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SALTSTONE CY07 TCLP RESULTS

Description: Saltstone waste forms were prepared in the Savannah River National Laboratory from Tank 50H samples and Z-Area premix material for each of the four quarters of calendar year 2007 (CY07). After the prescribed 28 day cure, samples of the saltstone were collected, and the waste form was shown to meet the South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79.261.24 and R.61-79.268.48(a) requirements for a nonhazardous waste form with respect to RCRA metals and underlying hazardous … more
Date: June 25, 2008
Creator: Cozzi, A
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hg removal from SRTC laboratory waste using an in-tank ion exchange probe

Description: An in-tank ion exchange column, described here, has been constructed to operate in the waste tanks at the Savannah River Technology Center (SRTC). The purpose of the column is to remove dissolved mercury from laboratory wastes and capture them on Duolite{trademark} GT-73 resin. This paper summarizes the results of operation of such a column on two batches of waste in one high activity tank and on one batch of waste in a low activity tank for the purpose of removing mercury from the liquid waste… more
Date: September 25, 1992
Creator: Bibler, J. P. & DeGange, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Response to requests by FMF and DWPF concerning disposal of FMF saltstone drums in Z-Area vaults

Description: Disposal of FMF saltstone in 55 gallon drums in the Z-Area Industrial Waste Landfill requires modification of the landfill permit. Approximately 5000 drums of FMF saltstone are currently stored on SC DHEC-permitted concrete storage pads adjacent to the burial ground. At a meeting with DWPF, FMF, and EPS on July 18, 1989, IWT agreed to supply the following information: (1) Consequence of disposal of CCA (Cu, Cr, As) treated wood pallets in the Z-Area vaults. (Four drums of FMF saltstone are curr… more
Date: July 25, 1989
Creator: Langton, C. A. & Cook, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical compatibility of DWPF canistered waste forms. Revision 1

Description: The Waste Acceptance Preliminary Specifications (WAPS) require that the contents of the canistered waste form are compatible with one another and the stainless steel canister. The canistered waste form is a closed system comprised of a stainless steel vessel containing waste glass, air, and condensate. This system will experience a radiation field and an elevated temperature due to radionuclide decay. This report discusses possible chemical reactions, radiation interactions, and corrosive react… more
Date: June 25, 1993
Creator: Harbour, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DISTRIBUTION COEFICIENTS (KD) GENERATED FROM A CORE SAMPLE COLLECTED FROM THE SALTSTONE DISPOSAL FACILITY

Description: Core samples originating from Vault 4, Cell E of the Saltstone Disposal Facility (SDF) were collected in September of 2008 (Hansen and Crawford 2009, Smith 2008) and sent to SRNL to measure chemical and physical properties of the material including visual uniformity, mineralogy, microstructure, density, porosity, distribution coefficients (K{sub d}), and chemical composition. Some data from these experiments have been reported (Cozzi and Duncan 2010). In this study, leaching experiments were co… more
Date: April 25, 2011
Creator: Almond, P. & Kaplan, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Information Basis for Developing Comprehensive Waste Management System-Us-Japan Joint Nuclear Energy Action Plan Waste Management Working Group Phase I Report.

Description: The activity of Phase I of the Waste Management Working Group under the United States - Japan Joint Nuclear Energy Action Plan started in 2007. The US-Japan JNEAP is a bilateral collaborative framework to support the global implementation of safe, secure, and sustainable, nuclear fuel cycles (referred to in this document as fuel cycles). The Waste Management Working Group was established by strong interest of both parties, which arise from the recognition that development and optimization of wa… more
Date: May 25, 2010
Creator: Nutt, M. & Division, Nuclear Engineering
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Solidification Tests Conducted on Transuranic Mixed Oil Waste (TRUM) at the Rocky Flats Environmental Technology Site (RFETS)

Description: Rocky Flats Environmental Technology Site (RFETS) near Golden, Colorado is the first major nuclear weapons site within the DOE complex that has been declared a full closure site. RFETS has been given the challenge of closing the site by 2006. Key to meeting this challenge is the removal of all waste from the site followed by site restoration. Crucial to meeting this challenge is Kaiser-Hill's (RFETS Operating Contractor) ability to dispose of significant quantities of ''orphan'' wastes. Orphan … more
Date: February 25, 2002
Creator: Brunkow, W. G.; Campbell, D.; Geimer, R.; Gilbreath, C. & Rivera, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Biosphere Process Model Report

