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At least 793 records · Page 44

Extraction, Scrub, and Strip Test Results for the Second Solvent Lot Qualification Sample for the Salt Waste Processing Facility

An Extraction, Scrub, and Strip (ESS) test was performed on the qualification sample from the second lot of Caustic-Side Solvent Extraction (CSSX) solvent for the Salt Waste Processing Facility (SWPF). Testing used simulated salt solution to determine cesium distribution ratios (D( Cs )), and cesium concentration in the strip effluent (SE) and decontaminated salt solution (DSS) streams. This data will be used by Parsons to help determine if the solvent is qualified for use at the SWPF. The ESS test showed acceptable performance of the solvent for extraction, scrub, and strip operations. The extraction D( Cs ) measured 14.4, exceeding the required value of 8. This value is consistent with results from previous ESS tests using similar solvent formulations. Similarly, scrub and strip cesium distribution ratios fell within acceptable ranges.

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Performance of Silver-Exchanged Mordenite and Silver-Functionalized Silica-Aerogel Under Vessel Off-gas Conditions

US regulations 40 CFR 61, 40 CFR 190, and 10 CFR 20 govern release limits for volatile radionuclides contained in the gaseous effluents of used nuclear fuel (UNF) reprocessing facilities. Of the four volatile radionuclides that are restricted by the release limits ( 3 H, 14 C, 85 Kr, and 129 I) 129 I will require the greatest degree of abatement. Previous studies have shown that overall plant decontamination factor (DF) for 129 I must, at minimum, exceed 1,000 to meet regulatory requirements. Iodine-containing off-gas will be present in the dissolver off-gas, the cell off-gas, the vessel off-gas (VOG), the waste off-gas, and the shear off-gas. The VOG will most likely contain 1%–5% of the total iodine at part per billion (ppb) concentrations. A number of studies have examined iodine abatement from the dissolver off-gas, which contains greater than 95% of the iodine inventory of the plant, but very few have examined the recovery of iodine from the VOG stream. Reduced silver-exchanged mordenite (Ag 0 Z) has been considered a promising iodine sorbent for use in UNF reprocessing plants, but recent efforts have identified silver-functionalized silica-aerogel (AgAerogel) as a potential alternative. The testing reported here reflects a substantial increase in the body of work available on iodine adsorption by both silver sorbents under prototypical VOG conditions. Both I2 and methyl iodide (CH 3 I) adsorption tests have been conducted with Ag 0 Z and AgAerogel at a range of concentrations up to 1,000 ppb. These experiments were performed with two specific aims: (1) to assess the effect of iodine concentration on its adsorption by the sorbent and (2) to compare the performance of Ag 0 Z and AgAerogel in the removal of iodine from a prototypical VOG stream.

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Evaluation of Tritium Management Approaches on Tritium Waste Volumes in Reprocessing Plants

Four radionuclides have been identified as likely to be volatilized during the reprocessing of nuclear fuel in amounts such that their gaseous release needs to be controlled to meet US regulatory requirements. These radionuclides are 3 H, 14 C, 85 Kr, and 129 I. While iodine has been the focus of a number of studies due to the high decontamination factor (DF) requirements on multiple off-gas pathways, it is also clear that the control of tritium could also be a significant issue for future reprocessing plants, especially if processing relatively short-cooled fuels (e.g., <10-yr post reactor discharge). Like iodine, tritium contained in a used nuclear fuel (UNF) matrix will be released into the liquid and off-gas streams during fuel reprocessing. The amount released into the process streams is a function of the type and burnup of the fuel processed, and the chemical processes and processing conditions employed within the reprocessing plant. The required DF for 3 H could be as high as 200, depending on the age of the fuel processed. This study examines three main cases with a number of subcases for comparative purposes.

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Analytical Results from final Salt Batch 9 Routine DSSHT and SEHT Monthly Samples

Strip Effluent Hold Tank (SEHT) and Decontaminated Salt Solution Hold Tank (DSSHT) samples from several of the “microbatches” of Integrated Salt Disposition Project (ISDP) Salt Batch (“Macrobatch”) 9 have been analyzed for 238 Pu, 90 Sr, 137 Cs, cations (Inductively Coupled Plasma Emission Spectroscopy - ICPES), and in some cases anions (Ion Chromatography Anions - IC-A). These three samples are from Salt Batch 9 material in the Modular Caustic-Side Solvent Extraction Unit (MCU) system, and prior to actual Salt Batch 10 processing. These samples are known to contain contactor cleaning material and should not be considered typical for samples under operating conditions. While the DSSHT sample is typical of this type of sample, the SEHT samples indicate a gross inclusion of nitric acid, likely from contactor cleaning solutions.

