Feasibility study of tank leakage mitigation using subsurface barriers. Revision 1

International Nuclear Information System (INIS)

Treat, R.L.; Peters, B.B.; Cameron, R.J.

1995-01-01

This document reflects the evaluations and analyses performed in response to Tri-Party Agreement Milestone M-45-07A - open-quotes Complete Evaluation of Subsurface Barrier Feasibilityclose quotes (September 1994). In addition, this feasibility study was revised reflecting ongoing work supporting a pending decision by the DOE Richland Operations Office, the Washington State Department of Ecology, and the US Environmental Protection Agency regarding further development of subsurface barrier options for SSTs and whether to proceed with demonstration plans at the Hanford Site (Tri-Party Agreement Milestone M-45-07B). Analyses of 14 integrated SST tank farm remediation alternatives were conducted in response to the three stated objectives of Tri-Party Agreement Milestone M-45-07A. The alternatives include eight with subsurface barriers and six without. Technologies used in the alternatives include three types of tank waste retrieval, seven types of subsurface barriers, a method of stabilizing the void space of emptied tanks, two types of in situ soil flushing, one type of surface barrier, and a clean-closure method. A no-action alternative and a surface-barrier-only alternative were included as nonviable alternatives for comparison. All other alternatives were designed to result in closure of SST tank farms as landfills or in clean-closure. Revision 1 incorporates additional analyses of worker safety, large leak scenarios, and sensitivity to the leach rates of risk controlling constituents. The additional analyses were conducted to support TPA Milestone M-45-07B

Biodegradation of international jet A-1 aviation fuel by microorganisms isolated from aircraft tank and joint hydrant storage systems.

Science.gov (United States)

Itah, A Y; Brooks, A A; Ogar, B O; Okure, A B

2009-09-01

Microorganisms contaminating international Jet A-1 aircraft fuel and fuel preserved in Joint Hydrant Storage Tank (JHST) were isolated, characterized and identified. The isolates were Bacillus subtillis, Bacillus megaterium, Flavobacterium oderatum, Sarcina flava, Micrococcus varians, Pseudomonas aeruginosa, Bacillus licheniformis, Bacillus cereus and Bacillus brevis. Others included Candida tropicalis, Candida albicans, Saccharomyces estuari, Saccharomyces cerevisiae, Schizosaccharomyces pombe, Aspergillus flavus, Aspergillus niger, Aspergillus fumigatus, Cladosporium resinae, Penicillium citrinum and Penicillium frequentans. The viable plate count of microorganisms in the Aircraft Tank ranged from 1.3 (+/-0.01) x 104 cfu/mL to 2.2 (+/-1.6) x 104 cfu/mL for bacteria and 102 cfu/mL to 1.68 (+/-0.32) x 103 cfu/mL for fungi. Total bacterial counts of 1.79 (+/-0.2) x 104 cfu/mL to 2.58 (+/-0.04) x 104 cfu/mL and total fungal count of 2.1 (+/-0.1) x 103 cfu/mL to 2.28 (+/-0.5) x 103 cfu/mL were obtained for JHST. Selected isolates were re-inoculated into filter sterilized aircraft fuels and biodegradation studies carried out. After 14 days incubation, Cladosporium resinae exhibited the highest degradation rate with a percentage weight loss of 66 followed by Candida albicans (60.6) while Penicillium citrinum was the least degrader with a weight loss of 41.6%. The ability of the isolates to utilize the fuel as their sole source of carbon and energy was examined and found to vary in growth profile between the isolates. The results imply that aviation fuel could be biodegraded by hydrocarbonoclastic microorganisms. To avert a possible deterioration of fuel quality during storage, fuel pipe clogging and failure, engine component damage, wing tank corrosion and aircraft disaster, efficient routine monitoring of aircraft fuel systems is advocated.

Yield of abrams needle pleural biopsy in exudative pleural effusion

International Nuclear Information System (INIS)

Khan, I.N.; Zaman, M.; Khan, N.; Jadoon, H.; Ahmed, A.

2009-01-01

Pleural effusion is the abnormal collection of fluid in the pleural space resulting from excessive fluid production or decreased absorption and it is one of the most common clinical conditions that we come across in pulmonology clinics and in hospitals. The objective of prospective study was to evaluate the diagnostic role of Abrams Needle Biopsy in Exudative Pleural Effusion The study was performed at the Department of Pulmonology, Ayub Teaching Hospital, Abbottabad over a period of 1 year, i.e., January 2008 to December 2008. Sixty-three patients of either sex and all ages with exudative pleural effusion, on whom Abrams Needle Biopsy was performed were included in the study. Minimum of four specimens from each patient were taken and histopathology done. Out of 63 patients, histopathology revealed the cause in 60 (95%) cases. Tuberculosis, malignancy and rheumatoid pleurisy were confirmed in 34, 24, and 2 cases respectively. Specimens of 3 patients did not reveal any result and showed non-specific inflammation and were further investigated accordingly. The diagnostic yield of Biopsy was 95%. Pleural biopsy is still a reliable and valuable investigation in diagnosing pleural effusion, provided that adequate pleural specimen is taken. (author)

Tank waste remediation system fiscal year 1998 multi-year work plan WBS 1.1

Energy Technology Data Exchange (ETDEWEB)

Lenseigne, D. L.

1997-09-15

The TWRS Project Mission is to manage and immobilize for disposal the Hanford Site radioactive tank waste and cesium (Cs)/strontium (Sr) capsules in a safe, environmentally sound, and cost-effective manner. The scope includes all activities needed to (1) resolve safety issues; (2) operate, maintain, and upgrade the tank farms and supporting infrastructure; (3) characterize, retrieve, pretreat, and immobilize the waste for disposal and tank farm closure; and (4) use waste minimization and evaporation to manage tank waste volumes to ensure that the tank capacities of existing DSTs are not exceeded. The TWRS Project is responsible for closure of assigned operable units and D&D of TWRS facilities.

The M1 Abrams Today and Tomorrow

Science.gov (United States)

2014-11-01

counterinsurgency, but that, as noted in the new Army Capstone Concept, the Abram’s combination of high mobility and protect - ed firepower can at times prove...forced on Congress and the White House from the current massive federal deficits, will almost certainly foster an era of less for the Department of...Conroy, Heavy Metal, (Washington, DC: Potomac Books, 2005), 195-209. 19. Christopher F. Foss, Jane’s Armour and Artillery 2010- 2011 (Surrey, UK: HIS

THE 76-MM GUN M1A1 AND M1A2: AN ANALYSIS OF U.S. ANTI-TANK CAPABILITIES DURING WORLD WAR II

Science.gov (United States)

2018-01-01

ballistic analysis is used to corroborate the battlefield history and gain an understanding of the physical and technological factors that spurred the...capabilities against the German Panther tank. Battle history indicates there was a technological capability gap against upgraded Panzer armor. This report...Engineering Technology Center Picatinny Arsenal, New Jersey UNCLASSIFIED UNCLASSIFIED The views, opinions, and/or

Engineering Assessment and Certification of Integrity of the 490-Q1 tank system

Energy Technology Data Exchange (ETDEWEB)

Schwartz, W.W. [Lawrence Livermore National Lab., CA (United States); Gee, C.W.; Graser, D.A. [Science Applications International Corp., San Diego, CA (US)

1993-07-01

This Engineering Assessment and Certification of Integrity of used freon storage tanks 490-Q1A1 and 490-Q1A2 has been prepared in response to 40 CFR 265.192(a) and 22 CCR 66265.192(a) for new tank systems that store hazardous waste and have secondary containment. The regulations require that this assessment be completed and certified by an independent, qualified, California-registered professional engineer before the tank system is placed in use as a hazardous waste storage tank system. The technical assessments for the 490-Q1A1 and 490-Q1A2 tank systems have been reviewed by an independent, qualified, California-registered professional engineer, who has certified that the tank systems have sufficient structural integrity, are acceptable for transferring and storing hazardous waste, are compatible with the stored waste, and the tanks and containment system are suitably designed to achieve the requirements of the applicable regulations so they will not collapse, rupture, or fail.

Think tank (1) - Its definition and the overseas situation

Science.gov (United States)

Obara, Michio

The definition as organization is that 1) the think tank should be policy oriented and propose the current issues, 2) it should be interdisciplinary and future oriented, and 3) it should be independent without any outside interference upon it. It is divided into three types in terms of business activity; 1) policy proposing, 2) R&D undertaking and 3) business consulting think tanks. Historically the U.S. has been leading the world because the first think tank was born in this country, and three types of think tanks have brought out the mature business undertakings there. Most of the countries other than the U.S. has held policy proposing type think tanks. The notable think tanks are Brookings Research Institute, Rand Research Institute, Battelle Memorial Institute, Arthur D. Little Co. Ltd. SRI International in the U.S.A., IFO Economic Research Institute, German Economic Research Institute in Germany, France International Relations Research Institute in France, Royal International Relations Research institute, International Strategic Matters Research Institute in the U.K., and Korean Development Research Institute, Korean industrial Research Institute in Korea. All of these have been active in the areas of politics, economics, industry and technology.

1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation

Energy Technology Data Exchange (ETDEWEB)

Fort, J.A.; Bamberger, J.A.; Bates, J.M.; Enderlin, C.W.; Elmore, M.R.

1993-01-01

Hanford tank 241-SY-101 is a 75-ft-dia double-shell tank that contains approximately 1.1 M gal of radioactive fuel reprocessing waste. Core samples have shown that the tank contents are separated into two main layers, a article laden supernatant liquid at the top of the tank and a more dense slurry on the bottom. Two additional layers may be present, one being a potentially thick sludge lying beneath the slurry at the bottom of the tank and the other being the crust that has formed on the surface of the supernatant liquid. The supernatant is more commonly referred to as the convective layer and the slurry as the non-convective layer. Accumulation of gas (partly hydrogen) in the non-convective layer is suspected to be the key mechanism behind the gas burp phenomena, and several mitigation schemes are being developed to encourage a more uniform gas release rate (Benegas 1992). To support the full-scale hydraulic mitigation test, scaled experiments were performed to satisfy two objectives: 1. provide an experimental database for numerical- model validation; 2. establish operating parameter values required to mobilize the settled solids and maintain the solids in suspension.

TANK 18 AND 19-F TIER 1A EQUIPMENT FILL MOCK UP TEST SUMMARY

Energy Technology Data Exchange (ETDEWEB)

Stefanko, D.; Langton, C.

2011-11-04

The United States Department of Energy (US DOE) has determined that Tanks 18-F and 19-F have met the F-Tank Farm (FTF) General Closure Plan Requirements and are ready to be permanently closed. The high-level waste (HLW) tanks have been isolated from FTF facilities. To complete operational closure they will be filled with grout for the purpose of: (1) physically stabilizing the tanks, (2) limiting/eliminating vertical pathways to residual waste, (3) discouraging future intrusion, and (4) providing an alkaline, chemical reducing environment within the closure boundary to control speciation and solubility of select radionuclides. Bulk waste removal and heel removal equipment remain in Tanks 18-F and 19-F. This equipment includes the Advance Design Mixer Pump (ADMP), transfer pumps, transfer jets, standard slurry mixer pumps, equipment-support masts, sampling masts, dip tube assemblies and robotic crawlers. The present Tank 18 and 19-F closure strategy is to grout the equipment in place and eliminate vertical pathways by filling voids in the equipment to vertical fast pathways and water infiltration. The mock-up tests described in this report were intended to address placement issues identified for grouting the equipment that will be left in Tank 18-F and Tank 19-F. The Tank 18-F and 19-F closure strategy document states that one of the Performance Assessment (PA) requirements for a closed tank is that equipment remaining in the tank be filled to the extent practical and that vertical flow paths 1 inch and larger be grouted. The specific objectives of the Tier 1A equipment grout mock-up testing include: (1) Identifying the most limiting equipment configurations with respect to internal void space filling; (2) Specifying and constructing initial test geometries and forms that represent scaled boundary conditions; (3) Identifying a target grout rheology for evaluation in the scaled mock-up configurations; (4) Scaling-up production of a grout mix with the target rheology

Evaluation of 241-AZ tank farm supporting phase 1 privatization waste feed delivery

Energy Technology Data Exchange (ETDEWEB)

CARLSON, A.B.

1998-11-19

This evaluation is one in a series of evaluations determining the process needs and assessing the adequacy of existing and planned equipment in meeting those needs at various double-shell tank farms in support of Phase 1 privatization. A number of tank-to-tank transfers and waste preparation activities are needed to process and feed waste to the private contractor in support of Phase 1 privatization. The scope of this evaluation is limited to process needs associated with 241-AZ tank farm during the Phase 1 privatization.

Evaluation of 241-AZ tank farm supporting phase 1 privatization waste feed delivery

International Nuclear Information System (INIS)

CARLSON, A.B.

1998-01-01

This evaluation is one in a series of evaluations determining the process needs and assessing the adequacy of existing and planned equipment in meeting those needs at various double-shell tank farms in support of Phase 1 privatization. A number of tank-to-tank transfers and waste preparation activities are needed to process and feed waste to the private contractor in support of Phase 1 privatization. The scope of this evaluation is limited to process needs associated with 241-AZ tank farm during the Phase 1 privatization

General Creighton Abrams: Ethical Leadership at the Strategic Level

National Research Council Canada - National Science Library

Leatherman, John

1998-01-01

.... This study describes General Abrams' ethical strategic leadership style during his Army career and examines the extent that his ethical principles and examples affected his soldiers and the Army...

Tank characterization report for single-shell tank 241-C-110. Revision 1

International Nuclear Information System (INIS)

Benar, C.J.

1997-01-01

One of the major functions of the Tank Waste Remediation System (IWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-C-110. The objectives of this report are to use characterization data in response to technical issues associated with 241-C-110 waste and to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Supporting data and information are contained in the appendixes. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order milestone M-44-05. Characterization information presented in this report originated from sample analyses and known historical sources. While only the results from recent sample events will be used to fulfill the requirements of the data quality objectives (DQOs), other information can be used to support or question conclusions derived from these results. Historical information for tank 241-C-110 are provided included surveillance information, records pertaining to waste transfers and tank operations, and 1124 expected tank contents derived from a process knowledge model. The sampling events are listed, as well as sample data obtained before 1989. The results of the 1992 sampling events are also reported in the data package. The statistical analysis and numerical manipulation of data used in issue resolution are reported in Appendix C. Appendix D contains the evaluation to establish the best basis for the inventory estimate and the statistical analysis performed for this evaluation. A bibliography that resulted from an in-depth literature search of all known information sources applicable to tank 241-C-110 and its respective waste types is contained in Appendix E

Physicochemical characterization of Capstone depleted uranium aerosols I: uranium concentration in aerosols as a function of time and particle size.

Science.gov (United States)

Parkhurst, Mary Ann; Cheng, Yung Sung; Kenoyer, Judson L; Traub, Richard J

2009-03-01

During the Capstone Depleted Uranium (DU) Aerosol Study, aerosols containing DU were produced inside unventilated armored vehicles (i.e., Abrams tanks and Bradley Fighting Vehicles) by perforation with large-caliber DU penetrators. These aerosols were collected and characterized, and the data were subsequently used to assess human health risks to personnel exposed to DU aerosols. The DU content of each aerosol sample was first quantified by radioanalytical methods, and selected samples, primarily those from the cyclone separator grit chambers, were analyzed radiochemically. Deposition occurred inside the vehicles as particles settled on interior surfaces. Settling rates of uranium from the aerosols were evaluated using filter cassette samples that collected aerosol as total mass over eight sequential time intervals. A moving filter was used to collect aerosol samples over time, particularly within the first minute after a shot. The results demonstrate that the peak uranium concentration in the aerosol occurred in the first 10 s after perforation, and the concentration decreased in the Abrams tank shots to about 50% within 1 min and to less than 2% after 30 min. The initial and maximum uranium concentrations were lower in the Bradley vehicle than those observed in the Abrams tank, and the concentration levels decreased more slowly. Uranium mass concentrations in the aerosols as a function of particle size were evaluated using samples collected in a cyclone sampler, which collected aerosol continuously for 2 h after perforation. The percentages of uranium mass in the cyclone separator stages ranged from 38 to 72% for the Abrams tank with conventional armor. In most cases, it varied with particle size, typically with less uranium associated with the smaller particle sizes. Neither the Abrams tank with DU armor nor the Bradley vehicle results were specifically correlated with particle size and can best be represented by their average uranium mass concentrations of 65

Microscopic Abrams-Strogatz model of language competition

OpenAIRE

Stauffer, Dietrich; Castello, Xavier; Eguiluz, Victor M.; Miguel, Maxi San

2006-01-01

The differential equation of Abrams and Strogatz for the competition between two languages is compared with agent based Monte Carlo simulations for fully connected networks as well as for lattices in one, two and three dimensions, with up to 10^9 agents. In the case of socially equivalent languages, agent-based models and a mean field approximation give grossly different results.

Performance requirements for the double-shell tank system: Phase 1

International Nuclear Information System (INIS)

Claghorn, R.D.

1998-01-01

This document establishes performance requirements for the double-shell tank system. These requirements, in turn, will be incorporated in the System Specification for the Double-Shell Tank System (Grenard and Claghorn 1998). This version of the document establishes requirements that are applicable to the first phase (Phase 1) of the Tank Waste Remediation System (TWRS) mission described in the TWRS Mission Analysis Report (Acree 1998). It does not specify requirements for either the Phase 2 mission or the double-shell tank system closure period

Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1

International Nuclear Information System (INIS)

Groth, B.D.

1995-01-01

The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements

1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation. Final report

Energy Technology Data Exchange (ETDEWEB)

Fort, J.A.; Bamberger, J.A.; Bates, J.M.; Enderlin, C.W.; Elmore, M.R.

1993-01-01

Hanford tank 241-SY-101 is a 75-ft-dia double-shell tank that contains approximately 1.1 M gal of radioactive fuel reprocessing waste. Core samples have shown that the tank contents are separated into two main layers, a article laden supernatant liquid at the top of the tank and a more dense slurry on the bottom. Two additional layers may be present, one being a potentially thick sludge lying beneath the slurry at the bottom of the tank and the other being the crust that has formed on the surface of the supernatant liquid. The supernatant is more commonly referred to as the convective layer and the slurry as the non-convective layer. Accumulation of gas (partly hydrogen) in the non-convective layer is suspected to be the key mechanism behind the gas burp phenomena, and several mitigation schemes are being developed to encourage a more uniform gas release rate (Benegas 1992). To support the full-scale hydraulic mitigation test, scaled experiments were performed to satisfy two objectives: 1. provide an experimental database for numerical- model validation; 2. establish operating parameter values required to mobilize the settled solids and maintain the solids in suspension.

