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Radioactive Demonstration Of Mineralized Waste Forms Made From Hanford Low Activity Waste (Tank SX-105, Tank AN-103, And AZ-101/102) By Fluidized Bed Steam Reformation (FBSR)

Description: Fluidized Bed Steam Reforming (FBSR) is a robust technology for the immobilization of a wide variety of radioactive wastes. Applications have been tested at the pilot scale for the high sodium, sulfate, halide, organic and nitrate wastes at the Hanford site, the Idaho National Laboratory (INL), and the Savannah River Site (SRS). Due to the moderate processing temperatures, halides, sulfates, and technetium are retained in mineral phases of the feldspathoid family (nepheline, sodalite, nosean, c… more
Date: September 18, 2013
Creator: Jantzen, Carol M.; Crawford, C. L.; Bannochie, C. J.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radioactive Demonstration Of Mineralized Waste Forms Made From Hanford Low Activity Waste (Tank Farm Blend) By Fluidized Bed Steam Reformation (FBSR)

Description: The U.S. Department of Energy’s Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford’s tank waste. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of… more
Date: August 21, 2013
Creator: Jantzen, Carol M.; Crawford, C. L.; Bannochie, C. J.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Results Of Copper Catalyzed Peroxide Oxidation (CCPO) Of Tank 48H Simulants

Description: Savannah River National Laboratory (SRNL) performed a series of laboratory-scale experiments that examined copper-catalyzed hydrogen peroxide (H{sub 2}O{sub 2}) aided destruction of organic components, most notably tetraphenylborate (TPB), in Tank 48H simulant slurries. The experiments were designed with an expectation of conducting the process within existing vessels of Building 241-96H with minimal modifications to the existing equipment. Results of the experiments indicate that TPB destructi… more
Date: December 13, 2012
Creator: Peters, T. B.; Pareizs, J. M.; Newell, J. D.; Fondeur, F. F.; Nash, C. A.; White, T. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radioactive Demonstrations Of Fluidized Bed Steam Reforming (FBSR) With Hanford Low Activity Wastes

Description: Several supplemental technologies for treating and immobilizing Hanford low activity waste (LAW) are being evaluated. One immobilization technology being considered is Fluidized Bed Steam Reforming (FBSR) which offers a low temperature (700-750?C) continuous method by which wastes high in organics, nitrates, sulfates/sulfides, or other aqueous components may be processed into a crystalline ceramic (mineral) waste form. The granular waste form produced by co-processing the waste with kaolin clay… more
Date: October 22, 2012
Creator: Jantzen, Carol M.; Crawford, C. L.; Burket, P. R.; Bannochie, C. J.; Daniel, W. G.; Nash, C. A. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Modeling Ion-Exchange Processing With Spherical Resins For Cesium Removal

Description: The spherical Resorcinol-Formaldehyde and hypothetical spherical SuperLig(r) 644 ion-exchange resins are evaluated for cesium removal from radioactive waste solutions. Modeling results show that spherical SuperLig(r) 644 reduces column cycling by 50% for high-potassium solutions. Spherical Resorcinol Formaldehyde performs equally well for the lowest-potassium wastes. Less cycling reduces nitric acid usage during resin elution and sodium addition during resin regeneration, therefore, significant… more
Date: September 19, 2012
Creator: Hang, T.; Nash, C. A. & Aleman, S. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radioactive Demonstrations of Fluidized Bed Steam Reforming With Acutal Hanford Low Activity Wastes Verifying Fbsr as a Supplementary Treatment

Description: The U.S. Department of Energy's Office of River Protection is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level waste (HLW) and low-activity waste (LAW… more
Date: January 12, 2012
Creator: Jantzen, Carol M.; Crawford, C. L.; Burket, P. R.; Bannochie, C. J.; Daniel, W. G.; Nash, C. A. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Entrainment of Solvent in Aqueous Stream from CINC V-5 Contactor

Description: Personnel completed a rapid study of organic entrainment during operation of a CINC V-5 contactor under prototypical conditions covering the range of expected MCU operation. The study only considered the entrainment of organic into the strip acid effluent destined for the Defense Waste Processing Facility. Based on this work, the following observations are noted: (1) Concentrations of total organic from the contactor discharge, based upon modifier measurements, in the acid typically averaged 33… more
Date: April 29, 2005
Creator: Fink, S. D.; Restivo, M. L.; Peters, T. B.; Fowley, M. D.; Burns, D. B.; Smith, W. M. Jr. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluating Residence Time for SuperLig(R) 644 Columns with Simulated LAW Envelope C (AN-107) Solution