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Investigation of Polymetric Biofilms Formed by Dangerous Pathogens, and the Prevention of Their Formation by Disinfectants and Bacteriophages Final Report CRADA No. TC02145.0

This was a collaborative effort between Lawrence Livermore National Security, LLC as manager and operator of Lawrence Livermore National Laboratory (LLNL) and Intralytix Inc., to study biofilms formed on the surfaces of polymers by especially dangerous pathogens and nosocomial infections, to explore the possibility of decontamination of surfaces using different classes of disinfectants and specific bacteriophages.

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Cliff Retreat Characterization at Technical Area 54, Los Alamos National Laboratory, Los Alamos, NM

Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational waste is generated from a wide variety of Laboratory functions; environmental restoration and decontamination and decommissioned waste is generated as contaminated sites and facilities undergo cleanup or remediation. The majority of this waste is low-level radioactive waste and is disposed of at the Technical Area (TA) 54, Area G disposal facility. Area G includes Material Disposal Area (MDA) G, the portion of the facility that currently receives waste, and the Zone 4 expansion area located immediately west of MDAG. The Laboratory no longer plans to use the Zone 4 expansion area.

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Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility – Fiscal Years 2015-2017

The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D&D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA -54), Area G disposal facility.

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Stabilization of Spherical Rescorcinol Resin in Grout- Maintenance of the Hanford Integrated Disposal Performance Assessment FY 2018

Operation of the low activity waste vitrification facility (LAW) part of the Waste Treatment and Immobilization Plant (WTP) at Hanford will generate several solid secondary waste (SSW) streams including used process equipment, contaminated tools and instruments, decontamination wastes, highefficiency particulate air filters (HEPA), carbon absorption beds, silver mordenite iodine sorbent beds, and spent ion exchange resins (IXr), all of which are to be disposed of in the Integrated Disposal Facility (IDF). The baseline treatment method in the IDF Performance Assessment (PA) for SSW is solidification/stabilization using cementitious material. The Hanford Mix 5 has been identified as the baseline grout for encapsulation of debris SSW (HEPA filters) and solidification/stabilization of non-debris SSW (carbon absorption beds, silver mordenite iodine sorbent beds, and spent ion exchange resins). Hanford Mix 5 is a blend of ASTM (C150-18) Type I-II cement (OPC), Class F fly ash (FA), water, BASF Pozzolith 80 and BASF Master Fiber M100 (fiber) that is currently used for disposal of debris in carbon steel containers (B25) in Hanford’s 200 West Area Low Level Waste Burial Ground trenches.

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Bench Scale Study of Coating Formulations for Abatement of Mercury Vapor and Recovery of Mercury Spills

A sealant formulation has been developed that effectively mitigates human exposure to elemental mercury vapor evolving from spilled mercury. The sealant may be dispensed using a fogging methodology (for industrial settings) or a common spray bottle (for home or school settings). In parallel, the potential for Hg recovery using strippable coatings was evaluated. Four liquid coatings were evaluated: one fogging fixative (FX2) developed at INL for the containment of surface and airborne contamination and three commercially available strippable decontamination gels (Carboset 441, Encor 449, and Stripcoat TLC Free). Bench scale mercury vapor abatement tests were conducted in an enclosure using FX2 with the addition of a mercury absorbent and a mercury reactant. Testing with FX2 showed the reactant contributed significantly to reducing the rate of mercury evaporation. The reactant had a minimal impact on the mercury evaporation rate for the strippable coatings. The potential of strippable coatings to remove/recover mercury was inferred from the adhesive and cohesive performance of sprayable dilutions of the coatings applied to porous and non-porous surfaces. Testing provided the following results: • Mercury vapor concentration was reduced by a factor of 40 using the reactant enhanced FX2 solution, as well as with dilutions of Carboset and Encor. Dilute Stripcoat was less effective at reducing Hg evaporation. • A 100× reduction in Hg evaporation rate was achieved using a coating of FX + the Hg reactant (a.k.a. FX Hg), compared to uncoated Hg. • A 2× reduction in the Hg vapor accumulation rate was achieved using FX Hg, compared to the strippable coatings. • Strippability and adhesion tests show that dilutions of Carboset and Stripcoat can be stripped from a variety of indoor surfaces. Dilute Encor was not strippable. Results suggest FX Hg and dilute Carboset will likely reduce Hg vapor concentrations, in an indoor setting, to a level at or below the Occupational Safety and Health Administration 8-hour human exposure limit (0.1 mg/m3). FX Hg dispensed via fogging would increase worker safety during remediation and demolition of industrial facilities with high levels of elemental mercury contamination. When applied via spray bottle, FX Hg may provide a safe and convenient method for the mitigation of Hg vapor in residential or commercial settings (e.g., offices, homes, schools). This approach would be most beneficial where recovery of the spilled Hg is impractical. A sprayed then stripped application of dilute Carboset may provide a safe and convenient method for recovery of small Hg spills in residential and commercial settings. Further testing is required to determine if liquid Hg sufficiently adheres to the strippable coating to be recovered in this way. If it can be dispensed as a fog, dilute Carboset could be employed to recover Hg contamination in industrial settings. Testing of the foggability of dilute Carboset is required to assess this potential.