Development of an Item Unique Identification Strategy for the Legacy Components of the US Marine Corps M1A1 Abrams Tank

Science.gov (United States)

2008-12-01

Program FIS Forward in Stores FLIR Forward Looking Infrared FOC Full Operating Capability FTL Far Target Locater FY Fiscal Year GAAP Generally...Accounting Principles ( GAAP ) and accurately represents the financial position of the department or agency. In 2002, President George W. Bush...exceeds the DoD-capitalization threshold of $100,000 for both the General and Working Capital funds must be valued, depreciated , and reported as GPP&E

Estimated dose to in-tank equipment: Phase 1 waste feed delivery

International Nuclear Information System (INIS)

Claghorn, R.D.

1998-01-01

This analysis estimates the radiation dose to the equipment that will be submerged in double-shell tank waste. The results of this analysis are intended to be the basis for specifications for in-tank equipment. The scope of this analysis is limited to the new equipment required for the delivery of waste feed to Phase 1 private contractors. Phase 1 refers to the first of a two-phase plan to privatize the remediation of Hanford's tank waste. The focus of this analysis is on waste feed delivery because of the extraordinarily high cost of any failure that would lead to the interruption of a steady flow of feed to the private contractors

A retrospective evaluation of a Bovine Herpesvirus-1 (BHV-1) antibody ELISA on bulk-tank milk samples for classification of the BHV-1 status of Danish dairy herds

DEFF Research Database (Denmark)

Nylin, Britta; Strøger, Ulla; Rønsholt, Leif

2000-01-01

Bulk-tank milk samples analysed in a Bovine Herpesvirus-1 (BHV-1) blocking ELISA are still in use in the Danish BHV-1 programme as a tool to classify dairy herds as BHV-1 infected or BHV-1 free herds. in this retrospective study, we used data from the Danish BHV-1 eradication campaign to evaluate...

Limits on Annulus Air Outages in Types 1, 2, and 3 Waste Tanks

International Nuclear Information System (INIS)

Wiersma, B.J.; Sindelar, R. L.

1995-01-01

An evaluation was performed on the impact of abnormal air flow conditions on the structural integrity of Types 1, 2, and 3 waste tanks. Warm, dry air in the annular space is necessary to preclude low temperature embrittlement and corrosive conditions for the carbon steel materials. For Type 1 and 2 tanks the annulus air system should be repaired within a month to minimize the potential for low temperature embrittlement and corrosive conditions, for Tanks 29-34, which are Type 3 tanks, it is recommended that the system be repaired within two months to minimize the potential for low temperature embrittlement. For all other Type 3 tanks repair of the system within six months is adequate to minimize general corrosion

Financial Analysis for Phase 1 Privatization for the Tank Farm Contractor

International Nuclear Information System (INIS)

BASCHE, A.D.

2000-01-01

The purpose of the Financial Analysis for Phase 1 Privatization for the Tank Farm Contractor is to provide a third-party quantitative and qualitative cost and schedule risk analysis of HNF-1946. The purpose of this Financial Analysis for Phase 1 Privatization for the Tank Farm Contractor (TFC) is to document the results of the risk-based financial analysis of HNF-1946, Programmatic Baseline Summary for Phase 1 Privatization f o r the Tank Farm Contractor (Diediker 2000). This analysis was performed to evaluate how well the proposed baseline meets the U. S. Department of Energy, Office of River Protection (ORP) Letter OO-MSO-009, ''Contract NO. DE-AC06-99RL14047--The US Department of Energy, Office of River Protection (ORP) Mission Planning Guidance for Fiscal Year (FY) 2002--Revision 1'' (Short 2000). The letter requires a confidence level in the baseline schedule that is consistent with the Phase 1A readiness-to-proceed (RTP) assessment conducted in fiscal year (FY) 1998. Because the success of the project depends not only on the budget but also on the schedule, this risk analysis addresses both components of the baseline

Characterization of Samples from Old Solvent Tanks S1 through S22

Energy Technology Data Exchange (ETDEWEB)

Leyba, J.D.

1999-03-25

The Old Radioactive Waste Burial Ground (ORWBG, 643-E) contains 22 old solvent tanks (S1 - S22) which were used to receive and store spent PUREX solvent from F- and H-Canyons. The tanks are cylindrical, carbon-steel, single-wall vessels buried at varying depths. A detailed description of the tanks and their history can be found in Reference 1. A Sampling and Analysis Plan for the characterization of the material contained in the old solvent tanks was developed by the Analytical Development Section (ADS) in October of 19972. The Sampling and Analysis Plan identified several potential disposal facilities for the organic and aqueous phases present in the old solvent tanks which included the Solvent Storage Tank Facility (SSTF), the Mixed Waste Storage Facilities (MWSF), Transuranic (TRU) Pad, and/or the Consolidated Incineration Facility (CIF). In addition, the 241-F/H Tank Farms, TRU Pads, and/or the MWSF were identified as potential disposal facilities for the sludge phases present in the tanks. The purpose of this sampling and characterization was to obtain sufficient data on the material present in the old solvent tanks so that a viable path forward could be established for the closure of the tanks. Therefore, the parameters chosen for the characterization of the various materials present in the tanks were based upon the Waste Acceptance Criteria (WAC) of the SSTF3, TRU Pads4, MWSF5, CIF6, and/or 241-F/H Tank Farms7. Several of the WAC's have been revised, canceled, or replaced by new procedures since October of 1997 and hence where required, the results of this characterization program were compared against the latest revision of the appropriate WAC.

Closure report for underground storage tank 141-R3U1 and its associated underground piping

Energy Technology Data Exchange (ETDEWEB)

Mallon, B.J.; Blake, R.G.

1994-03-01

Underground storage tank UST 141-R3U1 at Lawrence Livermore National Laboratory (LLNL), was registered with the State Water Resources Control Board on June 27, 1984. This tank system consisted of a concrete tank, lined with polyvinyl chloride, and approximately 100 feet of PVC underground piping. UST 141-R3U1 had a capacity of 450 gallons. The underground piping connected three floor drains and one sink inside Building 141 to UST 141-R3U1. The wastewater collected in UST 141-R3U1 contained organic solvents, metals, and inorganic acids. On November 30, 1987, the 141-R3U1 tank system failed a precision tank test. The 141-R3U1 tank system was subsequently emptied and removed from service pending further precision tests to determine the location of the leak within the tank system. A precision tank test on February 5, 1988, was performed to confirm the November 30, 1987 test. Four additional precision tests were performed on this tank system between February 25, 1988, and March 6, 1988. The leak was located where the inlet piping from Building 141 penetrates the concrete side of UST 141-R3U1. The volume of wastewater that entered the backfill and soil around and/or beneath UST 141-R3U1 is unknown. On December 13, 1989, the LLNL Environmental Restoration Division submitted a plan to close UST 141-R3U1 and its associated piping to the Alameda County Department of Environmental Health. UST 141-R3U1 was closed as an UST, and shall be used instead as additional secondary containment for two aboveground storage tanks.

Closure report for underground storage tank 141-R3U1 and its associated underground piping

International Nuclear Information System (INIS)

Mallon, B.J.; Blake, R.G.

1994-03-01

Underground storage tank UST 141-R3U1 at Lawrence Livermore National Laboratory (LLNL), was registered with the State Water Resources Control Board on June 27, 1984. This tank system consisted of a concrete tank, lined with polyvinyl chloride, and approximately 100 feet of PVC underground piping. UST 141-R3U1 had a capacity of 450 gallons. The underground piping connected three floor drains and one sink inside Building 141 to UST 141-R3U1. The wastewater collected in UST 141-R3U1 contained organic solvents, metals, and inorganic acids. On November 30, 1987, the 141-R3U1 tank system failed a precision tank test. The 141-R3U1 tank system was subsequently emptied and removed from service pending further precision tests to determine the location of the leak within the tank system. A precision tank test on February 5, 1988, was performed to confirm the November 30, 1987 test. Four additional precision tests were performed on this tank system between February 25, 1988, and March 6, 1988. The leak was located where the inlet piping from Building 141 penetrates the concrete side of UST 141-R3U1. The volume of wastewater that entered the backfill and soil around and/or beneath UST 141-R3U1 is unknown. On December 13, 1989, the LLNL Environmental Restoration Division submitted a plan to close UST 141-R3U1 and its associated piping to the Alameda County Department of Environmental Health. UST 141-R3U1 was closed as an UST, and shall be used instead as additional secondary containment for two aboveground storage tanks

The reactor kinetics code tank: a validation against selected SPERT-1b experiments

International Nuclear Information System (INIS)

Ellis, R.J.

1990-01-01

The two-dimensional space-time analysis code TANK is being developed for the simulation of transient behaviour in the MAPLE class of research reactors. MAPLE research reactor cores are compact, light-water-cooled and -moderated, with a high degree of forced subcooling. The SPERT-1B(24/32) reactor core had many similarities to MAPLE-X10, and the results of the SPERT transient experiments are well documented. As a validation of TANK, a series of simulations of certain SPERT reactor transients was undertaken. Special features were added to the TANK code to model reactors with plate-type fuel and to allow for the simulation of rapid void production. The results of a series of super-prompt-critical reactivity step-insertion transient simulations are presented. The selected SPERT transients were all initiated from low power, at ambient temperatures, and with negligible coolant flow. Th results of the TANK simulations are in good agreement with the trends in the experimental SPERT data

Aqueous sample from B-Plant, Tank 9-1. Revision 1

International Nuclear Information System (INIS)

Bell, K.E.

1995-01-01

Eight liquid samples were received from B-Plant Tank 9-1 in four lots of two samples each, for inorganic and organic analysis. This is the final report for the sampling and analysis effort; included are summary tables of the analytical and quality control data as well as all raw data. The analyses include pH, OH, inductively coupled plasma spectrography, ion chromatograph, total organic carbon, total inorganic carbon, and differential scanning calorimetry. Included are copies of the chain of custody and request for special analysis forms

ICPP tank farm closure study. Volume 1

International Nuclear Information System (INIS)

Spaulding, B.C.; Gavalya, R.A.; Dahlmeir, M.M.

1998-02-01

The disposition of INEEL radioactive wastes is now under a Settlement Agreement between the DOE and the State of Idaho. The Settlement Agreement requires that existing liquid sodium bearing waste (SBW), and other liquid waste inventories be treated by December 31, 2012. This agreement also requires that all HLW, including calcined waste, be disposed or made road ready to ship from the INEEL by 2035. Sodium bearing waste (SBW) is produced from decontamination operations and HLW from reprocessing of SNF. SBW and HLW are radioactive and hazardous mixed waste; the radioactive constituents are regulated by DOE and the hazardous constituents are regulated by the Resource Conservation and Recovery Act (RCRA). Calcined waste, a dry granular material, is produced in the New Waste Calcining Facility (NWCF). Two primary waste tank storage locations exist at the ICPP: Tank Farm Facility (TFF) and the Calcined Solids Storage Facility (CSSF). The TFF has the following underground storage tanks: four 18,400-gallon tanks (WM 100-102, WL 101); four 30,000-gallon tanks (WM 103-106); and eleven 300,000+ gallon tanks. This includes nine 300,000-gallon tanks (WM 182-190) and two 318,000 gallon tanks (WM 180-181). This study analyzes the closure and subsequent use of the eleven 300,000+ gallon tanks. The 18,400 and 30,000-gallon tanks were not included in the work scope and will be closed as a separate activity. This study was conducted to support the HLW Environmental Impact Statement (EIS) waste separations options and addresses closure of the 300,000-gallon liquid waste storage tanks and subsequent tank void uses. A figure provides a diagram estimating how the TFF could be used as part of the separations options. Other possible TFF uses are also discussed in this study

ICPP tank farm closure study. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Spaulding, B.C.; Gavalya, R.A.; Dahlmeir, M.M. [and others

1998-02-01

The disposition of INEEL radioactive wastes is now under a Settlement Agreement between the DOE and the State of Idaho. The Settlement Agreement requires that existing liquid sodium bearing waste (SBW), and other liquid waste inventories be treated by December 31, 2012. This agreement also requires that all HLW, including calcined waste, be disposed or made road ready to ship from the INEEL by 2035. Sodium bearing waste (SBW) is produced from decontamination operations and HLW from reprocessing of SNF. SBW and HLW are radioactive and hazardous mixed waste; the radioactive constituents are regulated by DOE and the hazardous constituents are regulated by the Resource Conservation and Recovery Act (RCRA). Calcined waste, a dry granular material, is produced in the New Waste Calcining Facility (NWCF). Two primary waste tank storage locations exist at the ICPP: Tank Farm Facility (TFF) and the Calcined Solids Storage Facility (CSSF). The TFF has the following underground storage tanks: four 18,400-gallon tanks (WM 100-102, WL 101); four 30,000-gallon tanks (WM 103-106); and eleven 300,000+ gallon tanks. This includes nine 300,000-gallon tanks (WM 182-190) and two 318,000 gallon tanks (WM 180-181). This study analyzes the closure and subsequent use of the eleven 300,000+ gallon tanks. The 18,400 and 30,000-gallon tanks were not included in the work scope and will be closed as a separate activity. This study was conducted to support the HLW Environmental Impact Statement (EIS) waste separations options and addresses closure of the 300,000-gallon liquid waste storage tanks and subsequent tank void uses. A figure provides a diagram estimating how the TFF could be used as part of the separations options. Other possible TFF uses are also discussed in this study.

Tank Farm Contractor Operation and Utilization Plan [SEC 1 Thru 3

International Nuclear Information System (INIS)

KIRKBRIDE, R.A.

2000-01-01

This document updates the operating scenario and plans for feed delivery to BNFL Inc. of retrieval and waste from single-shell tanks, and the overall process flowsheets for Phases 1 and 2 of the River Protection Project. The plans and flowsheets are updated with the most recent guidance from ORP and tank-by-tank inventory. The results provide the technical basis for the RTP-2 planning effort. Sensitivity cases were run to evaluate the effect of changes on key parameters

Aqueous samples from B-Plant, Tank 9-1

International Nuclear Information System (INIS)

Bell, K.E.

1995-01-01

This document is the final report for the B-Plant Tank 9-1 sampling and analysis program. This report is divided into three parts: first, a narrative about the history, sampling effort, quality control, sample tracking/laboratory identification, and a summary of the analysis; second, sampling and custody data; and lastly, a set of compiled data from the laboratory analysis

Chronic innate immune activation of TBK1 suppresses mTORC1 activity and dysregulates cellular metabolism.

Science.gov (United States)

Hasan, Maroof; Gonugunta, Vijay K; Dobbs, Nicole; Ali, Aktar; Palchik, Guillermo; Calvaruso, Maria A; DeBerardinis, Ralph J; Yan, Nan

2017-01-24

Three-prime repair exonuclease 1 knockout (Trex1 -/- ) mice suffer from systemic inflammation caused largely by chronic activation of the cyclic GMP-AMP synthase-stimulator of interferon genes-TANK-binding kinase-interferon regulatory factor 3 (cGAS-STING-TBK1-IRF3) signaling pathway. We showed previously that Trex1-deficient cells have reduced mammalian target of rapamycin complex 1 (mTORC1) activity, although the underlying mechanism is unclear. Here, we performed detailed metabolic analysis in Trex1 -/- mice and cells that revealed both cellular and systemic metabolic defects, including reduced mitochondrial respiration and increased glycolysis, energy expenditure, and fat metabolism. We also genetically separated the inflammatory and metabolic phenotypes by showing that Sting deficiency rescued both inflammatory and metabolic phenotypes, whereas Irf3 deficiency only rescued inflammation on the Trex1 -/- background, and many metabolic defects persist in Trex1 -/- Irf3 -/- cells and mice. We also showed that Leptin deficiency (ob/ob) increased lipogenesis and prolonged survival of Trex1 -/- mice without dampening inflammation. Mechanistically, we identified TBK1 as a key regulator of mTORC1 activity in Trex1 -/- cells. Together, our data demonstrate that chronic innate immune activation of TBK1 suppresses mTORC1 activity, leading to dysregulated cellular metabolism.

Tank characterization report for single-shell tank 241-B-104

International Nuclear Information System (INIS)

Field, J.G.

1996-01-01

This document summarizes information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-104. Sampling and analyses meet safety screening and historical data quality objectives. This report supports the requirements of Tri-party Agreement Milestone M-44-09. his characterization report summoned the available information on the historical uses and the current status of single-shell tank 241-B-104, and presents the analytical results of the June 1995 sampling and analysis effort. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order Milestone M-44-09 (Ecology et al. 1994). Tank 241-B-104 is a single-shell underground waste storage tank located in the 200 East Area B Tank Farm on the Hanford Site. It is the first tank in a three-tank cascade series. The tank went into service in August 1946 with a transfer of second-cycle decontamination waste generated from the bismuth phosphate process. The tank continued to receive this waste type until the third quarter of 1950, when it began receiving first-cycle decontamination waste also produced during the bismuth phosphate process. Following this, the tank received evaporator bottoms sludge from the 242-B Evaporator and waste generated from the flushing of transfer lines. A description and the status of tank 241-B-104 are sum in Table ES-1 and Figure ES-1. The tank has an operating capacity of 2,010 kL (530 kgal), and presently contains 1,400 kL (371 kgal) of waste. The total amount is composed of 4 kL (1 kgal) of supernatant, 260 kL (69 kgal) of saltcake, and 1,140 kL (301 kgal) of sludge (Hanlon 1995). Current surveillance data and observations appear to support these results

External corrosion of tanks 8D-1 and 8D-2. Final report

International Nuclear Information System (INIS)

Mackey, D.B.; Westerman, R.E.

1995-05-01

Tanks 8D-1 and 8D-2 at the West Valley Nuclear Services (WVNS) site, West Valley, New York, rest on layers of perlite brick contained within steel pans. The pans tend to collect water, which can contact the tanks directly and which also can be ''wicked'' to the external surfaces of the tank through the perlite brick. The presence of air in the tank vault is conducive to the formation of oxygen concentration cells, which can promote localized corrosion of the carbon steel tank wall. Pacific Northwest Laboratory conducted an experiment to estimate the extent to which the external surfaces of the tanks could have corroded in the 30 years since their construction. Specimens of carbon steel, similar to that used in the tank construction, were partially embedded in an upright position in particulate perlite in closed containers. The water line in the containers.was maintained at two levels: above the perlite level (high water level tests) and below the bottoms of the specimens (low water level tests). The water used in the tests was obtained from the pan of tank 8D-1. The containers were maintained in an aerated condition. Specimens were examined after 3-, 6-, 12-, 18-, 24-, and 30-month exposures

Braudel and Abrams open the door to an insoluble debate: The City

Directory of Open Access Journals (Sweden)

Tomás Antônio Moreira

2016-08-01

Full Text Available This paper looks to understand the definitions of the city to enrich the new reflections, in the current days. The starting point for reflection is the confrontation of positions in the understanding of the urban phenomenon, the city, by Fernand Braudel and Philip Abrams, later to emerge in front of the dilemma posed in the confrontation of these two authors, samplings of the main elaborate theorizing on City. Among the findings, it is emphasized that the names of propositions about the city seeking to account for the dynamic evolution of human settlements: métapole, edge city and tecnocity.

