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REACTOR GROUT THERMAL PROPERTIES

Description: Savannah River Site has five dormant nuclear production reactors. Long term disposition will require filling some reactor buildings with grout up to ground level. Portland cement based grout will be used to fill the buildings with the exception of some reactor tanks. Some reactor tanks contain significant quantities of aluminum which could react with Portland cement based grout to form hydrogen. Hydrogen production is a safety concern and gas generation could also compromise the structural inte… more
Date: January 28, 2011
Creator: Steimke, J.; Qureshi, Z.; Restivo, M. & Guerrero, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING GROUTING OPERATIONS IN C-REACTOR DISASSEMBLY BASIN

Description: C-reactor disassembly basin is being prepared for deactivation and decommissioning (D and D). D and D activities will consist primarily of immobilizing contaminated scrap components and structures in a grout-like formulation. The disassembly basin will be the first area of the C-reactor building that will be immobilized. The scrap components contain aluminum alloy materials. Any aluminum will corrode very rapidly when it comes in contact with the very alkaline grout (pH > 13), and as a resul… more
Date: July 12, 2011
Creator: Wiersma, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SLUDGE HEEL REMOVAL BY ALUMINUM DISSOLUTION AT SAVANNAH RIVER SITE 12390

Description: High Level Waste (HLW) at the Savannah River Site (SRS) is currently stored in aging underground storage tanks. This waste is a complex mixture of insoluble solids, referred to as sludge, and soluble salts. Continued long-term storage of these radioactive wastes poses an environmental risk. Operations are underway to remove and disposition the waste, clean the tanks and fill with grout for permanent closure. Heel removal is the intermediate phase of the waste retrieval and tank cleaning process… more
Date: January 12, 2012
Creator: Keefer, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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BENCH SCALE SALTSTONE PROCESS DEVELOPMENT MIXING STUDY

Description: The Savannah River National Laboratory (SRNL) was requested to develop a bench scale test facility, using a mixer, transfer pump, and transfer line to determine the impact of conveying the grout through the transfer lines to the vault on grout properties. Bench scale testing focused on the effect the transfer line has on the rheological property of the grout as it was processed through the transfer line. Rheological and other physical properties of grout samples were obtained prior to and after… more
Date: August 3, 2011
Creator: Cozzi, A. & Hansen, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TANKS 18 AND 19-F STRUCTURAL FLOWABLE GROUT FILL MATERIAL EVALUATION AND RECOMMENDATIONS

Description: Cementitious grout will be used to close Tanks 18-F and 19-F. The functions of the grout are to: (1) physically stabilize the final landfill by filling the empty volume in the tanks with a non compressible material; (2) provide a barrier for inadvertent intrusion into the tank; (3) reduce contaminant mobility by (a) limiting the hydraulic conductivity of the closed tank and (b) reducing contact between the residual waste and infiltrating water; and (4) providing an alkaline, chemically reducing… more
Date: November 1, 2011
Creator: Stefanko, D. & Langton, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SALTSTONE VAULT CLASSIFICATION SAMPLES MODULAR CAUSTIC SIDE SOLVENT EXTRACTION UNIT/ACTINIDE REMOVAL PROCESS WASTE STREAM APRIL 2011

Description: Savannah River National Laboratory (SRNL) was asked to prepare saltstone from samples of Tank 50H obtained by SRNL on April 5, 2011 (Tank 50H sampling occurred on April 4, 2011) during 2QCY11 to determine the non-hazardous nature of the grout and for additional vault classification analyses. The samples were cured and shipped to Babcock & Wilcox Technical Services Group-Radioisotope and Analytical Chemistry Laboratory (B&W TSG-RACL) to perform the Toxic Characteristic Leaching Procedure (TC… more
Date: September 28, 2011
Creator: Eibling, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radionuclide Retention in Concrete Waste Forms

Description: Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how waste form performance is affected by the full range of environmental conditions within the disposal facility; the process of waste form aging under conditions that are representative of proc… more
Date: September 30, 2010
Creator: Mattigod, Shas V.; Bovaird, Chase C.; Wellman, Dawn M. & Wood, Marcus I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Diffusion and Leaching Behavior of Radionuclides in Category 3 Waste Encasement Concrete and Soil Fill Material – Summary Report