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Iodobutane Deep Bed Adsorption Test Report

The Department of Energy (DOE) Nuclear Technology Research and Development (NTRD) Program Material Recovery and Waste Form Development (MRWFD) Campaign Off-gas Sigma Team has supported research and development on iodine control and iodine waste forms for the past several years. As a part of this on-going research, two deep-bed iodobutane adsorption tests have been performed with higher NO x levels. High (>1,000) iodine decontamination factors (DFs, the ratios of the inlet iodine concentrations divided by the outlet iodine concentrations, when the gas flowrate is constant) were achieved with both the silver aerogel and silver zeolite sorbents. The iodine adsorption mass transfer zone (the depth of the sorbent bed in which adsorption is occurring at any specific time) for these tests was estimated at 4 inches for both sorbents under the test conditions. Silver utilization for silver aerogel sorbent reached 41% (up to 12 g adsorbed iodine per 100 g silver aerogel sorbent), while silver utilization reached 43% (up to 6.8 g adsorbed iodine per 100 g silver zeolite sorbent). These values are generally consistent with results for prior methyl iodide adsorption tests. The results also indicate that, during iodine adsorption process, the organic iodide molecule decomposes so that the iodine can be adsorbed. Even when sorbent breakthrough is reached, the organic iodide molecule continues to decompose; and the unadsorbed iodine that passes through bed is no longer in the form of the original organic iodide; but in the form of iodine compounds that are soluble in NaOH solutions, such as HI or I 2 . This research and development has included iodine adsorption tests using a laboratory-scale test system containing segmented fixed beds of iodine adsorbents in series. Non-radioactive synthetic gas mixtures were blended from air, nitrogen, NO, NO 2 , water, and the target iodine compounds to represent dissolver off-gas (DOG) streams from used nuclear fuel aqueous reprocessing.

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Development of an Active, Man-Portable, Cooling System with Dehumidification Capabilities for Personal Protective Clothing/Equipment

Mainstream Engineering Corporation completed a highly successful SBIR program, during which we developed and commercialized products for microclimate cooling systems (MCS) and the heating, ventilation, air-conditioning, and refrigeration (HVAC/R) industry. We are marketing the MCS family of products for use with personal protective clothing/equipment (PPC/PPE) for firefighters, workers in clean rooms, HAZMAT response and other contamination/remediation teams, and military personnel that are required to wear Mission-Oriented Protective Posture (MOPP) suits and bomb disposal suits. Workers in these industries risk heat stress when confined within protective garments while in hot and humid environments. Our family of MCS and HVAC/R products that resulted from this SBIR program includes: 1. Active, Man-Portable, MCS for PPC/E—Our active system provides 350 W cooling of personal cooling for workers in thermally stressed environments. Although industrially hardened, this system is compact (0.69 ft 3 ) and lightweight (22.9 lbs). The MSC is easily decontaminated or disposed of between uses. 2. Miniature Screw Compressor for MCS—Our 350 Wcooling miniature screw compressor was originally designed for MCS and personal cooling systems. Occupying only 11 in 3 and weighing 1.4 lbs, the size and weight are less than any commercially available compressor with a similar cooling capacity. This miniature screw compressor is marketable as a low-pressure compressor or refrigerant pump. 3. Miniature Sliding Vane Compressor and Drive for MCS—Our 350 Wcooling compressor subassembly consists of a commercial miniature sliding vane compressor packaged with our motor controller. At 29.4 in3 and 1.5 lbs, this compressor is larger and heavier than the miniature screw but is lower cost and capable of producing higher head pressure. 4. Small Screw Compressor for HVAC/R—Our 50 kW cooling small screw compressor is for commercial HVAC/R applications. This compressor is extremely power dense at 0.34 ft 3 and 43 lbs and has a specific cooling capacity (kW/lb) five times greater than existing commercial compressors. We demonstrated high reliability (>5,100 hrs of operation and >3,400 on/off cycles), and we are currently discussing commercialization opportunities with laser manufacturers for cooling of their high-power devices. This final report summarizes the design, fabrication, testing, features, and benefits of each product. The commercialization potential and recommendations for the future are included.