Draft Environmental Impact Statement for the tank waste remediation system. Volume 1

International Nuclear Information System (INIS)

1996-04-01

This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, and Ex Situ/In Situ Combination. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. At this time, DOE and Ecology do not have a preferred alternative for the cesium and strontium capsules

A Survey on Aflatoxin M1 Content in Sheep and Goat Milk Produced in Sardinia Region, Italy (2005-2013).

Science.gov (United States)

Virdis, Salvatore; Scarano, Christian; Spanu, Vincenzo; Murittu, Gavino; Spanu, Carlo; Ibba, Ignazio; De Santis, Enrico Pietro Luigi

2014-12-09

In the present work the results of a survey conducted in Sardinia Region on Aflatoxin M 1 (AFM 1 ) contamination in milk of small ruminants from 2005 to 2013 are reported. A total of 517 sheep and 88 goat milk samples from bulk tank, tank trucks and silo tank milk were collected. Analyses were performed by the Regional Farmers Association laboratory using high-performance liquid chromatography following the ISO 14501:1998 standard. None of the sheep milk samples analysed during 2005-2012 showed AFM 1 contamination. In sheep milk samples collected in 2013, 8 out of 172 (4.6%) were contaminated by AFM 1 with a concentration (mean±SD) of 12.59±14.05 ng/L. In one bulk tank milk sample 58.82 ng/L AFM 1 was detected, exceeding the EU limit. In none of goat milk samples analysed from 2010 to 2012 AFM 1 was detected. In 2013, 9 out of 66 goat milk samples (13.6%) showed an AFM 1 concentration of 47.21±19.58 ng/L. Two of these samples exceeded the EU limit, with concentrations of 62.09 and 138.6 ng/L. Higher contamination frequency and concentration rates were detected in bulk tank milk samples collected at farm than in bulk milk truck or silo samples, showing a dilution effect on AFM 1 milk content along small ruminants supply chain. The rate and levels of AFM 1 contamination in sheep and goat milk samples were lower than other countries. However, the small number of milk samples analysed for AFM 1 in Sardinia Region in 2005-2013 give evidence that food business operators check programmes should be improved to ensure an adequate monitoring of AFM 1 contamination in small ruminant dairy chain.

A survey on Aflatoxin M1 content in sheep and goat milk produced in Sardinia Region, Italy (2005-2013

Directory of Open Access Journals (Sweden)

Salvatore Virdis

2014-12-01

Full Text Available In the present work the results of a survey conducted in Sardinia Region on Aflatoxin M1 (AFM1 contamination in milk of small ruminants from 2005 to 2013 are reported. A total of 517 sheep and 88 goat milk samples from bulk tank, tank trucks and silo tank milk were collected. Analyses were performed by the Regional Farmers Association laboratory using high-performance liquid chromatography following the ISO 14501:1998 standard. None of the sheep milk samples analysed during 2005- 2012 showed AFM1 contamination. In sheep milk samples collected in 2013, 8 out of 172 (4.6% were contaminated by AFM1 with a concentration (mean±SD of 12.59±14.05 ng/L. In one bulk tank milk sample 58.82 ng/L AFM1 was detected, exceeding the EU limit. In none of goat milk samples analysed from 2010 to 2012 AFM1 was detected. In 2013, 9 out of 66 goat milk samples (13.6% showed an AFM1 concentration of 47.21±19.58 ng/L. Two of these samples exceeded the EU limit, with concentrations of 62.09 and 138.6 ng/L. Higher contamination frequency and concentration rates were detected in bulk tank milk samples collected at farm than in bulk milk truck or silo samples, showing a dilution effect on AFM1 milk content along small ruminants supply chain. The rate and levels of AFM1 contamination in sheep and goat milk samples were lower than other countries. However, the small number of milk samples analysed for AFM1 in Sardinia Region in 2005-2013 give evidence that food business operators check programmes should be improved to ensure an adequate monitoring of AFM1 contamination in small ruminant dairy chain.

Super Phenix 1: in Service inspection of main and safety tanks weldments

International Nuclear Information System (INIS)

Asty, Michel; Vertut, Jean; Argous, J.P.

1980-05-01

In service inspection of the main tank of the Super Phenix 1 reactor is a new demand as compared to Phenix: the authorities have asked that surface and internal defects could be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks

Super Phenix 1: In-service inspection of main and safety tanks weldments

Energy Technology Data Exchange (ETDEWEB)

Asty, M [DTech/STA, Centre d' Etudes Nucleaires de Saclay (France); Vertut, J [DPR/STEP, Centre d' Etudes Nucleaires de Saclay (France); Argous, J P [DRNR/STRS, Centre d' Etudes Nucleaires de Cadarache (France)

1980-11-01

In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

Super Phenix 1: In-service inspection of main and safety tanks weldments

International Nuclear Information System (INIS)

Asty, M.; Vertut, J.; Argous, J.P.

1980-01-01

In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

La-related protein 1 (LARP1) represses terminal oligopyrimidine (TOP) mRNA translation downstream of mTOR complex 1 (mTORC1)

DEFF Research Database (Denmark)

Fonseca, Bruno; Zakaria, Chadi; Jia, J J

2015-01-01

is incompletely understood. Here, we report that LARP1 functions as a key repressor of TOP mRNA translation downstream of mTORC1. Our data show the following: (i) LARP1 associates with mTORC1 via RAPTOR; (ii) LARP1 interacts with TOP mRNAs in an mTORC1-dependent manner; (iii) LARP1 binds the 5′TOP motif...

CYP1A1 m1 and m2 polymorphisms: genetic susceptibility to lung cancer

Directory of Open Access Journals (Sweden)

Paula Mota

2010-01-01

Full Text Available Lung cancer is considered an environment-related disease that develops as a consequence of exposure to mutagenic agents, namely those present in tobacco. The CYP1A1 gene codifies the phase I enzyme aryl hydrocarbon hydroxilase (AHH belonging to the cytochrome P450 system that plays a major role in the bio-activation of tobacco procarcinogenes. Two CYP1A1 polymorphisms, m1 (T6235C transition and m2 (A4889G transition, are associated with greater enzymatic activity and have been described as genetic susceptibility factors for lung cancer.The aim of this study was to verify if this association holds true in blood samples of 175 lung cancer patients and 217 non-cancer patients from Portugal's midlands region. The samples were studied by restriction fragment length polymorphism (RFLP assay.The allelic frequencies of the mutant alleles were 0.12 for allele C and 1.14 for allele G in the control population. The results were not statistically different from those alleles in the patient population. There was also no statistically significant difference in genotype distribution in lung cancer patients and controls even when combining high risk genotypes. In our control sample, as in other populations of different ethnic origin, both polymorphisms also seem to be in linkage disequilibrium. We conclude that in this sample of the Portuguese population, CYP1A1 m1 and m2 polymorphisms are too rare to be of clinical relevance, and do not seem to be associated with susceptibility to lung cancer. Resumo: O cancro do pulmão é considerado uma doença relacionada com o meio ambiente, consequência da exposição a agentes mutagénicos, nomeadamente os presentes no fumo do tabaco. O gene CYP1A1 codifica a enzima aril hidrocarboneto hidroxilase (AHH, da fase I, do sistema multienzimático do citocromo P450, que desempenha uma função preponderante na bioactivação dos procarcinogénios do tabaco. Dois polimorfismos do CYP1A1, m1 (transi

The Development of a Single Tank Tactical Exercise for Training M1 Tank Commanders

Science.gov (United States)

1987-06-01

Evaluate the Conduct of Training NL NL NS Fire an M250 Grenade Launcher S S NS Identify Adjoining Map Sheets S S NS Identify Terrain Features on a Map S S...the Commander’s Weapon Station Establish, Enter, and Leave a Radio Net Estimate Range Evaluate the Conduct of Training Fire an M250 Grenade Launcher...from the Commander’s Weapon S Station (CWS) Fire an M250 Smoke Grenade Launcher Set Headspace and Timing on a Caliber .50 M2 HB Machinegun Zero a

Tank 241-C-108 vapor sampling and analysis tank characterization report. Revision 1

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

Tank 241-C-108 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in open-quotes Program Plan for the Resolution of Tank Vapor Issues.close quotes Tank 241-C-108 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

Tank 241-BY-107 vapor sampling and analysis tank characterization report. Revision 1

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

Tank 241-BY-107 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in open-quotes Program Plan for the Resolution of Tank Vapor Issues.close quotes Tank 241-BY-107 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

Tank 241-BY-108 vapor sampling and analysis tank characterization report. Revision 1

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

Tank 241-BY-108 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in ''Program Plan for the Resolution of Tank Vapor Issues'' (Osborne and Huckaby 1994). Tank 241-BY-108 was vapor sampled in accordance with ''Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution (Osborne et al., 1994)

Tank 241-BY-106 vapor sampling and analysis tank characterization report. Revision 1

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

Tank 241-BY-106 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in open-quotes Program Plan for the Resolution of Tank Vapor Issues.close quotes Tank 241-BY-106 was vapor sampled in accordance with open-quotes Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.close quotes

Fish stocking density impacts tank hydrodynamics

DEFF Research Database (Denmark)

Rasmussen, Michael R.; Lunger, Angela; Laursen, Jesper

2006-01-01

The effect of stocking density upon the hydrodynamics of a circular tank, configured in a recirculation system, was investigated. Red drums Sciaenops ocellatus of approximately 140 g wet weight, were stocked at five rates varying from 0 to 12 kg m-3. The impact of the presence of fish upon tank...... hydrodynamics was established using in-tank-based Rhodamine WT fluorometry at a flow rate of 0.23 l s-1 (tank exchange rate of 1.9 h-1). With increasing numbers of animals, curvilinear relationships were observed for dispersion coefficients and tank mixing times. Stocking densities of 3, 6, 9 and 12 kg m-3...

The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 1 [of 2

Energy Technology Data Exchange (ETDEWEB)

Lewis, BE

2003-10-07

The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. A phased and integrated approach to waste retrieval operations was used for the GAAT Remediation Project. The project promoted safety by obtaining experience from low-risk operations in the North Tank Farm before moving to higher-risk operations in the South Tank Farm. This approach allowed project personnel to become familiar with the tanks and waste, as well as the equipment, processes, procedures, and operations required to perform successful waste retrieval. By using an integrated approach to tank waste retrieval and tank waste management, the project was completed years ahead of the original baseline schedule, which resulted in avoiding millions of dollars in associated costs. This report is organized in two volumes. Volume 1 provides information on the various phases of the GAAT Remediation Project. It also describes the different types of equipment and how they were used. The emphasis of Volume 1 is on the description of the tank waste retrieval performance and the lessons learned during the GAAT Remediation Project. Volume 2 provides the appendixes for the report, which include the following information: (A) Background Information for the Gunite and Associated Tanks Operable Unit; (B) Annotated Bibliography; (C) Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; (D) GAAT Equipment Matrix; and (E) Vendor List

Initial tank calibration at NUCEF critical facility. 1. Measurement procedure and its result

International Nuclear Information System (INIS)

Yanagisawa, Hiroshi; Mineo, Hideaki; Tonoike, Kotaro; Takeshita, Isao; Hoshi, Katsuya; Hagiwara, Hiroyuki.

1994-07-01

Initial tank calibrations were carried out prior to hot operation of critical facilities in NUCEF: Nuclear Fuel Cycle Safety Engineering Research Facility, for the purpose of the nuclear material accountancy and control for the facility. Raw calibration data were collected from single run per one tank by measuring differential pressure with dip-tube systems, weight of calibration liquid (demineralized water) poured into the tank, temperature in the tank and so on, without operation of tank ventilation system. Volume and level data were obtained by applying density and buoyancy corrections to the raw data. As a result, the evaluated measurement errors of volume and level were small enough, e.g. within 0.2 lit. and 1.0 mm, respectively, for Pu accountancy tanks. This paper summarizes the above-mentioned measurement procedures, collected data, data correction procedures and evaluated measurement errors. (author)

Sampling and analysis of the inactive waste tanks TH-2, WC-1, and WC-15

International Nuclear Information System (INIS)

Autrey, J.W.; Keller, J.M.; Griest, W.H.; Botts, J.L.; Schenley, R.L.; Sipe, M.A.

1992-02-01

Thirty-eight inactive liquid low-level radioactive waste tanks are currently managed by the Environmental Restoration Program of Oak Ridge National Laboratory. The contents of these tanks are to be characterized in preparation for future corrective actions and remediation activities as part of compliance with the pending Federal Facility Agreement for the Oak Ridge Reservation. Twenty-nine of these tanks were sampled and analyzed in 1989. Three of the tanks (TH-2, WC-1, and WC-15) were not accessible from the surface and thus were not sampled until 1990. This report presents the sampling and analytical results of that campaign. All three tanks in this report had negligible regulatory organic compounds in the samples that were collected. There were no US Environmental Protection Agency (EPA) Target Compound List (TCL) constituents for volatile organics detected in any of the aqueous samples. The only semivolatile organics detected were 2-chlorophenol (52 μg/L) in tank TH-2 and dichloroethane (14--15 μg/L) and diethyl either (15--17 μg/L) in tank WC-15. A thin oil layer was discovered floating on top of the aqueous contents in tank WC-15. The analysis of the oil layer detected no volatile organics and showed only one EPA TCL constituent, di-n-butylphthalate, at 1900 μg/L. Low levels of Resource Conservation and Recovery Act (RCRA) metals were observed in the samples from tank TH-2, but only the mercury level exceeded the RCRA limit. Samples from tank WC-1 had elevated levels of the RCRA metals barium, chromium, and lead. There were also finely suspended particles in one of the samples from tank WC-1, which was filtered and analyzed separately. This solid fines have levels of transuranium elements 238 Pu and 241 Am high enough to classified as transuranic waste

M1 and M2 Monocytes in Rheumatoid Arthritis: A Contribution of Imbalance of M1/M2 Monocytes to Osteoclastogenesis

Directory of Open Access Journals (Sweden)

Shoichi Fukui

2018-01-01

Full Text Available ObjectivesWe investigated the relationships among M1 monocytes, M2 monocytes, osteoclast (OC differentiation ability, and clinical characteristics in patients with rheumatoid arthritis (RA.MethodsPeripheral blood mononuclear cells (PBMCs were isolated from RA patients and healthy donors, and we then investigated the number of M1 monocytes or M2 monocytes by fluorescence-activated cell sorting. We also obtained and cultured CD14-positive cells from PBMCs from RA patients and healthy donors to investigate OC differentiation in vitro.ResultsForty RA patients and 20 healthy donors were included. Twenty-two patients (55% were anticitrullinated protein antibody (ACPA positive. The median M1/M2 ratio was 0.59 (0.31–1.11, interquartile range. There were no significant differences between the RA patients and healthy donors. There was a positive correlation between the M1/M2 ratio and the differentiated OC number in vitro in RA patients (ρ = 0.81, p < 0.001. The ACPA-positive patients had significantly higher M1/M2 ratios in vivo (p = 0.028 and significantly greater numbers of OCs in vitro (p = 0.005 than the ACPA-negative patients. Multivariable regression analysis revealed that the M1/M2 ratio was the sole significant contribution factor to in vitro osteoclastogenesis. RA patients with M1/M2 ratios >1 (having relatively more M1 monocytes had higher C-reactive protein and erythrocyte sedimentation rates than RA patients with M1/M2 ratios ≤1. M1-dominant monocytes in vitro produced higher concentrations of interleukin-6 upon stimulation with lipopolysaccharide than M2 monocytes.ConclusionM1/M2 monocytes imbalance strongly contributes to osteoclastogenesis of RA patients. Our findings cast M1 and M2 monocyte subsets in a new light as a new target of treatments for RA to prevent progression of osteoclastic bone destruction.

THE GROWTH OF PATIN Pangasiodon hypophthalmus IN A CLOSE SYSTEM TANK

Directory of Open Access Journals (Sweden)

Taufik Ahmad

2007-06-01

Full Text Available This experiment aimed to evaluate the possibility of using integrated recirculation production system for patin grow-out. Each of twelve concrete 2.5 m x 4.0 m x 1.0 m tanks filled to 0.73 m depth was stocked with 100 juvenile patin, 9-10g body weight. Six tanks were equipped with sand and palm (Arenga pinata fibre filters planted with vegetables, lettuce and kangkoong. A submersible pump was installed in each tank to assure continuous water recirculation at the rate of 0.4 L sec-1. The filtered water flowed into the tank at the surface (SC treatment, or at the bottom (BC treatment. In the other 6 tanks, the water flowed continuously from a concrete canal in an open culture system at a similar rate and with similar water entrance positions (SO and BO treatments. The experiment was arranged in a completely randomized design with three replicates. The fish were fed dry pelleted feed to satiation and sampled every other week for growth observation. After 90 days, the average individual weight of the fish attained the range of 80-100 g. The fish grew significantly faster (P0.05 among treatment, ranging from 99% to 100%. In terms of water usage, the closed system tanks produced fish weighing 202.38–220.05 g m-3, much more efficiently than did the open system tanks, 1.87–1.89 g/m3. The vegetables, either lettuce or water spinach, grew well on the filter. These results suggest that the integrated recirculation tank system is suitable for patin culture.

Infinitely many N=1 dualities from m+1−m=1

Energy Technology Data Exchange (ETDEWEB)

Agarwal, Prarit; Intriligator, Kenneth; Song, Jaewon [Department of Physics, University of California,San Diego, La Jolla, CA 92093 (United States)

2015-10-06

We discuss two infinite classes of 4d supersymmetric theories, T{sub N}{sup (m)} and U{sub N}{sup (m)}, labelled by an arbitrary non-negative integer, m. The T{sub N}{sup (m)} theory arises from the 6d, A{sub N−1} type N=(2,0) theory reduced on a 3-punctured sphere, with normal bundle given by line bundles of degree (m+1,−m); the m=0 case is the N=2 supersymmetric T{sub N} theory. The novelty is the negative-degree line bundle. The U{sub N}{sup (m)} theories likewise arise from the 6d N=(2,0) theory on a 4-punctured sphere, and can be regarded as gluing together two (partially Higgsed) T{sub N}{sup (m)} theories. The T{sub N}{sup (m)} and U{sub N}{sup (m)} theories can be represented, in various duality frames, as quiver gauge theories, built from T{sub N} components via gauging and nilpotent Higgsing. We analyze the RG flow of the U{sub N}{sup (m)} theories, and find that, for all integer m>0, they end up at the same IR SCFT as SU(N) SQCD with 2N flavors and quartic superpotential. The U{sub N}{sup (m)} theories can thus be regarded as an infinite set of UV completions, dual to SQCD with N{sub f}=2N{sub c}. The U{sub N}{sup (m)} duals have different duality frame quiver representations, with 2m+1 gauge nodes.

Speciation of organic carbon in Hanford waste storage tanks: Part 1

International Nuclear Information System (INIS)

Carlson, C.D.