Description: One of the methods being considered for safely disposing of Category 3 low-level radioactive wastes is to encase the waste in concrete. Such concrete encasement would contain and isolate the waste packages from the hydrologic environment and would act as an intrusion barrier. The current plan for waste isolation consists of stacking low-level waste packages on a trench floor, surrounding the stacks with reinforced steel, and encasing these packages in concrete. These concrete-encased waste stac… more
Date: August 31, 2011
Creator: Mattigod, Shas V.; Wellman, Dawn M.; Bovaird, Chase C.; Parker, Kent E.; Clayton, Libby N.; Powers, Laura et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CEMENTITIOUS GROUT FOR CLOSING SRS HIGH LEVEL WASTE TANKS - #12315

Description: In 1997, the first two United States Department of Energy (US DOE) high level waste tanks (Tanks 17-F and 20-F: Type IV, single shell tanks) were taken out of service (permanently closed) at the Savannah River Site (SRS). In 2012, the DOE plans to remove from service two additional Savannah River Site (SRS) Type IV high-level waste tanks, Tanks 18-F and 19-F. These tanks were constructed in the late 1950's and received low-heat waste and do not contain cooling coils. Operational closure of Tank… more
Date: January 10, 2012
Creator: Langton, C.; Burns, H. & Stefanko, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TANK 18-F AND 19-F TANK FILL GROUT SCALE UP TEST SUMMARY

Description: High-level waste (HLW) tanks 18-F and 19-F have been isolated from FTF facilities. To complete operational closure the tanks will be filled with grout for the purpose of: (1) physically stabilizing the tanks, (2) limiting/eliminating vertical pathways to residual waste, (3) entombing waste removal equipment, (4) discouraging future intrusion, and (5) providing an alkaline, chemical reducing environment within the closure boundary to control speciation and solubility of select radionuclides. Thi… more
Date: January 3, 2012
Creator: Stefanko, D. & Langton, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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IMPACT OF THE SMALL COLUMN ION EXCHANGE PROCESS ON THE DEFENSE WASTE PROCESSING FACILITY - 12112

Description: The Savannah River Site (SRS) is investigating the deployment of a parallel technology to the Salt Waste Processing Facility (SWPF, presently under construction) to accelerate high activity salt waste processing. The proposed technology combines large waste tank strikes of monosodium titanate (MST) to sorb strontium and actinides with two ion exchange columns packed with crystalline silicotitanate (CST) resin to sorb cesium. The new process was designated Small Column Ion Exchange (SCIX), since… more
Date: November 7, 2011
Creator: Koopman, D.; Lambert, D.; Fox, K. & Stone, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

VARIABILITY OF KD VALUES IN CEMENTITIOUS MATERIALS AND SEDIMENTS

Description: Measured distribution coefficients (K{sub d} values) for environmental contaminants provide input data for performance assessments (PA) that evaluate physical and chemical phenomena for release of radionuclides from wasteforms, degradation of engineered components and subsequent transport of radionuclides through environmental media. Research efforts at SRNL to study the effects of formulation and curing variability on the physiochemical properties of the saltstone wasteform produced at the Sal… more
Date: February 2, 2012
Creator: Almond, P.; Kaplan, D. & Shine, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

OPERATIONS REVIEW OF THE SAVANNAH RIVER SITE INTEGRATED SALT DISPOSITION PROCESS - 11327

Description: The Savannah River Site (SRS) is removing liquid radioactive waste from its Tank Farm. To treat waste streams that are low in Cs-137, Sr-90, and actinides, SRS developed the Actinide Removal Process and implemented the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). The Actinide Removal Process contacts salt solution with monosodium titanate to sorb strontium and select actinides. After monosodium titanate contact, the resulting slurry is filtered to remove the monosodium titanate (a… more
Date: February 7, 2011
Creator: Peters, T.; Poirier, M.; Fondeur, F.; Fink, S.; Brown, S. & Geeting, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

MAGNESIUM MONO POTASSIUM PHOSPHATE GROUT FOR P-REACTOR VESSEL IN-SITU DECOMISSIONING

Description: The objective of this report is to document laboratory testing of magnesium mono potassium phosphate grouts for P-Reactor vessel in-situ decommissioning. Magnesium mono potassium phosphate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout (pH of about 12.4). A less alkaline material ({<=} 10.5) was desired to address a potential materials compatibility issue c… more
Date: January 5, 2011
Creator: Langton, C. & Stefanko, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MODELING ANALYSIS FOR GROUT HOPPER WASTE TANK