Description: A series of batch contact and column tests were conducted with new and aged Envelope C (AN-107) simulant using SuperLig{reg_sign} 644 resin. In addition to the batch contact tests, four column loading and elution tests were performed with aged Envelope C (AN-107) simulant to evaluate the effects of volumetric flow rate on cesium sorption. A single-column (2.7 cm i.d.) containing {approx} 100 mL of SuperLig 644{reg_sign} resin was used. The column test results show more than 100 BVs of simulated… more
Date: August 20, 2003
Creator: Nash, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Resin Particle Size and Solution Temperature on SuperLig(R) 644 Resin Performance with AN-105 Simulate

Description: The performance of the SuperLig(R) 644 resin loading and elution was evaluated at 25, 35, and 45 degree C using a single-column containing 2.25 g of oven-dry, hydrogen form of SuperLig(R) 664 resin. A simulated Envelope A solution was used to mimic the composition of low-activity waste solution from Tank 241-AN-105 supernate in the Hanford Site waste tank. The simulant was spiked with small quantities of trace metals (cadmium, chromium, iron, and lead) to evaluate the effects of these metals on… more
Date: July 15, 2003
Creator: Nash, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluating Residence Time for SuperLig(R) 644 Columns with Simulated LAW Envelope B Solution

Description: The Hanford River Protection Project Waste Treatment Plant (RPP-WTP) will be performing cesium and technetium ion exchange using SuperLig 644 and 639, respectively. Earlier work with LAW Envelope A (AN-105) simulant indicated that cesium adsorption by SuperLig 644 and perrhenate (pertechnetate analog) adsorption by SuperLig 639 are dependent on liquid volumetric flow rate during column loading. Acceptable lead column operation for both resins was attained (50 percent breakthrough at 100 column … more
Date: July 15, 2003
Creator: Nash, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SuperLig(TM) 644 Ion Exchange Resin Stability in Nitric Acid at Elevated Temperatures

Description: In the Hanford River Protection Project Waste Treatment Plan (RPP-WTP) flowsheet, opportunity exists for the organic SuperLig 644(TM) cation exchange resin to come in contact with concentrated (5 M) nitric acid at elevated temperatures in the acid recovery evaporator. These are similar conditions where other ion exchange resin (albeit usually anion) column explosions have occurred. The objective of these tests was to examine potential hazards by exposing the resin to conditions expected in the … more
Date: January 6, 2003
Creator: Nash, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Strontium-Transuranic Precipitation and Crossflow Filtration of 241-AN-102 Large C

Description: This work provides an important confirmation of the new strontium/permanganate precipitation process to achieve both acceptable filterability and decontamination for Envelope C (Tanks 241-AN-102 and 241-AN-107) wastes to be treated by the Hanford River Protection Project. As a bench-scale demonstration, a series of seven precipitation batches and crossflow filtration campaigns were performed to remove strontium-90 and transuranics from 16.5 liters of Tank 241-AN-102 ''Large C'' supernatant liqu… more
Date: May 21, 2001
Creator: Nash, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization of a Washed 241-C-106 Sludge Sample

Description: An Envelope D Tank 241-C-106 sample was characterized for solids, elemental, and radioactive isotope content. The work was done by the Savannah River Technology Center (SRTC) to support the Hanford River Protection Project (RPP). The sludge from Hanford Tank 241-C-106 is high level waste that is to be included in the first ten years of processing by the RPP Waste Treatment Plant (WTP). The sample was a composite of caustic-leached and washed sludge from previous work at the Pacific Northwest Na… more
Date: May 15, 2001
Creator: Nash, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Task and Quality Assurance Plan in Support of BNFL Part B: Studies of Ion Exchange Resin Integrity under Flowsheet Extremes: Part II

Description: This task will address four items related to ion exchange stability: (1) process upset evaluation of resin in contact with 1 molar sodium permanganate at 25 and 40 degrees C, (2) accelerated aging with nitric acid solution used during normal regeneration operations, (3) prolonged contacting of SuperLig 644 resin with 5 molar nitric acid at room temperature, and (4) prolonged contacting of SuperLig 644 resin with deionized water at 60 plus/minus 5 degrees C.
Date: August 23, 2000
Creator: Nash, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of Varied Strontium-Transuranic Precipitation Chemistries for Crossflow