Description: To evaluate the postclosure performance of a potential monitored geologic repository at Yucca Mountain, a Total System Performance Assessment (TSPA) will be conducted. Nine Process Model Reports (PMRs), including this document, are being developed to summarize the technical basis for each of the process models supporting the TSPA model. These reports cover the following areas: (1) Integrated Site Model; (2) Unsaturated Zone Flow and Transport; (3) Near Field Environment; (4) Engineered Barrier … more
Date: May 25, 2000
Creator: Schmitt, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Some Trends in Radioactive Waste Form Behavior Revealed in Long-Term Field Tests

Description: Results from long-term field tests with borosilicate glass, cement and bitumen waste forms containing actual intermediate-level radioactive waste are summarized and discussed in the paper. Leaching behavior of the waste forms was evaluated by monitoring the contamination of contacting water. Measured leach rates of the three waste-form materials were in a narrow range in shallow subsurface repositories, but varied in a wide range at an open testing site owing to weathering of bitumen and cement… more
Date: February 25, 2002
Creator: Ojovan, M. I.; Ojovan, N. V.; Startceva, I. V. & Barinov, A. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Sulfur Polymer Stabilization/Solidification (SPSS) Treatability of Simulated Mixed-Waste Mercury Contaminated Sludge

Description: The Environmental Protection Agency (EPA) is currently evaluating alternative treatment standards for radioactively contaminated high mercury (Hg) subcategory wastes, which do not require the removal of mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA… more
Date: February 25, 2002
Creator: Adams, J. W.; Bowerman, B. S. & Kalb, P. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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PRECLOSURE CRITICALITY ANALYSIS PROCESS REPORT

Description: This report describes a process for performing preclosure criticality analyses for a repository at Yucca Mountain, Nevada. These analyses will be performed from the time of receipt of fissile material until permanent closure of the repository (preclosure period). The process describes how criticality safety analyses will be performed for various configurations of waste in or out of waste packages that could occur during preclosure as a result of normal operations or event sequences. The critica… more
Date: October 25, 2004
Creator: Danise, A.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Monitoring the consistency of multiphase waste forms.

Description: Methods are being developed for demonstrating that nonstandard high-level radioactive waste (HLW) forms meet the intent of the product consistency requirement in the Waste Acceptance System Requirements document (WASRD). That requirement was established for borosilicate HLW glasses ''to ensure a consistent glass product by controlling the vitrification process, consistency is necessary to reflect consideration for the waste package designs.'' [1] The test method specified in the WASRD for HLW g… more
Date: June 25, 2001
Creator: Ebert, W. L.; Lewis, M. A. & Johnson, S. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Advanced Nuclear Fuel Cycle Effects on the Treatment of Uncertainty in the Long-Term Assessment of Geologic Disposal Systems - Ebs Input

Description: The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geolog… more
Date: April 25, 2012
Creator: Sutton, M.; Blink, J. A.; Greenberg, H. R. & Sharma, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Response to requests by FMF and DWPF concerning disposal of FMF saltstone drums in Z-Area vaults

Description: Disposal of FMF saltstone in 55 gallon drums in the Z-Area Industrial Waste Landfill requires modification of the landfill permit. Approximately 5000 drums of FMF saltstone are currently stored on SC DHEC-permitted concrete storage pads adjacent to the burial ground. At a meeting with DWPF, FMF, and EPS on July 18, 1989, IWT agreed to supply the following information: (1) Consequence of disposal of CCA (Cu, Cr, As) treated wood pallets in the Z-Area vaults. (Four drums of FMF saltstone are curr… more
Date: July 25, 1989
Creator: Langton, C. A. & Cook, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hg removal from SRTC laboratory waste using an in-tank ion exchange probe