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Modeling Analysis of Actual and Potential Atmospheric Dispersion of Plutonium-239 from the Hanford Site Plutonium Finishing Plant

This report presents the results of two studies conducted to assess actual and potential plutonium-239 environmental contamination during demolition of the Plutonium Finishing Plant (PFP) at the Hanford Site near Richland, Washington. The assessments described herein were conducted by the National Atmospheric Release Advisory Center (NARAC) at Lawrence Livermore National Laboratory (LLNL). The overall objective of NARAC’s work is to help determine if contamination levels that warrant controls will extend beyond the established radiological control boundaries around the Hanford Site PFP in the course of further decontamination and demolition activities.

54 ENVIRONMENTAL SCIENCES↗

Analytical Results from Final Salt Batch 9 Routine DSSHT and SEHT Monthly Samples

Strip Effluent Hold Tank (SEHT) and Decontaminated Salt Solution Hold Tank (DSSHT) samples from several of the “microbatches” of Integrated Salt Disposition Project (ISDP) Salt Batch (“Macrobatch”) 9 have been analyzed for 238Pu, 90Sr, 137Cs, elemental constituents (Inductively Coupled Plasma Emission Spectroscopy - ICPES), and in some cases anions (Ion Chromatography Anions - IC-A).

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Mercury Remediation Technology Development for Lower East Fort Poplar Creek - FY2018 Update

Mercury (Hg) remediation is a high priority for the US Department of Energy (DOE) Oak Ridge Office of Environmental Management (OREM). Mercury contamination in the environment can be found at all three DOE facilities in Oak Ridge, but probably the greatest environmental risk concern relative to Hg on the Oak Ridge Reservation is associated with historical Hg losses at and near the Y-12 National Security Complex (Y-12). Water and fish from East Fork Poplar Creek (EFPC) downstream of Y-12 exceed regulatory thresholds. Because of the complexities of Hg transport and fate in the aquatic environment, conventional remedial options for EFPC are highly uncertain. DOE is using a phased, adaptive management approach to Hg remediation at Y-12, with a focus in the next few years on construction of the Mercury Treatment Facility (MTF) to treat the most contaminated Y-12 outfall entering EFPC (DOE 2017a; DOE 2017b). Once operational, the MTF will provide additional protection against inadvertent releases of Hg into the stream from decontamination and decommissioning of Y-12 Hg-use buildings. Although it is anticipated that the MTF will substantially decrease Hg water concentrations and flux in the upper part of EFPC, research and technology development is needed to develop appropriate and longer-term remedial solutions for the downstream environment. Since late 2014, OREM and UCOR/RSI (URS | CH2M Oak Ridge LLC/Restoration Services, Inc.) have supported Oak Ridge National Laboratory (ORNL) Environmental Sciences Division staff in conducting field and laboratory studies to develop Hg remedial technology solutions for lower EFPC (LEFPC). A technology development strategy for lower EFPC was developed in 2014 that was consistent with the adaptive management paradigm and DOE’s Technology Readiness Level (TRL) guidelines (Peterson et al. 2015). Initially, a thorough review of the literature and site-specific information was conducted to develop a broad number of potential technologies that might be applied in lower EFPC. An adaptive management approach was then used to focus on technologies that might have the most promise and potential remediation benefit. Field and laboratory studies conducted during 2014–2018 have (1) identified the major drivers of Hg flux and bioaccumulation in EFPC and (2) narrowed the list of highmerit technologies that might be of use in remediating the downstream environment.

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Testing of an Integrated Iodine Scrubber and Polishing Bed System