Description: Precipitation chemistries for strontium and transuranic (TRU) removal have been tested for crossflow filterability and lanthanide removal with simulants of Hanford tank 241-AN-107 supernate. This is the initial work indicating the usefulness of a strontium and permanganate precipitation process as applied to the Hanford River Protection Project. Precipitations with both ferric and ferrous iron were shown to be at least two orders of magnitude less filterable than a 0.1 gpm/ft target average flu… more
Date: July 27, 2000
Creator: Nash, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Precipitation Results for AN-102: A Statistically Designed Approach to Evaluate Filterability and Sr/TRU Decontamination

Description: The work reported in this document is a series of statistically designed tests to examine the relationship between the four responses of interest and five precipitation parameters affiliated with the new precipitation scheme. The four responses are precipitate filterability, strontium decontamination, americium decontamination, and plutonium decontamination. The precipitation parameters were the initial sodium concentration of the waste, the initial hydroxide level of the waste, and the amounts… more
Date: January 4, 2000
Creator: Rosencrance, S. W.; Dewberry, R. A.; DiPrete, D. P.; Edwards, T. B.; Emory, S. J.; Nash, C. A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reverse flow through a large scale multichannel nozzle

Description: A database was developed for the flow of water through a scaled nozzle of a Savannah River Site reactor inlet plenum. The water flow in the nozzle was such that it ranged from stratified to water solid conditions. Data on the entry of air into the nozzle and plenum as a function of water flow are of interest in loss-of-coolant studies. The scaled nozzle was 44 cm long, had an entrance diameter of 95 mm, an exit opening of 58 mm {times} 356 mm, and an exit hydraulic diameter approximately equal … more
Date: December 31, 1992
Creator: Duignan, M. R. & Nash, C. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Late Wash Filter Demonstration Unit program plan

Description: This report details a planned a non-radioactive engineering demonstration of the DWPF Late Wash Facility (LWF) for washing salt precipitate feed, and of the In-Tank Precipitate (ITP) filters. The scale will be 0.05 to 0.1, with some larger components, prototypical instruments, and full-length filter elements. Precipitate slurry for late wash tests will be fully irradiated (3EO8 rads). Program needs and objectives are to demonstrate LWF design, optimize LWF process operations including filter cl… more
Date: November 10, 1992
Creator: Nash, C. A.; Budenstein, S. A. & Boersma, M. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Late Wash Filter Demonstration Unit program plan

Description: This report details a planned a non-radioactive engineering demonstration of the DWPF Late Wash Facility (LWF) for washing salt precipitate feed, and of the In-Tank Precipitate (ITP) filters. The scale will be 0.05 to 0.1, with some larger components, prototypical instruments, and full-length filter elements. Precipitate slurry for late wash tests will be fully irradiated (3EO8 rads). Program needs and objectives are to demonstrate LWF design, optimize LWF process operations including filter cl… more
Date: November 10, 1992
Creator: Nash, C. A.; Budenstein, S. A. & Boersma, M. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final report for the flow excursion follow-on testing

Description: The purpose of the Mark 22 Flow Excursion Follow-On testing was to investigate the theory that approximately 15% of the flow bypassed the primary flow channels in previous testing, whereas the design called for only a 3% bypass. The results of the follow-on tests clearly confirmed this theory. The testing was performed in two phases. During the first phase, characterization tests performed during the earlier test program were repeated.
Date: August 5, 1992
Creator: Nash, C. A. & Walters, T. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final report for the flow excursion follow-on testing

Description: The purpose of the Mark 22 Flow Excursion Follow-On testing was to investigate the theory that approximately 15% of the flow bypassed the primary flow channels in previous testing, whereas the design called for only a 3% bypass. The results of the follow-on tests clearly confirmed this theory. The testing was performed in two phases. During the first phase, characterization tests performed during the earlier test program were repeated.
Date: August 5, 1992
Creator: Nash, C. A. & Walters, T. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reverse flow through a large scale multichannel nozzle

Description: A database was developed for the flow of water through a scaled nozzle of a Savannah River Site reactor inlet plenum. The water flow in the nozzle was such that it ranged from stratified to water solid conditions. Data on the entry of air into the nozzle and plenum as a function of water flow are of interest in loss-of-coolant studies. The scaled nozzle was 44 cm long, had an entrance diameter of 95 mm, an exit opening of 58 mm [times] 356 mm, and an exit hydraulic diameter approximately equal … more
Date: January 1, 1992
Creator: Duignan, M.R. & Nash, C.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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