Description: An in-tank ion exchange column, described here, has been constructed to operate in the waste tanks at the Savannah River Technology Center (SRTC). The purpose of the column is to remove dissolved mercury from laboratory wastes and capture them on Duolite[trademark] GT-73 resin. This paper summarizes the results of operation of such a column on two batches of waste in one high activity tank and on one batch of waste in a low activity tank for the purpose of removing mercury from the liquid waste… more
Date: September 25, 1992
Creator: Bibler, J. P. & DeGange, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Efforts to Utilize High-Temperature Melting Technologies for ILLW and the Development of Guidelines for their Technical Assessment

Description: A couple of domestic institutions have been investigating the application of vitrification technology to treat low- and intermediate-level radioactive wastes in Korea. In the case that such investigations prove to be successful, it is expected that commercial vitrification plants will be constructed. The safety insuring on vitrification plants could not be compatible with criterion on radioactive waste management because the facilities are at high temperature and contain a variety of accommodat… more
Date: February 25, 2003
Creator: Lee, K. S.; Choi, Y. C.; Seo, Y. C.; Jeong, C. W. & Park, W. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Savannah River Site Waste Removal Program - Past, Present and Future

Description: The Savannah River Site has fifty-one high level waste tanks in various phases of operation and closure. These tanks were originally constructed to receive, store, and treat the high level waste (HLW) created in support of the missions assigned by the Department of Energy (DOE). The Federal Facilities Agreement (FFA) requires the high level waste to be removed from the tanks and stabilized into a final waste form. Additionally, closure of the tanks following waste removal must be completed. The… more
Date: February 25, 2002
Creator: Saldivar, E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The Evolution of Low-Level Radioactive Waste (LLW) Disposal Practices at the Savannah River Site Coupled with Vigorous Stakeholder Interaction

Description: Low-level radioactive waste (LLW) disposal practices at SRS evolved from trench disposal with little long-term performance basis to disposal in robust concrete vaults, again without modeling long-term performance. Now, based on an assessment of long-term performance of various waste forms and methods of disposal, the LLW disposal program allows for a ''smorgasbord'' of various disposal techniques and waste forms, all modeled to ensure long-term performance is understood. New disposal techniques… more
Date: February 25, 2002
Creator: Goldston, W. T.; Wilhite, E. L.; Cook, J. R. & Sauls, V. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Iron Phosphate Glass as Potential Waste Matrix for High-Level Radioactive Waste

Description: Recently, Iron Phosphate Glass (IPG) is investigated as the alternative final waste form for High-Level Radioactive Waste (HLW) in U.S. This study is aimed to investigate feasibility of IPG to HLW arising from commercial reprocessing in Japan. In order to evaluate favorable preparation conditions, maximum waste loading and property of IPG, the melting tests were carried. From the results of melting tests, the favorable preparation conditions was with matrix of Fe/P 0.43 (mole ratio in products)… more
Date: February 25, 2003
Creator: Fukui, T.; Ishinomori, T.; Endo, Y.; Sazarashi, M.; Ono, S. & Suzuki, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermogravimetric analysis studies

Description: Independent of thermal loading scenarios, the waste packages at the proposed repository at Yucca Mountain, Nevada will be exposed to environmental conditions of temperatures below 100 C with a range of possible relative humidities. Under high relative humidities, the formation of thin water films on the metal surfaces will occur. Previous work at ambient conditions has shown that on susceptible metals, the water-film-covered metal has an enhanced corrosion rate relative to the dry oxidation of … more
Date: August 25, 1995
Creator: Gdowski, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The effect of actinides on the microstructural development in a metallic high-level nuclear waste form

Description: Waste forms to contain material residual from an electrometallurgical treatment of spent nuclear fuel have been developed by Argonne National Laboratory. One of these waste forms contains waste stainless steel (SS), fission products that are noble to the process (e.g., Tc, Ru, Pd, Rh), Zr, and actinides. The baseline composition of this metallic waste form is SS-15wt.% Zr. The metallurgy of this baseline alloy has been well characterized. On the other hand, the effects of actinides on the alloy… more
Date: October 25, 1999
Creator: Keiser, D. D. Jr.; Sinkler, W.; Abraham, D. P.; Richardson, J. W., Jr. & McDeavitt, S. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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