2/ fuel and zircaloy cladding) produced in a severe reactivity initiated accident in-pile test and deposited on the inner surface of the test shroud wall. The wall had a finite thickness and was cooled along its outer surface by coolant bypass flow. Analyzed are the effects of debris temperature, radiation cooling at the debris layer surface, zircaloy volume ratio withi… more
Date: January 1, 1980
Creator: El-Genk, M.S. & Moore, R.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

High-level waste program progress report, January 1, 1980-March 31, 1980

Description: FUETAP concretes cured at 100/sup 0/C and 0.1 or 0.6 MPa had essentially the same physical properties as those cured at higher temperatures and pressures. Standard specimens containing high concentrations of /sup 244/Cm showed little gasification after 1 month. The large (23-cm ID) spray calciner has been completed and is operating satisfactorily. Construction was completed on a sphere-forming system capable of producing 100-g batches of Synroc spheres by internal gelation, and several runs wer… more
Date: May 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear waste management. Quarterly progress report, October-December 1979

Description: Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic iso… more
Date: April 1, 1980
Creator: Platt, A.M. & Powell, J.A. (comps.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Low-temperature ceramic radioactive waste form characteriztion of supercalcine-based monazite-cement composites

Description: Simulated radioactive waste solidification by a lower temperature ceramic (cement) process is being investigated. The monazite component (simulated by NdPO/sub 4/) of supercalcine-ceramic has been solidified in cement and found to generate a solid form with low leachability. Several types of commercial cements and modifications thereof were used. No detectable release of Nd or P was found through characterizing the products of accelerated hydrothermal leaching at 473/sup 0/K (200/sup 0/C) and 3… more
Date: April 18, 1980
Creator: Roy, D. M.; Wakeley, L. D. & Atkinson, S. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Alternative solid forms for Savannah River Plant defense waste

Description: Solid forms and processes were evaluated for immobilization of SRP high-level radioactive waste, which contains bulk chemicals such as hydrous iron and aluminium oxides. Borosilicate glass currently is the best overall choice. High-silica glass, tailored ceramics, and coated ceramics are potentially superior products, but require more difficult processes.
Date: January 1, 1980
Creator: Stone, J.A.; Goforth, S.T. & Smith, P.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Volatility of ruthenium-106, technetium-99, and iodine-129, and the evolution of nitrogen oxide compounds during the calcination of high-level, radioactive nitric acid waste

Description: The nitrate anion is the predominant constituent in all high-level nuclear wastes. Formic acid reacts with the nitrate anion to yield noncondensable, inert gases (N/sub 2/ or N/sub 2/O), which can be scrubbed free of /sup 106/Ru, /sup 129/I, and /sup 99/Tc radioactivities prior to elimination from the plant by passing through HEPA filters. Treatment of a high-level authentic radioactive waste with two moles of formic acid per mole of nitrate anion leads to a low RuO/sub 4/ volatility of about 0… more
Date: February 1, 1980
Creator: Rimshaw, S. J.; Case, F. N. & Tompkins, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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