1997-02-01

This report is the first in a series to report on speciation of organic carbon in Hanford waste storage tanks. The comparison of the existing total organic carbon with oxalate and limited analyses of other organic species (acetate, formate, and normal paraffin hydrocarbons [NPH]) are reported. All of the data have been previously reported by the Grout and Characterization programs; the information includes all of the publicly available data through October 1996. Oxalate data were reported for 33 tanks, TOC data were reported for 82 tanks, and both oxalate and TOC data were available for 27 tanks. Of these 27 tanks, seven were found to have greater than 80% of the TOC identified as oxalate: 241-BY-104, 241-BY-105, 241-BY-106, 241-BY-110, 241-S-109, and 241-SX-108. Eighty percent accountability has been tentatively established as a minimum goal of the Organic Safety Program for speciation of TOC. Accountability of TOC through speciation will allow more accurate estimate of the potential energy content of the wastes as currently stored. Of the remaining 19 tanks, seven had between 40 and 80% of the TOC identified as oxalate, and eleven had less than 35% of the TOC identified. Of these, only five tanks had segment results that were greater than 1% TOC, and none was above 2%. Since the cur-rent safety criterion outlined in the Safety Analysis is 4.5% TOC, it may be determined that the further analyses of these tank wastes are not necessary. If additional analyses are deemed necessary, minimal work may be required, possibly limited to ion chromatography (IC), ion pair chromatography and capillary zone electrophoresis (CZE). Additional speciation work is planned for this fiscal year in both the Organic Tanks Safety and Characterization programs. The Characterization program reports acetate and formate data in addition to the oxalate data for all the tank cores it processes

Proceedings of the IDA Workshop on Formal Specification and Verification of Ada (Trade Name) (1st) Held in Alexandria, Virginia on 18-20 March 1985.

Science.gov (United States)

1985-12-01

on the third day. 5 ADA VERIFICATION WORKSHOP MARCH 18-20, 1985 LIST OF PARTICIPANTS Bernard Abrams ABRAMS@ADA20 Grumman Aerospace Corporation Mail...20301-3081 (202) 694-0211 Mark R. Cornwell CORNWELL @NRL-CSS Code 7590 Naval Research Lab Washington, D.C. 20375 (202) 767-3365 Jeff Facemire FACEMIRE...accompanied by descriptions of their purpose in English, to LUCKHAM@SAIL for annotation. - X-2 DISTRIBUTION LIST FOR M-146 Bernard Abrams ABRAMS@USC-ECLB

A survey of aflatoxin M1 in cow milk in Southern Iran

Directory of Open Access Journals (Sweden)

Majid Hashemi

2016-10-01

Full Text Available The competitive enzyme-linked immunosorbent assay technique was used to evaluate aflatoxin M1 (AFM1 levels in 168 samples of raw milk (135 samples and 33 samples from bulk tanks of farms and milk collection centers, respectively and 12 samples of pasteurized milk in Fars province, Southern Iran. AFM1 was found in 55.56% of the samples with a mean concentration of 21.31 ng/L. The concentration of AFM1 in raw milk samples from farms was significantly (p < 0.05 lower than that in samples from collection centers and pasteurized milk. The concentration of AFM1 was not influenced by season, location, or type of farm. The concentrations of AFM1 in all samples were lower than the Iranian national standard limit (100 ng/L, but in 30% of raw cow milk samples they were higher than the maximum tolerance limit accepted by the European Union (50 ng/L; therefore, more effort is needed to control AFM1 levels in milk produced in Southern Iran.

Double-shell tank ultrasonic inspection plan. Revision 1

International Nuclear Information System (INIS)

Pfluger, D.C.

1994-01-01

The waste tank systems managed by the Tank Waste Remediation System Division of Westinghouse Hanford Company includes 28 large underground double-shell tanks (DST) used for storing hazardous radioactive waste. The ultrasonic (UT) inspection of these tanks is part of their required integrity assessment (WAC 1993) as described in the tank systems integrity assessment program plan (IAPP) (Pfluger 1994a) submitted to the Ecology Department of the State of Washington. Because these tanks hold radioactive waste and are located underground examinations and inspections must be done remotely from the tank annuli with specially designed equipment. This document describes the UT inspection system (DSTI system), the qualification of the equipment and procedures, field inspection readiness, DST inspections, and post-inspection activities. Although some of the equipment required development, the UT inspection technology itself is the commercially proven and available projection image scanning technique (P-scan). The final design verification of the DSTI system will be a performance test in the Hanford DST annulus mockup that includes the demonstration of detecting and sizing corrosion-induced flaws

Sampling and Analysis Plan for Tank 241-AP-108 Waste in Support of Evaporator Campaign 2000-1

International Nuclear Information System (INIS)

RASMUSSEN, J.H.

2000-01-01

This Tank Sampling and Analysis Plan (TSAP) identifies sample collection, laboratory analysis, quality assurance/quality control (QA/QC), and reporting objectives for the characterization of tank 241-AP-108 waste. Technical bases for these objectives are specified in the 242-A Evaporator Data Quality Objectives (Bowman 2000 and Von Bargen 1998) and 108-AP Tank Sampling Requirements in Support of Evaporator Campaign 2000-1 (Le 2000). Evaporator campaign 2000-1 will process waste from tank 241-AP-108 in addition to that from tank 241-AP-107. Characterization results will be used to support the evaporator campaign currently planned for early fiscal year 2000. No other needs (or issues) requiring data for this tank waste apply to this sampling event

Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Appendix A

International Nuclear Information System (INIS)

1995-09-01

This document is a compilation of data relating to the Tank Waste Remediation System Multi-Year Program. Topics discussed include: management systems; waste volume, transfer and evaporation management; transition of 200 East and West areas; ferricyanide, volatile organic vapor, and flammable gas management; waste characterization; retrieval from SSTs and DSTs; heat management; interim storage; low-level and high-level radioactive waste management; and tank farm closure

Tank 241-BY-108 vapor sampling and analysis tank characterization report

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

Tank BY-108 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-108 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-108 using the vapor sampling system (VSS) on october 27, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 25.7 C. Air from the Tank BY-108 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 1, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, and Pacific Northwest Laboratories. The 40 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks that accompanied the samples

ULC/ORD-C80.1 : the standard for aboveground non-metallic tanks for fuel oil

Energy Technology Data Exchange (ETDEWEB)

Nikolic, G. [Underwriters' Lab. of Canada, Toronto, ON (Canada)

2001-09-01

As a rule, flammable and combustible liquids were stored in aboveground tanks made of steel. Non-metallic materials are now being used for a new generation of aboveground tanks. Corrosion is a problem faced by most tank owners in many parts of Canada. Saltwater mist, sand blasting and bacteria growth formed in the condensation water at the bottom of the tank in the Maritimes affects an aboveground tank installed outdoors and close to the seashore. European non-metallic aboveground tanks for fuel oil first arrived on the North American market, and are now followed by designs from Canada. Requirements for these tanks were developed and tested by the Underwriters' Laboratories of Canada (ULC). It is a not-for-profit, independent organization accredited by the Standards Council of Canada to perform safety, certification, testing, quality registration, and standards development. The minimum criteria for non-metallic aboveground tank construction are contained in the ULC/ORD-C80.1 document. They can be constructed of fiber-reinforced plastic (FRP), single or double wall, or they can be double wall tanks consisting of primary plastic tanks within metallic secondary containment. Other tanks are made of the blow molded high-density polyethylene. To simulate an in-house installation, fire tests were performed where a tank filled with fuel was exposed to pool fire for 30 minutes. A successful test meant the tank had not ruptured nor leaked during and after the test. Testers had to observe that any collapse occurred above the liquid level, and that violent explosion of any part of the tank or its content did not occur. The design requirements were evaluated by performing an analysis of the temperature chart: maximum vapour temperature inside the tank was 358 Celsius, while the liquid reached a maximum temperature of 91 Celsius and the outside temperature reached 600 Celsius. Primary tank pressure did not exceed 17 kilo Pascal. Building simulation of venting installation

Tank 241-C-111 vapor sampling and analysis tank characterization report. Revision 1

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

This report presents the details of the Hanford waste tank characterization study for tank 241-C-111. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedures that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to tank farm workers due to fugitive emissions from the tank

Tank 241-BY-110 vapor sampling and analysis tank characterization report. Revision 1

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

This report presents the details of the Hanford waste tank characterization study for tank 241-BY-110. The drivers and objectives of the headspace vapor sampling and analysis were in accordance with procedures that were presented in other reports. The vapor and headspace gas samples were collected and analyzed to determine the potential risks to the tank farm workers due to fugitive emissions from the tank

46 CFR 32.55-1 - Ventilation of tank vessels constructed on or after July 1, 1951-TB/ALL.

Science.gov (United States)

2010-10-01

... natural ventilation, with at least one duct extending to immediately below the floor plates will be... 46 Shipping 1 2010-10-01 2010-10-01 false Ventilation of tank vessels constructed on or after July... VESSELS SPECIAL EQUIPMENT, MACHINERY, AND HULL REQUIREMENTS Ventilation and Venting § 32.55-1 Ventilation...

2006 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

International Nuclear Information System (INIS)

D. E. Shanklin

2007-01-01

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report covers the time period from January 1 through December 31, 2006, and describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action (DOE/ID-10660) as described in the Group 1 Remedial Design/Remedial Action Work Plan (DOE/ID-10772)

Tank 241-BY-110 tank characterization plan. Revision 1

International Nuclear Information System (INIS)

Homi, C.S.

1995-01-01

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-BY-110

Tank 241-AN-102 tank characterization plan. Revision 1

International Nuclear Information System (INIS)

Homi, C.S.

1995-01-01

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-AN-102

Tank 241-U-111 tank characterization plan. Revision 1

International Nuclear Information System (INIS)

Homi, C.S.

1995-01-01

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-U-111

Tank 241-S-107 tank characterization plan. Revision 1

International Nuclear Information System (INIS)

Homi, C.S.

1995-01-01

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-S-107

Tank 241-B-106 tank characterization plan. Revision 1

International Nuclear Information System (INIS)

Homi, C.S.

1995-01-01

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-B-106

Tank 241-SY-103 tank characterization plan. Revision 1

International Nuclear Information System (INIS)

Homi, C.S.

1995-01-01

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-SY-103

Programmatic Baseline Summary for Phase 1 Privatization for the Tank Farm contractor

International Nuclear Information System (INIS)

DIEDIKER, J.A.

2000-01-01

The document describes the systematic integrated baseline planning process and provides a summary of the Tank Farm Contractor scope, schedule and cost analysis developed in support of the Phase 1 privatization mission

Programmatic Baseline Summary for Phase 1 Privatization for the Tank Farm contractor

Energy Technology Data Exchange (ETDEWEB)

DIEDIKER, J.A.

2000-04-22

The document describes the systematic integrated baseline planning process and provides a summary of the Tank Farm Contractor scope, schedule and cost analysis developed in support of the Phase 1 privatization mission.

Headspace vapor characterization of Hanford Waste Tank 241-SX-109: Results from samples collected on August 1, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

Pool, K.H.; Clauss, T.W.; Evans, J.C.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-109 (Tank SX-109) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5048. Samples were collected by WHC on August 1, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

TBK1 Regulates Prostate Cancer Dormancy through mTOR Inhibition

Directory of Open Access Journals (Sweden)

Jin Koo Kim

2013-09-01

Full Text Available The mechanisms that regulate hematopoietic stem cell (HSC dormancy and self-renewal are well established and are largely dependent on signals emanating from the HSC niche. Recently, we found that prostate cancer (PCa cells target the HSC niche in mouse bone marrow (BM during metastasis. Little is known, however, as to how the HSC niche may regulate dormancy in cancer cells. In this study, we investigated the effects of TANK binding kinase 1 (TBK1 on PCa dormancy in the BM niche. We found that binding with niche osteoblasts induces the expression of TBK1 in PCa cells PC3 and C4-2B. Interestingly, TBK1 interacts with mammalian target of rapamycin (mTOR and inhibits its function. Rapamycin, an mTOR inhibitor, induces cell cycle arrest of PCa cells and enhances chemotherapeutic resistance of PCa cells. As a result, the knockdown of TBK1 decreases PCa stem-like cells and drug resistance in vitro and in vivo. Taken together, these results strongly indicate that TBK1 plays an important role in the dormancy and drug resistance of PCa.

Comparison of the 1D flux theory with a 2D hydrodynamic secondary settling tank model.

Science.gov (United States)

Ekama, G A; Marais, P

2004-01-01

The applicability of the 1D idealized flux theory (1DFT) for design of secondary settling tanks (SSTs) is evaluated by comparing its predicted maximum surface overflow (SOR) and solids loading (SLR) rates with that calculated from the 2D hydrodynamic model SettlerCAD using as a basis 35 full scale SST stress tests conducted on different SSTs with diameters from 30 to 45m and 2.25 to 4.1 m side water depth, with and without Stamford baffles. From the simulations, a relatively consistent pattern appeared, i.e. that the 1DFT can be used for design but its predicted maximum SLR needs to be reduced by an appropriate flux rating, the magnitude of which depends mainly on SST depth and hydraulic loading rate (HLR). Simulations of the sloping bottom shallow (1.5-2.5 m SWD) Dutch SSTs tested by STOWa and the Watts et al. SST, all with doubled SWDs, and the Darvill new (4.1 m) and old (2.5 m) SSTs with interchanged depths, were run to confirm the sensitivity of the flux rating to depth and HLR. Simulations with and without a Stamford baffle were also done. While the design of the internal features of the SST, such as baffling, have a marked influence on the effluent SS concentration for underloaded SSTs, these features appeared to have only a small influence on the flux rating, i.e. capacity, of the SST, In the meantime until more information is obtained, it would appear that from the simulations so far that the flux rating of 0.80 of the 1DFT maximum SLR recommended by Ekama and Marais remains a reasonable value to apply in the design of full scale SSTs--for deep SSTs (4 m SWD) the flux rating could be increased to 0.85 and for shallow SSTs (2.5 m SWD) decreased to 0.75. It is recommended that (i) while the apparent interrelationship between SST flux rating and depth suggests some optimization of the volume of the SST, that this be avoided and that (ii) the depth of the SST be designed independently of the surface area as is usually the practice and once selected, the

40 CFR Table 1 to Subpart Bbbbbb... - Applicability Criteria, Emission Limits, and Management Practices for Storage Tanks

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 14 2010-07-01 2010-07-01 false Applicability Criteria, Emission Limits, and Management Practices for Storage Tanks 1 Table 1 to Subpart BBBBBB of Part 63 Protection of... Criteria, Emission Limits, and Management Practices for Storage Tanks If you own or operate Then you must 1...

Influenza A Virus NS1 Protein Promotes Efficient Nuclear Export of Unspliced Viral M1 mRNA.

Science.gov (United States)

Pereira, Carina F; Read, Eliot K C; Wise, Helen M; Amorim, Maria J; Digard, Paul

2017-08-01

Influenza A virus mRNAs are transcribed by the viral RNA-dependent RNA polymerase in the cell nucleus before being exported to the cytoplasm for translation. Segment 7 produces two major transcripts: an unspliced mRNA that encodes the M1 matrix protein and a spliced transcript that encodes the M2 ion channel. Export of both mRNAs is dependent on the cellular NXF1/TAP pathway, but it is unclear how they are recruited to the export machinery or how the intron-containing but unspliced M1 mRNA bypasses the normal quality-control checkpoints. Using fluorescent in situ hybridization to monitor segment 7 mRNA localization, we found that cytoplasmic accumulation of unspliced M1 mRNA was inefficient in the absence of NS1, both in the context of segment 7 RNPs reconstituted by plasmid transfection and in mutant virus-infected cells. This effect was independent of any major effect on steady-state levels of segment 7 mRNA or splicing but corresponded to a ∼5-fold reduction in the accumulation of M1. A similar defect in intronless hemagglutinin (HA) mRNA nuclear export was seen with an NS1 mutant virus. Efficient export of M1 mRNA required both an intact NS1 RNA-binding domain and effector domain. Furthermore, while wild-type NS1 interacted with cellular NXF1 and also increased the interaction of segment 7 mRNA with NXF1, mutant NS1 polypeptides unable to promote mRNA export did neither. Thus, we propose that NS1 facilitates late viral gene expression by acting as an adaptor between viral mRNAs and the cellular nuclear export machinery to promote their nuclear export. IMPORTANCE Influenza A virus is a major pathogen of a wide variety of mammalian and avian species that threatens public health and food security. A fuller understanding of the virus life cycle is important to aid control strategies. The virus has a small genome that encodes relatively few proteins that are often multifunctional. Here, we characterize a new function for the NS1 protein, showing that, as well as

Tank 241-BY-103 Tank Characterization Plan. Revision 1

International Nuclear Information System (INIS)

Schreiber, R.D.

1995-01-01

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-BY-103

Heat removal characteristics of waste storage tanks. Revision 1

International Nuclear Information System (INIS)

Kummerer, M.

1995-10-01

A topical report that examines the relationship between tank heat load and maximum waste temperatures. The passive cooling response of the tanks is examined, and loss of active cooling in ventilated tanks is investigated

Tank 241-C-101 vapor sampling and analysis tank characterization report

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

Tank C-101 headspace gas and vapor samples were collected and analyzed to help determine the potential risks of fugitive emissions to tank farm workers. Gas and vapor samples from the Tank C-101 headspace were collected on July 7, 1994 using the in situ sampling (ISS) method, and again on September 1, 1994 using the more robust vapor sampling system (VSS). Gas and vapor concentrations in Tank C-101 are influenced by its connections to other tanks and its ventilation pathways. At issue is whether the organic vapors in Tank C-101 are from the waste in that tank, or from Tanks C-102 or C-103. Tank C-103 is on the Organic Watch List; the other two are not. Air from the Tank C-101 headspace was withdrawn via a 7.9-m long heated sampling probe mounted in riser 8, and transferred via heated tubing to the VSS sampling manifold. The tank headspace temperature was determined to be 34.0 C, and all heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 39 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks provided by the laboratories

Apolipoprotein M can discriminate HNF1A-MODY from Type 1 diabetes.