In 2016 an initial engineering evaluation and design of the off-gas abatement systems required for a hypothetical 1000 t/yr used nuclear fuel (UNF) reprocessing facility treating 5 yr–cooled, 60 GWd/tIHM UNF was completed. In this study two types of silver-based iodine sorbents were considered. The first was a silver-exchanged mordenite (AgZ), and the second was a silver-functionalized silica aerogel. In the initial design of the dissolver off-gas (DOG) iodine capture beds, the sorbent capacity was assumed to be 40 mg I/g sorbent. The total iodine released from the fuel, used as input for the design of the DOG system, was 1.635 kg/day. Tramp halogens increased this to ~5.1 kg/day on an iodine equivalent basis. The daily consumption of iodine sorbent was ~166 kg (including the mass transfer zones that have lower iodine loading). The iodine capture system was designed to utilize five beds in parallel. In this design each bed was ~1 m in diameter and 1.5 m long. This design allowed the beds to remain on line for 20 days, but at that point all five beds would need to be replaced, resulting in considerable material handling. It was proposed that the bed life could be extended and the number of parallel beds reduced if an aqueous iodine scrubber preceded the solid sorbent iodine capture beds. The testing described in this report was intended to provide an evaluation of an integrated system in which bulk iodine would first be removed by an aqueous NaOH scrubber with a target iodine decontamination factor (DF) of 10 to 50. This would reduce the sorbent usage by 90 to 95% and significantly reduce the associated frequent remote handling of the iodine filter beds. The effluent from the scrubber would then be passed through an AgZ sorbent bed to remove residual iodine. The integration of these unit operations was intended to demonstrate an iodine DF of >1000, which would facilitate regulatory compliance with regards to total volatile radionuclide emission from a reprocessing facility. Initial baseline performance testing of the scrubber system includes the characterization of CO 2 removal by the aqueous NaOH scrubber as a function of temperature, caustic concentration, packing length, liquid-to-gas mass ratio, and liquid flow rate. It was found that when the column was well wetted, very high CO 2 DFs were achieved (>650 and potentially as high as 15,000), preventing the ability to elucidate the effects of each specific variable tested. The L/G ratio in this system was not representative of typical L/G ratios found in industrial-scale scrubber systems. By significantly lowering the liquid recirculation rate to the point that column wetting was marginal, some significant variations in the CO 2 DF or CO 2 effluent concentrations could be observed. The additional tests conducted under these more adverse conditions still showed CO 2 DFs >100. The only operational parameter with significant effects was determined to be column length, with increased column length resulting in higher CO 2 DFs. Following these CO 2 tests, a single iodine scrubber test was performed deliberately at a condition indicated by the CO 2 demonstration to result in poor column performance. This was intended to establish a lower performance bound for iodine removal by the aqueous scrubber. The result showed that even under the adverse operating conditions, an iodine DF of >100 could be achieved. Finally, the aqueous scrubber and a AgZ polishing bed were integrated. This simple caustic scrubber system achieved an iodine DF of >12,000 for just the scrubber portion. Using this iodine DF, the iodine loading on the polishing bed was reduced by 99.993%. The performance of that integrated system was compared to a system including only a AgZ sorbent bed. The system without the scrubber also showed iodine DFs >3000 until breakthrough was observed. The loading on the saturated portion of the bed averaged 87.2 mg I 2 /gm AgZ. Comparing the penetration of iodine into the sorbent beds for these two systems showed a marked difference; the penetration with the scrubber was only 0.65 cm at a maximum loading of 0.11 mg I 2 /gm AgZ, whereas for the case without the caustic scrubber, the bed was saturated for the first 7 cm and breakthrough of the 13.3 cm bed occurred.

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Analytical Results from the Salt Batch 10 Routine DSSHT and SEHT Monthly Samples

Strip Effluent Hold Tank (SEHT) and Decontaminated Salt Solution Hold Tank (DSSHT) samples from several of the “microbatches” of Integrated Salt Disposition Project (ISDP) Salt Batch (“Macrobatch”) 10 have been analyzed for 238Pu, 90Sr, 137Cs, elemental constituents (Inductively Coupled Plasma Emission Spectroscopy - ICPES), and in some cases anions (Ion Chromatography Anions - IC-A). The included tables contain the data. These samples are from Salt Batch 10 material recently introduced into the Modular Caustic-Side Solvent Extraction Unit (MCU) system. The DSSHT results are typical for this type of sample, although the dilution due to processing is lower than expected. The August sample is known to have incorporated large amounts of rain water and cannot be compared to other DSSHT samples. The SEHT sample results are typical except for the May sample which is known to have rain water and Contactor Drain Tank (CDT) material in it.

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Special Analysis: 2016-002, Analysis of Cover Erosion and Enhanced Infiltration at Pit 25, TA-54 Area G

The Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Operational waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration, and decontamination and decommissioning (D&D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities.

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Central Characterization Program Acceptable Knowledge Summary Report for Sandia National Laboratories/New Mexico Remote Handled Hot Cell Facility and Other Research Transuranic Waste (Debris)

This acceptable knowledge(AK)Summary Report has been prepared for the Central Characterization Program (CCP) for remote-handled (RH) transuranic (TRU) waste generated and managed by Sandia National Laboratories/New Mexico (SNL/NM) in Albuquerque, New Mexico. The waste described in this report was predominately generated in the SNL/NM Hot Cell Facility (HCF) during the removal and packaging of experimental material and decontamination operations in Building 6580 at Technical Area (TA)-V.

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