Description: The Saltstone facility at Savannah River Site (SRS) has a grout hopper tank to provide agitator stirring of the Saltstone feed materials. The tank has about 300 gallon capacity to provide a larger working volume for the grout nuclear waste slurry to be held in case of a process upset, and it is equipped with a mechanical agitator, which is intended to keep the grout in motion and agitated so that it won't start to set up. The primary objective of the work was to evaluate the flow performance fo… more
Date: January 4, 2012
Creator: Lee, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Radionuclide Retention in Concrete Wasteforms

Description: Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of proces… more
Date: September 30, 2011
Creator: Bovaird, Chase C.; Jansik, Danielle P.; Wellman, Dawn M. & Wood, Marcus I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EVOLUTION OF CHEMICAL CONDITIONS AND ESTIMATED PLUTONIUM SOLUBILITY IN THE RESIDUAL WASTE LAYER DURING POST-CLOSURE AGING OF TANK 18

Description: This document updates the Eh-pH transitions from grout aging simulations and the plutonium waste release model of Denham (2007, Rev. 1) based on new data. New thermodynamic data for cementitious minerals are used for the grout simulations. Newer thermodynamic data, recommended by plutonium experts (Plutonium Solubility Peer Review Report, LA-UR-12-00079), are used to estimate solubilities of plutonium at various pore water compositions expected during grout aging. In addition, a new grout formu… more
Date: February 29, 2012
Creator: Denham, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OPERATIONAL AND COMPOSITIONAL FACTORS THAT AFFECT THE PERFORMANCE PROPERTIES OF ARP/MCU SALTSTONE GROUT

Description: The Saltstone Production Facility (SPF) receives low level waste (LLW) salt solution from Tank 50H for treatment and disposal. Tank 50H receives transfers from the Effluent Treatment Project (ETP), the H-Canyon General Purpose Evaporator, and the Actinide Removal Process/Modular Caustic Side Solvent Extraction Unit (ARP/MCU) Decontaminated Salt Solution Hold Tank (DSS-HT). At the SPF, the LLW is mixed with premix (a cementitious mixture of portland cement (PC), blast furnace slag (BFS) and Clas… more
Date: February 15, 2012
Creator: Reigel, M.; Edwards, T. & Pickenheim, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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USE OF CEMENTITIOUS MATERIALS FOR SRS REACTOR FACILITY IN-SITU DECOMMISSIONING - 11620

Description: The United States Department of Energy (US DOE) concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., producing (reactor facilities), processing (isotope separation facilities) or storing radioactive materials. The Savannah River Site 105-P and 105-R Reactor Facility ISD requires about 250,000 cubic yards of grout to fill the below grade structure. The fills … more
Date: December 7, 2010
Creator: Langton, C.; Stefanko, D.; Serrato, M.; Blankenship, J.; Griffin, W.; Waymer, J. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Technical Insights for Saltstone PA Maintenance

Description: The Cementitious Barriers Partnership (CBP) is a collaborative program sponsored by the US DOE Office of Waste Processing. The objective of the CBP is to develop a set of computational tools to improve understanding and prediction of the long-term structural, hydraulic, and chemical performance of cementitious barriers and waste forms used in nuclear applications. CBP tools are expected to better characterize and reduce the uncertainties of current methodologies for assessing cementitious barri… more
Date: July 20, 2011
Creator: Flach, G.; Sarkar, S.; Mahadevan, S. & Kosson, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SALTSTONE 3QCY11 TCLP RESULTS

Description: A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the third quarter of calendar year 2011 (3QCY11). After the prescribed 32 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 hazardou… more
Date: January 12, 2012
Creator: Bannochie, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Performance Properties of Saltstone Produced Using SWPF Stimulants

Description: The overwhelming majority of waste to be immobilized at the Saltstone Production Facility will come from the waste stream exiting the Salt Waste Processing Facility (SWPF). These SWPF batches are salt solutions that result from pretreatment of the High Level Waste (HLW) supernate by an Actinide Removal Process followed by Caustic Side Solvent Extraction. The concentration of aluminate within these streams will vary and be determined by (1) the concentration in the incoming salt waste stream, (2… more
Date: February 16, 2010
Creator: Harbour, J. & Edwards, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SALTSTONE 3QCY09 TCLP RESULTS

Description: A Saltstone waste form was prepared in the Savannah River National Laboratory (SRNL) from a Tank 50H sample and Z-Area premix material for the third quarter of calendar year 2009 (3QCY09). 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 hazardou… more
Date: January 13, 2010
Creator: Reigel, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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