Science.gov (United States)

Mughal, S A; Park, R; Nowak, N; Gloyn, A L; Karpe, F; Matile, H; Malecki, M T; McCarthy, M I; Stoffel, M; Owen, K R

2013-02-01

Missed diagnosis of maturity-onset diabetes of the young (MODY) has led to an interest in biomarkers that enable efficient prioritization of patients for definitive molecular testing. Apolipoprotein M (apoM) was suggested as a biomarker for hepatocyte nuclear factor 1 alpha (HNF1A)-MODY because of its reduced expression in Hnf1a(-/-) mice. However, subsequent human studies examining apoM as a biomarker have yielded conflicting results. We aimed to evaluate apoM as a biomarker for HNF1A-MODY using a highly specific and sensitive ELISA. ApoM concentration was measured in subjects with HNF1A-MODY (n = 69), Type 1 diabetes (n = 50), Type 2 diabetes (n = 120) and healthy control subjects (n = 100). The discriminative accuracy of apoM and of the apoM/HDL ratio for diabetes aetiology was evaluated. Mean (standard deviation) serum apoM concentration (μmol/l) was significantly lower for subjects with HNF1A-MODY [0.86 (0.29)], than for those with Type 1 diabetes [1.37 (0.26), P = 3.1 × 10(-18) ) and control subjects [1.34 (0.22), P = 7.2 × 10(-19) ). There was no significant difference in apoM concentration between subjects with HNF1A-MODY and Type 2 diabetes [0.89 (0.28), P = 0.13]. The C-statistic measure of discriminative accuracy for apoM was 0.91 for HNF1A-MODY vs. Type 1 diabetes, indicating high discriminative accuracy. The apoM/HDL ratio was significantly lower in HNF1A-MODY than other study groups. However, this ratio did not perform well in discriminating HNF1A-MODY from either Type 1 diabetes (C-statistic = 0.79) or Type 2 diabetes (C-statistic = 0.68). We confirm an earlier report that serum apoM levels are lower in HNF1A-MODY than in controls. Serum apoM provides good discrimination between HNF1A-MODY and Type 1 diabetes and warrants further investigation for clinical utility in diabetes diagnostics. © 2012 The Authors. Diabetic Medicine © 2012 Diabetes UK.

Root cause analysis for waste area grouping 1, Batch I, Series 1 Tank T-30 project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-08-01

Four inactive liquid low-level waste (LLLW) tanks were scheduled for remedial actions as the Batch L Series I Tank Project during fiscal year (FY) 1995. These tanks are 3001-B, 3004-B, T-30, and 3013. The initial tank remediation project was conducted as a maintenance action. One project objective was to gain experience in remediation efforts (under maintenance actions) to assist in conducting remedial action projects for the 33 remaining inactive LLLW tanks. Batch I, Series 1 project activities resulted in the successful remediation of tanks 3001-B, 3004-B, and 3013. Tank T-30 remedial actions were halted as a result of information obtained during waste characterization activities. The conditions discovered on tank T-30 would not allow completion of tank removal and smelting as originally planned. A decision was made to conduct a root cause analysis of Tank T-30 events to identify and, where possible, correct weaknesses that, if uncorrected, could result in similar delays for completion of future inactive tank remediation projects. The objective of the analysis was to determine why a portion of expected project end results for Tank T-30 were not fully achieved. The root cause analysis evaluates project events and recommends beneficial improvements for application to future projects. This report presents the results of the Batch I, Series root cause analysis results and makes recommendations based on that analysis

Tank safety screening data quality objective. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Hunt, J.W.

1995-04-27

The Tank Safety Screening Data Quality Objective (DQO) will be used to classify 149 single shell tanks and 28 double shell tanks containing high-level radioactive waste into safety categories for safety issues dealing with the presence of ferrocyanide, organics, flammable gases, and criticality. Decision rules used to classify a tank as ``safe`` or ``not safe`` are presented. Primary and secondary decision variables used for safety status classification are discussed. The number and type of samples required are presented. A tabular identification of each analyte to be measured to support the safety classification, the analytical method to be used, the type of sample, the decision threshold for each analyte that would, if violated, place the tank on the safety issue watch list, and the assumed (desired) analytical uncertainty are provided. This is a living document that should be evaluated for updates on a semiannual basis. Evaluation areas consist of: identification of tanks that have been added or deleted from the specific safety issue watch lists, changes in primary and secondary decision variables, changes in decision rules used for the safety status classification, and changes in analytical requirements. This document directly supports all safety issue specific DQOs and additional characterization DQO efforts associated with pretreatment and retrieval. Additionally, information obtained during implementation can assist in resolving assumptions for revised safety strategies, and in addition, obtaining information which will support the determination of error tolerances, confidence levels, and optimization schemes for later revised safety strategy documentation.

Tank 241-C-103 tank characterization plan. Revision 1

International Nuclear Information System (INIS)

Schreiber, R.D.

1995-01-01

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, and PNL 325 Analytical Chemistry Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples from tank 241-C-103

Tank 241-BY-110 vapor sampling and analysis tank characterization report

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

Tank BY-110 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-110 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-110 using the vapor sampling system (VSS) on November 11, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 27 C. Air from the Tank BY-110 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 12B, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, and Pacific Northwest Laboratories. The 40 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks that accompanied the samples

TANK VIBRATION LIMIT STUDY IN SUPPORT OF THE VADOSE ZONE DRILLING OPERATION [SEC 1 & 2

Energy Technology Data Exchange (ETDEWEB)

STURGES, M.H.

2005-01-18

The analysis contained herein supports the 0.1 g vibration limit that is currently established for the tanks. The natural frequency distributions and mode shapes for several different tank-soil models are presented. These frequencies can be compared to the natural frequencies from the measured test data. The best tank-soil model can then be selected for further study. This document is provided for historical information and has not been reviewed and checked beyond originator.

2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

International Nuclear Information System (INIS)

D. Shanklin

2006-01-01

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003

Toxic chemical considerations for tank farm releases. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Van Keuren, J.C.

1995-11-01

This document provides a method of determining the toxicological consequences of accidental releases from Hanford Tank Farms. A determination was made of the most restrictive toxic chemicals that are expected to be present in the tanks. Concentrations were estimated based on the maximum sample data for each analyte in all the tanks in the composite. Composite evaluated were liquids and solids from single shell tanks, double shell tanks, flammable gas watch list tanks, as well as all solids, all liquids, head space gases, and 241-C-106 solids. A sum of fractions of the health effects was computed for each composite for unit releases based emergency response planning guidelines (ERPGs). Where ERPGs were not available for chemical compounds of interest, surrogate guidelines were established. The calculation method in this report can be applied to actual release scenarios by multiplying the sum of fractions by the release rate for continuous releases, or the release amount for puff releases. Risk guidelines are met if the product is less than for equal to one.

Toxic chemical considerations for tank farm releases. Revision 1

International Nuclear Information System (INIS)

Van Keuren, J.C.

1995-11-01

This document provides a method of determining the toxicological consequences of accidental releases from Hanford Tank Farms. A determination was made of the most restrictive toxic chemicals that are expected to be present in the tanks. Concentrations were estimated based on the maximum sample data for each analyte in all the tanks in the composite. Composite evaluated were liquids and solids from single shell tanks, double shell tanks, flammable gas watch list tanks, as well as all solids, all liquids, head space gases, and 241-C-106 solids. A sum of fractions of the health effects was computed for each composite for unit releases based emergency response planning guidelines (ERPGs). Where ERPGs were not available for chemical compounds of interest, surrogate guidelines were established. The calculation method in this report can be applied to actual release scenarios by multiplying the sum of fractions by the release rate for continuous releases, or the release amount for puff releases. Risk guidelines are met if the product is less than for equal to one

Assessment of irradiation effects on beryllium reflector and heavy water tank of JRR-3M

Energy Technology Data Exchange (ETDEWEB)

Murayama, Yoji; Kakehuda, Kazuhiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-10-01

The JRR-3M, a swimming pool type research reactor with beryllium and heavy water reflectors, has been operated since 1990. Since the beryllium reflectors are close to fuel and receive high fast neutron fluence in a relatively short time, they may be subject to change their dimensions by swelling due mostly to entrapped helium gaseous. This may bend the reflectors to the outside and narrow gaps between the reflectors and the fuel elements. The gaps have been measured with an ultrasonic thickness gage in an annual inspection. The results in 1996 show that the maximum of expansion in the diametral directions was 0.6 mm against 1.6 mm of a managed value for replacement of the reflector. A heavy water tank of the JRR-3M is made of aluminum alloy A5052. Surveillance tests of the alloy have been conducted to evaluate irradiation effects of the heavy water tank. Five sets of specimens of the alloy have been irradiated in the beryllium reflectors where fast neutron flux is higher than that in the heavy water tank. In 1994, one set of specimens had been unloaded and carried out the post-irradiation tests. The results show that the heavy water tank preserved satisfactory mechanical properties. (author)

46 CFR 32.50-1 - Cargo pumps for tank vessels constructed on or after November 10, 1936-TB/ALL.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Cargo pumps for tank vessels constructed on or after... TANK VESSELS SPECIAL EQUIPMENT, MACHINERY, AND HULL REQUIREMENTS Pumps, Piping, and Hose for Cargo Handling § 32.50-1 Cargo pumps for tank vessels constructed on or after November 10, 1936—TB/ALL. On all...

Tank Characterization report for single-shell tank 241-SX-103

International Nuclear Information System (INIS)

WILMARTH, S.R.

1999-01-01

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-SX-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-103 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for fiscal year 1999'' (Adams et al. 1998)

Tank characterization report for single-shell tank 241-U-103

Energy Technology Data Exchange (ETDEWEB)

SASAKI, L.M.

1999-02-24

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-U-103. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-U-103 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with Waste Information Requirements Documents developed for 1998.''

Revised corrective action plan for underground storage tank 2331-U at the Building 9201-1 Site

International Nuclear Information System (INIS)

Bohrman, D.E.; Ingram, E.M.

1993-09-01

This document represents the Corrective Action Plan for underground storage tank (UST) 2331-U, previously located at Building 9201-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2331-U, a 560-gallon UST, was removed on December 14, 1988. This document presents a comprehensive summary of all environmental assessment investigations conducted at the Building 9201-1 Site and the corrective action measures proposed for remediation of subsurface petroleum product contamination identified at the site. This document is written in accordance with the regulatory requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-15-.06(7)

Preliminary characterization of abandoned septic tank systems. Volume 1

International Nuclear Information System (INIS)

1995-12-01

This report documents the activities and findings of the Phase I Preliminary Characterization of Abandoned Septic Tank Systems. The purpose of the preliminary characterization activity was to investigate the Tiger Team abandoned septic systems (tanks and associated leachfields) for the purpose of identifying waste streams for closure at a later date. The work performed was not to fully characterize or remediate the sites. The abandoned systems potentially received wastes or effluent from buildings which could have discharged non-domestic, petroleum hydrocarbons, hazardous, radioactive and/or mixed wastes. A total of 20 sites were investigated for the preliminary characterization of identified abandoned septic systems. Of the 20 sites, 19 were located and characterized through samples collected from each tank(s) and, where applicable, associated leachfields. The abandoned septic tank systems are located in Areas 5, 12, 15, 25, and 26 on the Nevada Test Site

Sampling and Analysis for Tank 241-AW-104 Waste in Support of Evaporator Campaign 2001-1

International Nuclear Information System (INIS)

MCKINNEY, S.G.

2000-01-01

This Tank Sampling and Analysis Plan (TSAP) identifies sample collection, laboratory analysis, quality assurance/quality control (QA/QC), and reporting objectives for the characterization of tank 241-AW-104 waste. Technical bases for these objectives are specified in the 242-A Evaporator Data Quality Objectives (Bowman 2000a and Von Bargen 1998), 242-A Evaporator Quality Assurance Project Plan (Bowman 1998 and Bowman 2000b), Tank 241-AW-104 Sampling Requirements in Support of Evaporator Campaign 2000-1 (Le 2000). Characterization results will be used to support the evaporator campaign currently planned for early fiscal year 2001. No other needs (or issues) requiring data for this tank waste apply to this sampling event

Thermocouple module halt failure acceptance test procedure for Tank 241-SY-101 DACS-1

International Nuclear Information System (INIS)

Ermi, A.M.

1997-01-01

The readiness of the Tank 241-SY-101 Data Acquisition and Control System (DACS-1) to provide monitoring and alarms for a halt failure of any thermocouple module will be tested during the performance of this procedure. Updated DACS-1 ''1/0 MODULE HEALTH STATUS'', ''MININ1'', and ''MININ2'' screens, which now provide indication of thermocouple module failure, will also be tested as part of this procedure

LARP1 functions as a molecular switch for mTORC1-mediated translation of an essential class of mRNAs.

Science.gov (United States)

Hong, Sungki; Freeberg, Mallory A; Han, Ting; Kamath, Avani; Yao, Yao; Fukuda, Tomoko; Suzuki, Tsukasa; Kim, John K; Inoki, Ken

2017-06-26

The RNA binding protein, LARP1, has been proposed to function downstream of mTORC1 to regulate the translation of 5'TOP mRNAs such as those encoding ribosome proteins (RP). However, the roles of LARP1 in the translation of 5'TOP mRNAs are controversial and its regulatory roles in mTORC1-mediated translation remain unclear. Here we show that LARP1 is a direct substrate of mTORC1 and Akt/S6K1. Deep sequencing of LARP1-bound mRNAs reveal that non-phosphorylated LARP1 interacts with both 5' and 3'UTRs of RP mRNAs and inhibits their translation. Importantly, phosphorylation of LARP1 by mTORC1 and Akt/S6K1 dissociates it from 5'UTRs and relieves its inhibitory activity on RP mRNA translation. Concomitantly, phosphorylated LARP1 scaffolds mTORC1 on the 3'UTRs of translationally-competent RP mRNAs to facilitate mTORC1-dependent induction of translation initiation. Thus, in response to cellular mTOR activity, LARP1 serves as a phosphorylation-sensitive molecular switch for turning off or on RP mRNA translation and subsequent ribosome biogenesis.

Tank characterization report for single-shell tank 241-T-105

International Nuclear Information System (INIS)

Field, J.G.

1998-01-01

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-T-105. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-T-105 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03, to ''issue characterization deliverables consistent with the waste information requirements documents developed for 1998''

Tank characterization report for single-shell tank 241-U-112

International Nuclear Information System (INIS)

Field, J.G.

1998-01-01

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-U-112. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-U-112 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendixes contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to issue characterization deliverables consistent with the Waste Information Requirements Document developed for 1998

Tank characterization report for single-shell tank 241-T-112

International Nuclear Information System (INIS)

McCain, D.J.

1998-01-01

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-T-112. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-T-112 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03, to ''issue characterization deliverables consistent with the Waste Information Requirements Documents developed for 1998.''

Tank characterization report for single-shell tank 241-T-105

Energy Technology Data Exchange (ETDEWEB)

Field, J.G.

1998-06-18

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-T-105. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-T-105 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03, to ``issue characterization deliverables consistent with the waste information requirements documents developed for 1998``.

Tank characterization report for single-shell tank 241-TX-104

International Nuclear Information System (INIS)

FIELD, J.G.

1999-01-01

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-TX-104. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-TX-104 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15c, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for FY 1999'' (Adams et al. 1998)

49 CFR 172.330 - Tank cars and multi-unit tank car tanks.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Tank cars and multi-unit tank car tanks. 172.330..., TRAINING REQUIREMENTS, AND SECURITY PLANS Marking § 172.330 Tank cars and multi-unit tank car tanks. (a... material— (1) In a tank car unless the following conditions are met: (i) The tank car must be marked on...

AT on Buried LPG Tanks Over 13 m3: An Innovative and Practical Solution

Science.gov (United States)

Di Fratta, Crescenzo; Ferraro, Antonio; Tscheliesnig, Peter; Lackner, Gerald; Correggia, Vincenzo; Altamura, Nicola

In Italy, since 2005, techniques based on Acoustic Emission have been introduced for testing of underground LPG tanks up to 13 m3, according to the European standard EN 12818:2004. The testing procedure for these tanks plans to install one or more pairs of sensors inside the "dome" suited for the access to the valves and fittings of the tank, directly on the accessible metal shell. This methodology is not applicable for the underground LPG buried tanks, where it is necessary to install a larger number of AE sensors, in order to cover at 100% the whole tank shell, even at very deep positions. Already in 2004, the European standard EN 12820 (Appendix C - Informative)give the possibility to use Acoustic Emission testing of LPG underground or buried tanks with a capacity exceeding 13 m3, but no technique was specified for the application. In 2008, TÜV AUSTRIA ITALIA - BLU SOLUTIONS srl - Italian company of TÜV AUSTRIA Group - has developed a technique to get access at tank shell, where tank capacity is greater than 13 m3 and its' diameter greater than 3,5 m. This methodology was fully in comply with the provisions of the European Standard EN 12819:2010, becoming an innovative solution widely appreciated and is used in Italy since this time. Currently, large companies and petrochemical plants, at the occurrence of the tank's requalification, have engaged TÜV AUSTRIA ITALIA - BLU SOLUTIONS to install such permanent predispositions, which allow access to the tank shell - test object - with diameters from 4 to 8 m. Through this access, you can install the AE sensors needed to cover at 100% the tank surface and then to perform AE test. In an economic crisis period, this technique is proving a valid and practically applicable answer, in order to reduce inspection costs and downtime by offering a technically advanced solution (AT), increasing the safety of the involved operators, protecting natural resources and the environment.

Final report for tank 241-AN-102, grab samples 2AN-95-1 through 2AN-95-6 and 102-AN-1 through 102-AN-4

International Nuclear Information System (INIS)

Esch, R.A.

1996-01-01

Ten grab samples (2AN-95-1, 2, 3, 4A, 5A; 102-AN-1, 2, 3(A), 3(B), and 4) and one field blank (2AN-95-6) were taken from tank 241-AN-102. In support of the safety screening program, total organic carbon and cyanide were performed as secondary analyses because the differential scanning calorimetry results exceeded the notification limit. These were compared to safety screening limits at a confidence level of 95%. Waste compatibility analyses were performed on the 3 supernate samples and the field blank from the latest sampling event. Results presented in the 45 day and in this report show that the waste in Tank 241-AN-1D2 has energetics greater than 480 J/g (dry) and total organic carbon > 3 wt%; however, with a moisture content > 17 wt%, the tank may be considered ''conditionally'' safe in accordance with the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue

Sloshing Simulation of Three Types Tank Ship on Pitching and Heaving Motion

Directory of Open Access Journals (Sweden)

Edi Djatmiko

2017-06-01

Full Text Available As an important part of a ship, tanker / cargo hold specifically designed to distribute the load to be maintained safely. In a related IMO classification of LNG carrier, there are a wide variety of types of LNG tanks on ships. Are generally divided into two types, namely tank (Independent Self Supporting Tank and (Non Self Supporting Tanks. The tank-type variation will affect the characteristics of fluid motion that is inside the tank. Need for simulation of sloshing and analysis of the structure of the tank due to the force created by the load when the heaving and pitching. Sloshing the effect of the free movement of the fluid in the tank with the striking motion wall tank walls that can damage the walls of the tank. Type 1 tank is a tank octagonal (octogonal for membrane-type LNG carrier with dimensions of length 38 m width 39.17 m 14.5 m high side of the tank. Type 2 tank is a tank-shaped capsule with the long dimension of 26.6 m and a diameter of 10.5 m. Type 3 tank is rectangular tank (rectanguler with dimensions of length of 49.68 m, width 46.92 and 32.23 m high. Simulations conducted using Computational Fluid Dynamic (CFD using ANSYS FLUENT software. From the simulation results concluded that the tank 1 to form (octogonal have a total pressure of 3013.99 Pa on the front wall with a height of 13.65 m from the base of the tank

ApolipoproteinA1-75 G/A (M1- polymorphism and Lipoprotein(a; Anti- vs. Pro-Atherogenic properties

Directory of Open Access Journals (Sweden)

Ranganath L

2007-08-01

Full Text Available Abstract Background ApolipoproteinA1(apoA1 is the major apoprotein constituent of high-density-lipoprotein(HDL. The relationship of apoA1 -75 bp(M1- allele polymorphism with lipoprotein phenotype and cardiovascular diseae (CVD remain unclear. Overnight fasting blood samples were collected from a cohort of high-risk Omani population, 90 non-diabetic subjects and 149 type 2 diabetes mellitus (T2DM subjects for genotype and phenotype studies. Results The M1+ and M1- alleles frequencies were 0.808 and 0.192 for M1+ and M1-, respectively, comparable to the frequency of apoA1 (M1+ and M1- amongst a healthy Omani population, 0.788 and 0.212, respectively. The frequencies of the hetero- and homozygous subjects for the MspI polymorphism at -75 (M1- of the apoA1 gene were in Hardy-Weinberg equilibrium. The mean Lp(a concentration was significantly higher(P = 0.02 in subjects carrying M1- allele compared to M1+ allele of the APOA1 gene with an odd ratio of 2.3(95% CI, 1.13–14.3, irrespective of gender and the diabetic status. Conclusion ApolipoproteinA1-75 G/A (M1- polymorphism is relatively common and is positively associated with Lp(a and therefore, may confer a potential risk for cardiovascular disease (CVD.

The WA105-3x1x1 m3 dual phase LAr-TPC demonstrator

CERN Document Server

Murphy, Sebastien

2016-11-15

The dual phase Liquid Argon Time Projection Chamber (LAr TPC) is the state-of-art technology for neutrino detection thanks to its superb 3D tracking and calorimetry performance. Its main feature is the charge amplification in gas argon which provides excellent signal-to-noise ratio. Electrons produced in the liquid argon are extracted in the gas phase. Here, a readout plane based on Large Electron Multiplier detectors provides amplification of the charges before its collection onto an anode with strip readout. The charge amplification enables constructing fully homoge- nous giant LAr-TPCs with tuneable gain, excellent charge imaging performance and increased sensitivity to low energy events. Following a staged approach the WA105 collaboration is con- structing a dual phase LAr-TPC with an active volume of 3x1x1m3 that will soon be tested with cosmic rays. Its construction and operation aims to test scalable solutions for the crucial aspects of this technology: ultra high argon purity in non-evacuable tank, la...

Tank waste remediation system retrieval and disposal mission phase 1 financial analysis

International Nuclear Information System (INIS)

Wells, M.W.

1998-01-01

The purpose of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Phase 1 Financial Analysis is to provide a quantitative and qualitative cost and schedule risk analysis of HNF-1946, Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (Swita et al. 1998). The Updated Baseline (Section 3.0) is compared to the current TWRS Project Multi-Year Work Plan (MYWP) for fiscal year (FY) 1998 and target budgets for FY 1999 through FY 2011 (Section 4.1). The analysis then evaluates the executability of HNF-1946 (Sections 4.2 through 4.5) and recommends a path forward for risk mitigation (Sections 4.6, 4.7, and 5.0). A sound systems engineering approach was applied to understand and analyze the Phase 1B Retrieval and Disposal mission. Program and Level 1 Logics were decomposed to Level 8 of the Work Breakdown Structure (WBS) where logic was detailed, scope was defined, detail durations and estimates prepared, and resource loaded schedules developed. Technical Basis Review (TBR) packages were prepared which include this information and, in addition, defined the enabling assumptions for each task, and the risks associated with performance. This process is discussed in Section 2.1. Detailed reviews at the subactivity within the Level 1 Logic TBR levels were conducted to provide the recommended solution to the Phase 1B Retrieval and Disposal Mission. Independent cost analysis and risk assessments were performed by members of the Lockheed Martin Hanford Corporation (LMHC) Business Management and Chief Financial Officer organization along with specialists in risk analysis from TRW, Inc. and Lockheed Martin Energy Systems. The process evaluated technical, schedule, and cost risk by category (program specific fixed and variable, integrated program, and programmatic) based on risk certainly from high probability well defined to very low probability that is not bounded or priceable as discussed in Section 2.2. The results have been

Technical Note: Direct measurement of continuous TMR data with a 1D tank and automated couch movements.

Science.gov (United States)

Knutson, Nels C; Schmidt, Matthew C; Belley, Matthew D; Nguyen, Ngoc B; Li, H Harold; Sajo, Erno; Price, Michael J

2017-07-01

Real-time dynamic control of the linear accelerator, couch, and imaging parameters during radiation delivery was investigated as a novel technique for acquiring tissue maximum ratio (TMR) data. TrueBeam Developer Mode (Varian Medical Systems, Palo Alto, CA, USA) was used to control the linear accelerator using the Extensible Markup Language (XML). A single XML file was used to dynamically manipulate the machine, couch, and imaging parameters during radiation delivery. A TG-51 compliant 1D water tank was placed on the treatment couch, and used to position a detector at isocenter at a depth of 24.5 cm. A depth scan was performed towards the water surface. Via XML control, the treatment couch vertical position was simultaneously lowered at the same rate, maintaining the detector position at isocenter, allowing for the collection of TMR data. To ensure the detector remained at isocenter during the delivery, the in-room camera was used to monitor the detector. Continuous kV fluoroscopic images during 10 test runs further confirmed this result. TMR data at multiple Source to Detector Distances (SDD) and scan speeds were acquired to investigate their impact on the TMR data. Percentage depth dose (PDD) scans (for conversion to TMR) along with traditional discrete TMR data were acquired as a standard for comparison. More than 99.8% of the measured points had a gamma value (1%/1 mm) < 1 when compared with discrete or PDD converted TMR data. Fluoroscopic images showed that the concurrent couch and tank movements resulted in SDD errors < 1 mm. TMRs acquired at SDDs of 99, 100, and 101 cm showed differences less than 0.004. TrueBeam Developer Mode was used to collect continuous TMR data with the same accuracy as traditionally collected discrete data, but yielded higher sampled resolution and reduced acquisition time. This novel method does not require the modification of any equipment and does not use a 3D tank or reservoir. © 2017 American Association of Physicists in

Tank-Binding Kinase 1 (TBK1) Gene and Open-Angle Glaucomas (An American Ophthalmological Society Thesis).

Science.gov (United States)

Fingert, John H; Robin, Alan L; Scheetz, Todd E; Kwon, Young H; Liebmann, Jeffrey M; Ritch, Robert; Alward, Wallace L M

2016-08-01

To investigate the role of TANK-binding kinase 1 ( TBK1 ) gene copy-number variations (ie, gene duplications and triplications) in the pathophysiology of various open-angle glaucomas. In previous studies, we discovered that copy-number variations in the TBK1 gene are associated with normal-tension glaucoma. Here, we investigated the prevalence of copy-number variations in cohorts of patients with other open-angle glaucomas-juvenile-onset open-angle glaucoma (n=30), pigmentary glaucoma (n=209), exfoliation glaucoma (n=225), and steroid-induced glaucoma (n=79)-using a quantitative polymerase chain reaction assay. No TBK1 gene copy-number variations were detected in patients with juvenile-onset open-angle glaucoma, pigmentary glaucoma, or steroid-induced glaucoma. A TBK1 gene duplication was detected in one (0.44%) of the 225 exfoliation glaucoma patients. TBK1 gene copy-number variations (gene duplications and triplications) have been previously associated with normal-tension glaucoma. An exploration of other open-angle glaucomas detected a TBK1 copy-number variation in a patient with exfoliation glaucoma, which is the first example of a TBK1 mutation in a glaucoma patient with a diagnosis other than normal-tension glaucoma. A broader phenotypic range may be associated with TBK1 copy-number variations, although mutations in this gene are most often detected in patients with normal-tension glaucoma.

111-B Metal Examination Facility Concrete Tanks Characterization Plan

International Nuclear Information System (INIS)

Encke, D.B.

1997-08-01

The 111-B Metal Examination Facility was a single-story, wood frame 'L'-shaped building built on a concrete floor slab. The facility served as a fuel failure inspection facility. Irradiated fuel pieces were stored and examined in two below grade concrete storage tanks filled with water. The tanks have been filled with grout to stabilize the contamination they contained, and overall dimensions are 5 ft 9 in. (1.5 m 22.8 cm ) wide, 9 ft 1 in. (2.7 m 2.54 cm ) deep, and 10 ft 8 in. (3.0 m 20.32 cm) long, and are estimated to weigh 39 tons. The tanks were used to store and examine failed fuel rods, using water as a radiation shield. The tanks were lined with stainless steel; however, drawings show the liner has been removed from at least one tank (south tank) and was partially filled with grout. The south tank was used to contain the Sample Storage Facility, a multi-level metal storage rack for failed nuclear fuel rods (shown in drawings H-1-2889 and -2890). Both tanks were completely grouted sometime before decontamination and demolition (D ampersand D) of the above ground facility in 1984. The 111-B Metal Examination Facility contained two concrete tanks located below floor level for storage and examination of failed fuel. The tanks were filled with concrete as part of decommissioning the facility prior to 1983 (see Appendix A for description of previous work). Funding for removal and disposal of the tanks ran out before they could be properly disposed

Development of a remote tank inspection robotic system

International Nuclear Information System (INIS)

Knape, B.P.; Bares, L.C.

1990-01-01

RedZone Robotics is currently developing a remote tank inspection (RTI) robotic system for Westinghouse Idaho Nuclear Company (WINCO). WINCO intends to use the RTI robotic system at the Idaho Chemical Processing Plant, a facility that contains a tank farm of several 1,135,500-ell (300,000-gal), 15.2-m (50-ft)-diam, high-level liquid waste storage tanks. The primary purpose of the RTI robotic system is to inspect the interior of these tanks for corrosion that may have been caused by the combined effects of radiation, high temperature, and caustic by the combined effects of radiation, high temperature, and caustic chemicals present inside the tanks. The RTI robotic system features a vertical deployment unit, a robotic arm, and a remote control console and computer [located up to 30.5 m (100 ft) away from the tank site]. All actuators are high torque, electric dc brush motors that are servocontrolled with absolute position feedback. The control system uses RedZone's standardized intelligent controller for enhanced telerobotics, which provides a high speed, multitasking environment on a VME bus. Currently, the robot is controlled in a manual, job-button, control mode; however, control capability is available to develop preprogrammed, automated modes of operation

Tank 21 and Tank 24 Blend and Feed Study: Blending Times, Settling Times, and Transfers

International Nuclear Information System (INIS)

Lee, S.; Leishear, R.; Poirier, M.

2012-01-01

The Salt Disposition Integration (SDI) portfolio of projects provides the infrastructure within existing Liquid Waste facilities to support the startup and long term operation of the Salt Waste Processing Facility (SWPF). Within SDI, the Blend and Feed Project will equip existing waste tanks in the Tank Farms to serve as Blend Tanks where salt solutions of up to 1.2 million gallons will be blended in 1.3 million gallon tanks and qualified for use as feedstock for SWPF. In particular, Tanks 21 and 24 are planned to be used for blending and transferring to the SDI feed tank. These tanks were evaluated here to determine blending times, to determine a range of settling times for disturbed sludge, and to determine that the SWPF Waste Acceptance Criteria that less than 1200 mg/liter of solids will be entrained in salt solutions during transfers from the Tank 21 and Tank 24 will be met. Overall conclusions for Tank 21 and Tank 24 operations include: (1) Experimental correction factors were applied to CFD (computational fluid dynamics) models to establish blending times between approximately two and five hours. As shown in Phase 2 research, blending times may be as much as ten times greater, or more, if lighter fluids are added to heavier fluids (i.e., water added to salt solution). As the densities of two salt solutions converge this effect may be minimized, but additional confirmatory research was not performed. (2) At the current sludge levels and the presently planned operating heights of the transfer pumps, solids entrainment will be less than 1200 mg/liter, assuming a conservative, slow settling sludge simulant. (3) Based on theoretical calculations, particles in the density range of 2.5 to 5.0 g/mL must be greater than 2-4 (micro)m in diameter to ensure they settle adequately in 30-60 days to meet the SWPF feed criterion ( 60 days) settling times in Tank 21.

Internal (m=1, n=1) and (m=2, n=1) resistive modes in the toroidal tokamak with circular cross-section

International Nuclear Information System (INIS)

Bussac, M.N.; Pellat, R.; Edery, D.; Soule, J.L.

1977-01-01

A linear analysis is presented of the toroidal coupling between the internal resistive modes (m=1, n=1) and (m=2, n=1) in the tokamak with circular cross-section. The resistive and diamagnetic effects are included in the singular layers where the safety factor q takes respectively the values one and two. By expanding the MHD equations in powers of epsilon, the local inverse of the aspect ratio, a system of two coupled equations is obtained for the harmonic amplitudes. When the shear is finite on q=1 the toroidal coupling is negligible. In the opposite limit, one can explain (a) the experimental behaviour of the (m=1, n=1) mode before the internal disruption, and (b) the simultaneous observation of the modes (m=1, n=1) and (m=2, n=1) before the main disruption. (author)

A field study of virus removal in septic tank drainfields.

Science.gov (United States)

Nicosia, L A; Rose, J B; Stark, L; Stewart, M T

2001-01-01

Two field studies were conducted at a research station in Tampa, Florida to assess the removal of bacteriophage PRD1 from wastewater in septic tank drainfields. Infiltration cells were seeded with PRD1 and bromide and the effects of effluent hydraulic loading rate and rainfall on virus removal were monitored. Septic tank effluent samples were collected after passage through 0.6 m of unsaturated fine sand and PRD1 was detected over an average of 67 d. Bacteriophage PRD1 breakthrough was detected at approximately the same time as bromide in all three cells except for the low-load cell (Study 1), where bromide was never detected. Log10 removals of PRD1 were 1.43 and 1.91 for the high-load cells (hydraulic loading rate = 0.063 m/d) and 2.21 for the low-load cell (hydraulic loading rate = 0.032 m/d). Virus attenuation is attributed to dispersion, dilution, and inactivation. Significant increases in PRD1 elution with rainfall were observed in the first 10 d of the study. Approximately 125 mm of rainfall caused a 1.2 log10 increase of PRD1 detected at the 0.6-m depth. Current Florida onsite wastewater disposal standards, which specify a 0.6-m distance from the drainfield to the water table, may not provide sufficient removal of viruses, particularly during the wet season.

241-AY/AZ waste storage tanks: Supplemental gravity load analysis. Volume 1

International Nuclear Information System (INIS)

Baliga, R.

1994-01-01

An analysis of the 241SY tanks performed by ADVENT(1994b) to resolve dome overload issues indicated that the tank can sustain the dome loads resulting from additional soil overburden depth, increased soil density, and increased concentrated load. Similar issues exist for the 241AY/AZ tanks and therefore, an interim analysis of the 241AY/AZ tanks is presented herein. The scope of this effort is to review and compare all design drawings pertaining to the 241AY and 241AZ tanks with those pertaining to the 241SY tanks; to modify the axisymmetric model of the 241SY tanks to represent the 241AY/AZ tanks; and to evaluate the effect of additional dome load on the 241AY/AZ tanks by performing a structural analysis for gravity loads (dead load + live load). ADVENTS's additional scope of work is to perform a qualitative evaluation of the 241AY/AZ tanks for seismic and thermal loadings (Vollert 1982 and Blume 1971). This qualitative evaluation does not include any detailed finite element analysis of the tanks. The following design-based gravity loading conditions are used in this interim analysis of the 241AY/AZ tanks to determine a baseline for the tank stresses or section loads

Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Volume 1

International Nuclear Information System (INIS)

1995-09-01

The 1995 Hanford Mission Plan specifically addresses the tank waste issue and clarifies the link with other initiatives, such as improving management practices and the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE/RL-91-31). This document captures the results of decision making regarding the application of systems engineering at the Hanford Site, external involvement policy, and site end-state goals. Section 3.5 of the Hanford Mission Plan on Decisions and Directives provides an integrating discussion of the actions of the National Environmental Policy Act (NEPA), and DOE policy, guidance, and decisions associated with binding agreements such as the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). Two significant components of the Hanford Mission Plan 1994 planning basis are (1) the decisions regarding the disposition of onsite material inventory, and the key programs and interfaces to accomplish this; and (2) the Program Interface Issues section, which identified issues that stretch across program boundaries

Current Status of TRR-1/M1

International Nuclear Information System (INIS)

Sittichai, Chaiyut

2000-01-01

In 1961, the first Thai Research Reactor, TRR-1, having power of 1 MW was established. It was located at Office of Atomic Energy for Peace (OAEP) in Bangkok. TRR-1 was completely commissioned in June 1962. Plate typed high-enriched uranium (HEU) and U 3 O 8 -Al were used as fuel. Light water used as moderator and coolant. During 1975-1977, TRR-1 was shut down for modification. The reactor core and control system were disassembled and replaced by TRIGA Mark III. It is a circular hexagonal core typed reactor designed by General Atomics Company (GA). Afterwards, TRR-1 was officially renamed to Thai Research Reactor 1/Modification 1 (TRR-1/M1). TRR-1/M1 is a multipurpose reactor with nominal power of 2 MW. This swimming pool typed reactor uses low-enriched uranium (LEU) as fuel and light water as coolant and moderator. To date, the reactor has been operated with core No.12 that released power 1135 MWD to serve the user. The reactor has been serving for various kinds of utilization, for example, to produce radioisotope, neutron beam experiments and reactor physics experiments. This report explains in detail regarding operational experience and current status of this reactor, for example, reactor operation and reactor utilization. (author)

Tank Farm Contractor Operation and Utilization Plan [SEC 1 Thru 3

Energy Technology Data Exchange (ETDEWEB)

KIRKBRIDE, R.A.

1999-05-04

The Tank Waste Remediation System Operation and Utilization Plan updates the operating scenario and plans for the delivery of feed to BNFL Inc., retrieval of waste from single-shell tanks, and the overall process flowsheets for Phases I and II of the privatization of the Tank Waste Remediation System. The plans and flowsheets are updated with the most recent tank-by-tank inventory and sludge washing data. Sensitivity cases were run to evaluate the impact or benefits of proposed changes to the BNFL Inc. contract and to evaluate a risk-based SST retrieval strategy.

M1 muscarinic receptor facilitates cognitive function by interplay with AMPA receptor GluA1 subunit.

Science.gov (United States)

Zhao, Lan-Xue; Ge, Yan-Hui; Xiong, Cai-Hong; Tang, Ling; Yan, Ying-Hui; Law, Ping-Yee; Qiu, Yu; Chen, Hong-Zhuan

2018-03-06

M1 muscarinic acetylcholine receptors (M1 mAChRs) are the most abundant muscarinic receptors in the hippocampus and have been shown to have procognitive effects. AMPA receptors (AMPARs), an important subtype of ionotropic glutamate receptors, are key components in neurocognitive networks. However, the role of AMPARs in procognitive effects of M1 mAChRs and how M1 mAChRs affect the function of AMPARs remain poorly understood. Here, we found that basal expression of GluA1, a subunit of AMPARs, and its phosphorylation at Ser845 were maintained by M1 mAChR activity. Activation of M1 mAChRs promoted membrane insertion of GluA1, especially to postsynaptic densities. Impairment of hippocampus-dependent learning and memory by antagonism of M1 mAChRs paralleled the reduction of GluA1 expression, and improvement of learning and memory by activation of M1 mAChRs was accompanied by the synaptic insertion of GluA1 and its increased phosphorylation at Ser845. Furthermore, abrogation of phosphorylation of Ser845 residue of GluA1 ablated M1 mAChR-mediated improvement of learning and memory. Taken together, these results show a functional correlation of M1 mAChRs and GluA1 and the essential role of GluA1 in M1 mAChR-mediated cognitive improvement.-Zhao, L.-X., Ge, Y.-H., Xiong, C.-H., Tang, L., Yan, Y.-H., Law, P.-Y., Qiu, Y., Chen, H.-Z. M1 muscarinic receptor facilitates cognitive function by interplay with AMPA receptor GluA1 subunit.

Characterization of the C1 and C2 waste tanks located in the BVEST system at ORNL

International Nuclear Information System (INIS)

Keller, J.M.; Giaquinto, J.M.

1998-02-01

There was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report discusses the analytical characterization data for the supernatant and sludge in the BVEST waste tanks C-1 and C-2. The isotopic data presented in this report supports the position that fissile isotopes of uranium ( 233 U and 235 U) and plutonium ( 239 Pu and 241 Pu) were denatured as required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). In general, the sludge in tanks C1 and C2 was found to be hazardous based on RCRA characteristics and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. Additional characteristics of the C1 and C2 sludge inventory relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP

Status report on resolution of Waste Tank Safety Issues at the Hanford Site. Revision 1

International Nuclear Information System (INIS)

Dukelow, G.T.; Hanson, G.A.

1995-05-01

The purpose of this report is to provide and update the status of activities supporting the resolution of waste tank safety issues and system deficiencies at the Hanford Site. This report provides: (1) background information on safety issues and system deficiencies; (2) a description of the Tank Waste Remediation System and the process for managing safety issues and system deficiencies; (3) changes in safety issue description, prioritization, and schedules; and (4) a summary of the status, plans, order of magnitude, cost, and schedule for resolving safety issues and system deficiencies

Internal (m=1, n=1) and (m=2, n=1) resistive modes in the toroidal Tokomak with circular cross sections

International Nuclear Information System (INIS)

Bussac, M.N.; Pellat, R.; Edery, D.; Soule, J.L.

1976-01-01

A linear analysis is presented of the toroidal coupling between the internal resistive modes (m=1, n=1) and (m=2, n=1) in the Tokomak with circular cross sections. One includes the resistive and diamagnetic effects in the singular layers where the safety factor q takes respectively the values one and two. By expanding the MHD equations in powers of epsilon, the local inverse of the aspect ratio, one obtains a system of two coupled equations for the harmonic amplitudes. When the shear is finite on q=1, the toroidal coupling is negligible. In the opposite limit, one can explain: the experimental behaviour of the (m=1, n=1) mode before the internal disruption; the simultaneous observation of the modes (m=1, n=1) and [de

Single-channel ground airborne radio system (SINCGARS) based remote control for the M1 Abrahms

Science.gov (United States)

Urda, Joseph R.

1995-04-01

Remote control of the Ml Abrahms Main Battle Tank through a minefield breach operation will remove the vehicle crew from the inherent hazard. A successful remote control system will provide automotive control yet not impair normal operation. This requires a minimum of physical parts, and an unobtrusive installation. Most importantly, a system failure must not impair the regular operation as a manned system. The system itself need not be complex. A minefield breach only requires simple control of automotive function and a mine plow interface. Control hardware for the Ml-Al can be reduced to two linear actuators, an electrical interface for the engine control unit, an interface for the mine plow, and the associated cables. Communication between vehicle control and operator control takes place over the vehicles organic radio (typically SINCGARS). This helps reduce the number of special purpose components for the remote control device. The device is currently awaiting an automotive safety test to prepare for its safety release. Because of the specific nature of the MDL-STD 1553-B data bus the device will not control an M1-A2 Main Battle Tank. The architecture will allow control of the M1-A2 through the 1553-B data bus however the physical hardware has not been constructed. The control scheme will not change. The communication interface will provide greater flexibility when interfacing to the vehicle tactical radio. Operational utility will be determined by U.S. Army Training and Doctrine Command personnel. The obvious benefit is that if a remote tank is lost during a minefield breach the crew is saved.

Tank characterization report for double-shell tank 241-AP-105

International Nuclear Information System (INIS)

DeLorenzo, D.S.; Simpson, B.C.

1994-01-01

Double-Shell Tank 241-AP-105 is a radioactive waste tank most recently sampled in March of 1993. Sampling and characterization of the waste in Tank 241-AP-105 contributes toward the fulfillment of Milestone M-44-05 of the Hanford Federal Facility Agreement and Consent Order (Ecology, EPA, and DOE, 1993). Characterization is also needed tot evaluate the waste's fitness for safe processing through an evaporator as part of an overall waste volume reduction program. Tank 241-AP-105, located in the 200 East Area AP Tank Farm, was constructed and went into service in 1986 as a dilute waste receiver tank; Tank 241AP-1 05 was considered as a candidate tank for the Grout Treatment Facility. With the cancellation of the Grout Program, the final disposal of the waste in will be as high- and low-level glass fractions. The tank has an operational capacity of 1,140,000 gallons, and currently contains 821,000 gallons of double-shell slurry feed. The waste is heterogeneous, although distinct layers do not exist. Waste has been removed periodically for processing and concentration through the 242-A Evaporator. The tank is not classified as a Watch List tank and is considered to be sound. There are no Unreviewed Safety Questions associated with Tank 241-AP-105 at this time. The waste in Tank 241-AP-105 exists as an aqueous solution of metallic salts and radionuclides, with limited amounts of organic complexants. The most prevalent soluble analytes include aluminum, potassium, sodium, hydroxide, carbonate, nitrate, and nitrite. The calculated pH is greater than the Resource Conservation and Recovery Act established limit of 12.5 for corrosivity. In addition, cadmium, chromium, and lead concentrations were found at levels greater than their regulatory thresholds. The major radionuclide constituent is 137 Cs, while the few organic complexants present include glycolate and oxalate. Approximately 60% of the waste by weight is water

Tank waste source term inventory validation. Volume 1. Letter report

International Nuclear Information System (INIS)

Brevick, C.H.; Gaddis, L.A.; Johnson, E.D.

1995-01-01

The sample data for selection of 11 radionuclides and 24 chemical analytes were extracted from six separate sample data sets, were arranged in a tabular format and were plotted on scatter plots for all of the 149 single-shell tanks, the 24 double-shell tanks and the four aging waste tanks. The solid and liquid sample data was placed in separate tables and plots. The sample data and plots were compiled from the following data sets: characterization raw sample data, recent core samples, D. Braun data base, Wastren (Van Vleet) data base, TRAC and HTCE inventories. This document is Volume I of the Letter Report entitled Tank Waste Source Term Inventory Validation

A time-variant analysis of the 1/f^(2) phase noise in CMOS parallel LC-Tank quadrature oscillators

DEFF Research Database (Denmark)

Andreani, Pietro

2006-01-01

This paper presents a study of 1/f2 phase noise in quadrature oscillators built by connecting two differential LC-tank oscillators in a parallel fashion. The analysis clearly demonstrates the necessity of adopting a time-variant theory of phase noise, where a more simplistic, time...

Rac1 Regulates the Activity of mTORC1 and mTORC2 and Controls Cellular Size

Science.gov (United States)

Saci, Abdelhafid; Cantley, Lewis C.; Carpenter, Christopher L.

2013-01-01

SUMMARY Mammalian target of rapamycin (mTOR) is a serine/threonine kinase that exists in two separate complexes, mTORC1 and mTORC2, that function to control cell size and growth in response to growth factors, nutrients, and cellular energy levels. Low molecular weight GTP-binding proteins of the Rheb and Rag families are key regulators of the mTORC1 complex, but regulation of mTORC2 is poorly understood. Here, we report that Rac1, a member of the Rho family of GTPases, is a critical regulator of both mTORC1 and mTORC2 in response to growth-factor stimulation. Deletion of Rac1 in primary cells using an inducible-Cre/Lox approach inhibits basal and growth-factor activation of both mTORC1 and mTORC2. Rac1 appears to bind directly to mTOR and to mediate mTORC1 and mTORC2 localization at specific membranes. Binding of Rac1 to mTOR does not depend on the GTP-bound state of Rac1, but on the integrity of its C-terminal domain. This function of Rac1 provides a means to regulate mTORC1 and mTORC2 simultaneously. PMID:21474067

Tank 241-TX-302C grab samples 302C-TX-97-1A through 302C-TX-97-3B analytical results for the final report

Energy Technology Data Exchange (ETDEWEB)

Esch, R.A.

1998-03-12

This document is the final report for tank 241-TX-302C grab samples. Six grabs samples (302C-TX-97-1A, 302C-TX-97-1B, 302C-TX-97-2A, 302C-TX-97-2B, 302C-TX-97-3A, and 302C-TX-97-3B) were collected from the catch tank level gauge riser on December 19, 1997. The ``A`` and ``B`` portions from each sample location were composited and analyses were performed on the composites in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Miller, 1997). The analytical results are presented in Table 1. No notification limits were exceeded. Appearance and Sample Handling Attachment 1 is provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed. Table 2 provides the appearance information.

Tank 241-TX-302C grab samples, 302C-TX-97-1A through 302C-TX-97-3B analytical results for the final report

International Nuclear Information System (INIS)

Esch, R.A.

1998-01-01

This document is the final report for tank 241-TX-302C grab samples. Six grabs samples (302C-TX-97-1A, 302C-TX-97-1B, 302C-TX-97-2A, 302C-TX-97-2B, 302C-TX-97-3A, and 302C-TX-97-3B) were collected from the catch tank level gauge riser on December 19, 1997. The ''A'' and ''B'' portions from each sample location were composited and analyses were performed on the composites in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Miller, 1997). The analytical results are presented in Table 1. No notification limits were exceeded. Appearance and Sample Handling Attachment 1 is provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed. Table 2 provides the appearance information

Final report for Tank 241-B-101, push mode cores 90 and 91. Revision 1

International Nuclear Information System (INIS)

Schreiber, R.D.

1995-11-01

This is the final report for tank 241-at sign 101, cores 90 and 91. Samples from these cores were analyzed for safety screening purposes in accordance with the Tank 241-B-101 Tank Characterization Plan (TCP) (Reference 1). This final report contains the results for three sets of TGA and gravimetric analyses performed after the 90-day report was issued. Two of these TGA/gravimetric percent water sets of analyses were done because low original TGA results were obtained for the lower half segment of core 90, segment 2 and the facie of core 91, segment 2; the third set of analyses were performed because the TGA and gravimetric percent water results for the upper half segment of core 90, segment 2 differed by approximately a factor of three and further investigation was warranted

Multi-Function Waste Tank Facility phase out basis. Revision 1

International Nuclear Information System (INIS)

Awadalla, N.G.

1995-01-01

Additional double-shell tank storage capacity is not needed until FY 2004 or later. The waste volume in the current baseline program can be managed within the existing tank capacity. However, this requires implementation of some risk management actions and significant investment in software and hardware to accomplish the actions necessary to maximize use of existing storage tank space.''

Destruction of Ion-Exchange Resin In Waste From the HFIR, T1 and T2 Tanks Using Fenton's Reagent

International Nuclear Information System (INIS)

Taylor, P.A.

2002-01-01

The use of Fenton's reagent (hydrogen peroxide and a ferrous iron catalyst) has been tested as a method for destroying ion-exchange resin in radioactive waste from three underground storage tanks at the Oak Ridge National Laboratory. The resin in these wastes must be destroyed before they can be transferred to the Melton Valley Storage Tanks (MVSTs) prior to solidification and disposal at the Waste Isolation Pilot Plant. The reaction with ion-exchange resin requires a dilute acidic solution (pH = 3 to 5) and moderate temperatures (T = 60 to 100 C). Laboratory-scale tests of the process have been successfully completed using both simulants and actual waste samples. The ion-exchange resin is oxidized to carbon dioxide and inorganic salts. The reaction rate is quite slow for temperatures below 70 C but increases almost linearly as the temperature of the slurry increases from 70 to 90 C. Pilot-scale tests have demonstrated the process using larger samples of actual waste slurries. A sample from the High Flux Isotope Reactor (HFIR) tank, containing 500 mL of settled solids (resin and inorganic sludge) in a total volume of 1800 mL, was successfully treated to meet MVST waste acceptance requirements in 9 h of processing time, using 1650 mL of 50 wt% hydrogen peroxide. A composite sample from the T1 and T2 tanks, which contained 1000 mL of settled solids in a total volume of 2000 mL required 8 h of treatment, using 1540 mL of 50 wt% peroxide, to meet waste acceptance requirements. Hydrogen peroxide reaction rates were 0.71 to 0.74 g H 2 O 2 /L/min, with very low (<2000 mg/L) concentrations of peroxide in the slurry. The reaction produces mostly carbon dioxide gas during the early part of the treatment, when organic carbon concentrations in the slurry are high, and then produces increasing amounts of oxygen as the organic carbon concentration drops. Small amounts (<3 vol%) of carbon monoxide are also generated. The off-gas from the pilot-scale tests, which was 81 vol

Levitating Drop in a Tilted Rotating Tank - Gallery of Fluid Motion Entry V044

OpenAIRE

White, Andrew; Swan, David; Ward, Thomas

2011-01-01

A cylindrical acrylic tank with inner diameter D = 4 in. is mounted such that its axis of symmetry is at some angle measured from the vertical plane. The mixing tank is identical to that described in [1] The tank is filled with 200 mL of 1000 cSt silicone oil and a 5 mL drop of de-ionized water is placed in the oil volume. The water drop is allowed to come to rest and then a motor rotates the tank about its axis of symmetry at a fixed frequency = 0.3 Hz. Therefore the Reynolds number is fixed...

The effect of dilution on the gas-retention behavior of Tank 241-SY-101 waste

International Nuclear Information System (INIS)

Bredt, P.R.; Tingey, S.M.; Shade, E.H.

1995-09-01

The effect of dilution on gas retention in waste from Tank 241-SY-101 was investigated. A composite sample was prepared from material collected during the Window ''C'' and Window ''E'' sampling events. The composite contained material from both the convective and nonconvective layer in the proportions existing in the tank. Operation of the mixer pump in Tank 241-SY-101 has homogenized the tank material, and dilution of the current waste would require additional mixing; therefore, no attempt was made to use unhomogenized tank waste to prepare the composite. The composite was diluted with 2 M NaOH at ratios of 0.5:1, 0.75: 1, 1:1, and 3:1 per volume (2 M NaOH:tank waste)

M.A. Streicher findings regarding high-level waste tank corrosion issues

International Nuclear Information System (INIS)

Husa, E.I.

1994-01-01

Dr. Michael A. Streicher is a nationally recognized metallurgist and corrosion scientist. He has served on the Department of Energy, Headquarters Tank Structural Integrity panel as the primary corrosion technical expert since the panel's inception in October 1991. Attachments 3 through 13 are Dr. Streicher's correspondence and presentations to the panel between November 1991 and May 1994. This compilation addresses Dr. Streicher's findings on High-Level Waste tank corrosion issues such as: corrosion mechanisms in carbon steels; hydrogen generation from waste tank corrosion; stress corrosion cracking in carbon steel tanks; water line attack in Hanford's single-shell tanks; stress corrosion cracking of austenitic stainless steels; and materials selection for new Hanford waste tanks. These papers discuss both generic and specific corrosion issues associated with waste tanks and transfer systems at Hanford, Savannah River, Idaho National Engineering Laboratory, and West Valley Demonstration Project

Tank 241-C-107 tank characterization plan

International Nuclear Information System (INIS)

Schreiber, R.D.

1995-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) has advised the US Department of Energy (DOE) to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The data quality objective (DQO) process was chosen as a tool to be used to identify sampling and analytical needs for the resolution of safety issues. As a result, a revision in the Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) milestone M-44-00 has been made, which states that ''A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process... Development of TCPs by the DQO process is intended to allow users (e.g., Hanford Facility user groups, regulators) to ensure their needs will be met and that resources are devoted to gaining only necessary information.'' This document satisfies that requirement for the Tank 241-C-107 (C-107) sampling activities. Currently tank C-107 is categorized as a sound, low-heat load tank with partial isolation completed in December 1982. The tank is awaiting stabilization. Tank C-107 is expected to contain three primary layers of waste. The bottom layer should contain a mixture of the following wastes: ion exchange, concentrated phosphate waste from N-Reactor, Hanford Lab Operations, strontium semi-works, Battelle Northwest, 1C, TBP waste, cladding waste, and the hot semi-works. The middle layer should contain strontium recovery supernate. The upper layer should consist of non-complexed waste

TANK 21 AND TANK 24 BLEND AND FEED STUDY: BLENDING TIMES, SETTLING TIMES, AND TRANSFERS

Energy Technology Data Exchange (ETDEWEB)

Lee, S.; Leishear, R.; Poirier, M.

2012-05-31

The Salt Disposition Integration (SDI) portfolio of projects provides the infrastructure within existing Liquid Waste facilities to support the startup and long term operation of the Salt Waste Processing Facility (SWPF). Within SDI, the Blend and Feed Project will equip existing waste tanks in the Tank Farms to serve as Blend Tanks where salt solutions of up to 1.2 million gallons will be blended in 1.3 million gallon tanks and qualified for use as feedstock for SWPF. In particular, Tanks 21 and 24 are planned to be used for blending and transferring to the SDI feed tank. These tanks were evaluated here to determine blending times, to determine a range of settling times for disturbed sludge, and to determine that the SWPF Waste Acceptance Criteria that less than 1200 mg/liter of solids will be entrained in salt solutions during transfers from the Tank 21 and Tank 24 will be met. Overall conclusions for Tank 21 and Tank 24 operations include: (1) Experimental correction factors were applied to CFD (computational fluid dynamics) models to establish blending times between approximately two and five hours. As shown in Phase 2 research, blending times may be as much as ten times greater, or more, if lighter fluids are added to heavier fluids (i.e., water added to salt solution). As the densities of two salt solutions converge this effect may be minimized, but additional confirmatory research was not performed. (2) At the current sludge levels and the presently planned operating heights of the transfer pumps, solids entrainment will be less than 1200 mg/liter, assuming a conservative, slow settling sludge simulant. (3) Based on theoretical calculations, particles in the density range of 2.5 to 5.0 g/mL must be greater than 2-4 {micro}m in diameter to ensure they settle adequately in 30-60 days to meet the SWPF feed criterion (<1200 mg/l). (4) Experimental tests with sludge batch 6 simulant and field turbidity data from a recent Tank 21 mixing evolution suggest the solid

Lipozyme IM-catalyzed interesterification for the production of margarine fats in a 1 kg scale stirred tank reactor

DEFF Research Database (Denmark)

Zhang, Hong; Xu, Xuebing; Mu, Huiling

2000-01-01

Lipozyme IM-catalyzed interesterification of the oil blend between palm stearin and coconut oil (75/25 w/w) was studied for the production of margarine fats in a 1 kg scale batch stirred tank reactor. Parameters such as lipase load, water content, temperature, and reaction time were investigated...

TNKVNT: A model of the Tank 48 purge/ventilation exhaust system. Revision 1

International Nuclear Information System (INIS)

Shadday, M.A. Jr.

1996-04-01

The waste tank purge ventilation system for Tank 48 is designed to prevent dangerous concentrations of hydrogen or benzene from accumulating in the gas space of the tank. Fans pull the gas/water vapor mixture from the tank gas space and pass it sequentially through a demister, a condenser, a reheater, and HEPA filters before discharging to the environment. Proper operation of the HEPA filters requires that the gas mixture passing through them has a low relative humidity. The ventilation system has been modified by increasing the capacity of the fans and changing the condenser from a two-pass heat exchanger to a single-pass heat exchanger. It is important to understand the impact of these modifications on the operation of the system. A hydraulic model of the ventilation exhaust system has been developed. This model predicts the properties of the air throughout the system and the flowrate through the system, as functions of the tank gas space and environmental conditions. This document serves as a Software Design Report, a Software Coding report, and a User's Manual. All of the information required for understanding and using this code is herein contained: the governing equations are fully developed, the numerical algorithms are described in detail, and an extensively commented code listing is included. This updated version of the code models the entire purge ventilation system, and is therefore more general in its potential applications

40 CFR Table 3 to Subpart Dd of... - Tank Control Levels for Tanks at Existing Affected Sources as Required by 40 CFR 63.685(b)(1)

Science.gov (United States)

2010-07-01

... Existing Affected Sources as Required by 40 CFR 63.685(b)(1) 3 Table 3 to Subpart DD of Part 63 Protection... Hazardous Air Pollutants from Off-Site Waste and Recovery Operations Pt. 63, Subpt. DD, Table 3 Table 3 to Subpart DD of Part 63—Tank Control Levels for Tanks at Existing Affected Sources as Required by 40 CFR 63...

Target-specific M1 inputs to infragranular S1 pyramidal neurons

Science.gov (United States)

Fanselow, Erika E.; Simons, Daniel J.

2016-01-01

The functional role of input from the primary motor cortex (M1) to primary somatosensory cortex (S1) is unclear; one key to understanding this pathway may lie in elucidating the cell-type specific microcircuits that connect S1 and M1. Recently, we discovered that a subset of pyramidal neurons in the infragranular layers of S1 receive especially strong input from M1 (Kinnischtzke AK, Simons DJ, Fanselow EE. Cereb Cortex 24: 2237–2248, 2014), suggesting that M1 may affect specific classes of pyramidal neurons differently. Here, using combined optogenetic and retrograde labeling approaches in the mouse, we examined the strengths of M1 inputs to five classes of infragranular S1 neurons categorized by their projections to particular cortical and subcortical targets. We found that the magnitude of M1 synaptic input to S1 pyramidal neurons varies greatly depending on the projection target of the postsynaptic neuron. Of the populations examined, M1-projecting corticocortical neurons in L6 received the strongest M1 inputs, whereas ventral posterior medial nucleus-projecting corticothalamic neurons, also located in L6, received the weakest. Each population also possessed distinct intrinsic properties. The results suggest that M1 differentially engages specific classes of S1 projection neurons, thereby regulating the motor-related influence S1 exerts over subcortical structures. PMID:27334960

Analysis of CYP1A1 and COMT polymorphisms in women with cervical cancer.

Science.gov (United States)

Kleine, J P; Camargo-Kosugi, C M; Carvalho, C V; Silva, F C; Silva, I D C G

2015-12-29

The aim of this case-control study was to obtain a comprehensive panel of genetic polymorphisms present only in genes (cytochrome P-450 1A1--CYP1A1 and catechol-O-methyl transferase--COMT) within the metabolic pathway of sex steroids and determine their possible associations with the presence or absence of cervical cancer. Genotypes of 222 women were analyzed: a) 81 with cancer of the cervix treated at the Cancer Hospital Alfredo Abram, between June 2012 and May 2013, with diagnosis confirmed surgically and/or through histomorphological examination; and b) 141 healthy women who assisted at the Endocrine Gynecology and Climacteric Ambulatory, Department of Gynecology, UNIFESP-EPM. These polymorphisms were detected by polymerase chain reaction amplification-restriction fragment length polymorphism analysis and visualized on 3% agarose gels stained with ethidium bromide. We found a significant association between the frequency of the CYP1A1 polymorphism and the development of cervical cancer. A statistical difference was observed between patient and control groups for CYP1A1 polymorphism genotype distributions (P 0.05) or between other risk variables analyzed. The CYP1A1 gene involved in the metabolic pathway of sex steroids might influence the emergence of pathological conditions such as cervical cancer in women who carry a mutated allele, and result in 1.80 and 13.46 times increased risk for women with heterozygous or homozygous mutated genotypes, respectively.

Effect of tank geometry on its average performance

Science.gov (United States)

Orlov, Aleksey A.; Tsimbalyuk, Alexandr F.; Malyugin, Roman V.; Leontieva, Daria A.; Kotelnikova, Alexandra A.

2018-03-01

The mathematical model of non-stationary filling of vertical submerged tanks with gaseous uranium hexafluoride is presented in the paper. There are calculations of the average productivity, heat exchange area, and filling time of various volumes tanks with smooth inner walls depending on their "height : radius" ratio as well as the average productivity, degree, and filling time of horizontal ribbing tank with volume 6.10-2 m3 with change central hole diameter of the ribs. It has been shown that the growth of "height / radius" ratio in tanks with smooth inner walls up to the limiting values allows significantly increasing tank average productivity and reducing its filling time. Growth of H/R ratio of tank with volume 1.0 m3 to the limiting values (in comparison with the standard tank having H/R equal 3.49) augments tank productivity by 23.5 % and the heat exchange area by 20%. Besides, we have demonstrated that maximum average productivity and a minimum filling time are reached for the tank with volume 6.10-2 m3 having central hole diameter of horizontal ribs 6.4.10-2 m.

Technical bases for leak detection surveillance of waste storage tanks. Revision 1

International Nuclear Information System (INIS)

Johnson, M.G.; Badden, J.J.

1995-01-01

This document provides the technical bases for specification limits, monitoring frequencies and baselines used for leak detection and intrusion (for single shell tanks only) in all single and double shell radioactive waste storage tanks, waste transfer lines, and most catch tanks and receiver tanks in the waste tank farms and associated areas at Hanford

Tank characterization report for double-shell tank 241-AN-105

International Nuclear Information System (INIS)

Jo, J.

1997-01-01

A major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for double-shell tank 241-AN-105. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-AN-105 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-10

Tank characterization report for single-shell tank 241-C-104

Energy Technology Data Exchange (ETDEWEB)

Baldwin, J.H.

1997-05-21

A major function of the Tank Waste Remediation System is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-C-104. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-C-104 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-10.

Tank characterization report for single-shell tank 241-S-111

International Nuclear Information System (INIS)

Conner, J.M.

1997-01-01

One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-S-111. The objectives of this report are: (1) to use characterization data to address technical issues associated with tank 241-S-111 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices. This report also supports the requirements of Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-10

Tank characterization report for single-shell tank 241-S-111

Energy Technology Data Exchange (ETDEWEB)

Conner, J.M.

1997-04-28

One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-S-111. The objectives of this report are: (1) to use characterization data to address technical issues associated with tank 241-S-111 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices. This report also supports the requirements of Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-10.

Composite Cryotank Technologies and Development 2.4 and 5.5M out of Autoclave Tank Test Results

Science.gov (United States)

Jackson, Justin R.; Vickers, John; Fikes, John

2015-01-01

The Composite Cryotank Technologies and Demonstration (CCTD) project substantially matured composite, cryogenic propellant tank technology. The project involved the design, analysis, fabrication, and testing of large-scale (2.4-m-diameter precursor and 5.5-m-diameter) composite cryotanks. Design features included a one-piece wall design that minimized tank weight, a Y-joint that incorporated an engineered material to alleviate stress concentration under combined loading, and a fluted core cylindrical section that inherently allows for venting and purging. The tanks used out-of-autoclave (OoA) cured graphite/epoxy material and processes to enable large (up to 10-m-diameter) cryotank fabrication, and thin-ply prepreg to minimize hydrogen permeation through tank walls. Both tanks were fabricated at Boeing using automated fiber placement on breakdown tooling. A fluted core skirt that efficiently carried axial loads and enabled hydrogen purging was included on the 5.5-m-diameter tank. Ultrasonic inspection was performed, and a structural health monitoring system was installed to identify any impact damage during ground processing. The precursor and 5.5-m-diameter tanks were tested in custom test fixtures at the National Aeronautics and Space Administration Marshall Space Flight Center. The testing, which consisted of a sequence of pressure and thermal cycles using liquid hydrogen, was successfully concluded and obtained valuable structural, thermal, and permeation performance data. This technology can be applied to a variety of aircraft and spacecraft applications that would benefit from 30 to 40% weight savings and substantial cost savings compared to aluminum lithium tanks.

On The Possible Leakage of ET-RR1 Liquid Waste Tank: Hydrological and Migration Modes Studies

Directory of Open Access Journals (Sweden)

N. S. Mahmoud

2005-01-01

Full Text Available The first Egyptian (ET-RR1 research reactor has been in operation since 1961 at the Egyptian Atomic Energy Authority (EAEA Inshas site. Therefore, at present, it faces a serious problem due to aging equipment, especially those directly in contact with the environment such as the underground settling tanks of nuclear and radioactive waste. The possible leakage of radionuclides from these aging tanks and their migration to the aquifer was studied using instantaneous release.This study was done based on the geological and hydrological characteristics of the site, which were obtained from the hydrogeological data of 25 wells previously drilled at the site of the reactor[1]. These data were used to calculate the trend of water levels, hydraulic gradient, and formulation of water table maps from 1993–2002. This information was utilized to determine water velocity in the unsaturated zone.Radionuclides released from the settling tank to the aquifer were screened according to the radionuclides that have high migration ability and high activity. The amount of fission and activation products of the burned fuels that contaminated the water content of the reactor pool were considered as 10% of the original spent fuel. The radionuclides considered in this case were H-3, Sr-90, Zr-93, Tc-99, Cd-113, Cs-135, Cs-137, Sm-151, Pu-238, Pu-240, Pu-241, and Am-241.The instantaneous release was analyzed by theoretical calculations, taking into consideration the migration mechanism of the various radionuclides through the soil space between the tank bottom and the aquifer. The migration mechanism through the unsaturated zone was considered depending on soil type, thickness of the unsaturated zone, water velocity, and other factors that are specific for each radionuclide, namely retardation factor, which is the function of the specific distribution coefficient of each radionuclide. This was considered collectively as delay time. Meanwhile, the mechanism of

HYDRAULICS AND MIXING EVALUATIONS FOR NT-21/41 TANKS

Energy Technology Data Exchange (ETDEWEB)

Lee, S.; Barnes, O.

2014-11-17

The hydraulic results demonstrate that pump head pressure of 20 psi recirculates about 5.6 liters/min flowrate through the existing 0.131-inch orifice when a valve connected to NT-41 is closed. In case of the valve open to NT-41, the solution flowrates to HB-Line tanks, NT-21 and NT-41, are found to be about 0.5 lpm and 5.2 lpm, respectively. The modeling calculations for the mixing operations of miscible fluids contained in the HB-Line tank NT-21 were performed by taking a three-dimensional Computational Fluid Dynamics (CFD) approach. The CFD modeling results were benchmarked against the literature results and the previous SRNL test results to validate the model. Final performance calculations were performed for the nominal case by using the validated model to quantify the mixing time for the HB-Line tank. The results demonstrate that when a pump recirculates a solution volume of 5.7 liters every minute out of the 72-liter tank contents containing two acid solutions of 2.7 M and 0 M concentrations (i.e., water), a minimum mixing time of 1.5 hours is adequate for the tank contents to get the tank contents adequately mixed. In addition, the sensitivity results for the tank contents of 8 M existing solution and 1.5 M incoming species show that the mixing time takes about 2 hours to get the solutions mixed.

Tank characterization report for single-shell tank 241-U-106

International Nuclear Information System (INIS)

Brown, T.M.

1997-01-01

One major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-U-106. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-U-106 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 of this report summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations regarding safety status and additional sampling. The appendixes contain supporting data and information. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ikology et al. 1996), Milestone M-44-10

Tank characterization report for single-shell tank 241-U-106

Energy Technology Data Exchange (ETDEWEB)

Brown, T.M.

1997-04-15

One major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-U-106. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-U-106 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 of this report summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations regarding safety status and additional sampling. The appendixes contain supporting data and information. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ikology et al. 1996), Milestone M-44-10.

Action memorandum for the Waste Area Grouping 1 Tank WC-14 removal action at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1994-11-01

This action memorandum documents approval for a Comprehensive Environmental Response, Compensation, and Liability Act of 1980, as amended (CERCLA), time-critical action. The action will remove radiologically contaminated water from Tank WC-14. The water contains a polychlorinated biphenyl (PCB) at a level below regulatory concern. Tank WC-14 is located in the Waste Area Grouping (WAG) 1 WC-10 Tank Farm at the Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. Contaminated sludge remaining in the tank after removal of the liquid will be the subject of a future action

Tank characterization report for Single-Shell Tank B-111

International Nuclear Information System (INIS)

Remund, K.M.; Tingey, J.M.; Heasler, P.G.; Toth, J.J.; Ryan, F.M.; Hartley, S.A.; Simpson, D.B.; Simpson, B.C.

1994-09-01

Tank 241-B-111 (hereafter referred to as B-111) is a 2,006,300 liter (530,000 gallon) single-shell waste tank located in the 200 East B tank farm at Hanford. Two cores were taken from this tank in 1991 and analysis of the cores was conducted by Battelle's 325-A Laboratory in 1993. Characterization of the waste in this tank is being done to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-44-05. Tank B-111 was constructed in 1943 and put into service in 1945; it is the second tank in a cascade system with Tanks B-110 and B-112. During its process history, B-111 received mostly second-decontamination-cycle waste and fission products waste via the cascade from Tank B-110. This tank was retired from service in 1976, and in 1978 the tank was assumed to have leaked 30,300 liters (8,000 gallons). The tank was interim stabilized and interim isolated in 1985. The tank presently contains approximately 893,400 liters (236,000 gallons) of sludge-like waste and approximately 3,800 liters (1,000 gallons) of supernate. Historically, there are no unreviewed safety issues associated with this tank and none were revealed after reviewing the data from the latest core sampling event in 1991. An extensive set of analytical measurements was performed on the core composites. The major constituents (> 0.5 wt%) measured in the waste are water, sodium, nitrate, phosphate, nitrite, bismuth, iron, sulfate and silicon, ordered from largest concentration to the smallest. The concentrations and inventories of these and other constituents are given. Since Tanks B-110 and B-111 have similar process histories, their sampling results were compared. The results of the chemical analyses have been compared to the dangerous waste codes in the Washington Dangerous Waste Regulations (WAC 173-303). This assessment was conducted by comparing tank analyses against dangerous waste characteristics 'D' waste codes; and against state waste codes

Responses to Three USARIEM Job Analysis Questionnaires (JAQs) Conducted with Cavalry Scouts and Armor Crewmen (MOSs 19D and 19K)

Science.gov (United States)

2016-11-18

gun for one fire command 56 24 Boxes of rounds loaded for the .50 Cal Machine Gun on an Abrams Tank 56 25 Mean estimates of time spent by 19Ds...Number of rounds loaded for one fire command 55 22 Total boxes of rounds loaded for .50 cal machine gun on an Abrams tank 56 23 Number of Soldiers...and 19K MOSs, respectively). A total o f 8,580 Army calvary scouts and 6,613 armor crewmen in the USA Army as of May or June of 2014 were invited

mTORC1 directly phosphorylates and regulates human MAF1.

Science.gov (United States)

Michels, Annemieke A; Robitaille, Aaron M; Buczynski-Ruchonnet, Diane; Hodroj, Wassim; Reina, Jaime H; Hall, Michael N; Hernandez, Nouria

2010-08-01

mTORC1 is a central regulator of growth in response to nutrient availability, but few direct targets have been identified. RNA polymerase (pol) III produces a number of essential RNA molecules involved in protein synthesis, RNA maturation, and other processes. Its activity is highly regulated, and deregulation can lead to cell transformation. The human phosphoprotein MAF1 becomes dephosphorylated and represses pol III transcription after various stresses, but neither the significance of the phosphorylations nor the kinase involved is known. We find that human MAF1 is absolutely required for pol III repression in response to serum starvation or TORC1 inhibition by rapamycin or Torin1. The protein is phosphorylated mainly on residues S60, S68, and S75, and this inhibits its pol III repression function. The responsible kinase is mTORC1, which phosphorylates MAF1 directly. Our results describe molecular mechanisms by which mTORC1 controls human MAF1, a key repressor of RNA polymerase III transcription, and add a new branch to the signal transduction cascade immediately downstream of TORC1.

Operations and maintenance manual for the temporary septic holding tank at the 300-FF-1 Remedial Action Support Facility

International Nuclear Information System (INIS)

Gilkeson, D.E.; Jackson, G.J.

1997-02-01

This document provides detailed information regarding the operations and maintenance of the septic holding tank system at the 300-FF-1 Remedial Action Support Facility, located in the 300 Area. This document includes the type and frequency of requirement maintenance, failure response procedures, and reporting requirements. Sanitary wastewater and raw sewage will enter the holding tank via a sloped 102 mm polyvinyl chloride (PVC) line from the office trailers. The septic holding tank will be emptied, as required, by system demands. During normal usage, it is estimated that the tank will require pumping every 3 working days. Approximately 834 gallons of sanitary wastewater and raw sewage will be disposed of into the septic system during this time

Final characterization and safety screen report of double shell tank 241-AP-105 for evaporator campaign 97-1

International Nuclear Information System (INIS)

Miller, G.L.

1997-01-01

Evaporator candidate feed from tank 241-AP-105 (hereafter referred to as AP-105) was characterized for physical, inorganic, organic and radiochemical parameters by the 222-S Laboratory as directed by the Tank Sample and Analysis Plan (TSAP), References 1 through 4, and Engineering Change Notice, number 635332, Reference 5. This data package satisfies the requirement for a format IV, final report as described in Reference 1. This data package is also a follow-up to the 45-Day safety screen results for tank AP-105, Reference 8, which was issued on November 5, 1996, and is attached as Section II to this report. Preliminary data in the form of summary analytical tables were provided to the project in advance of this final report to enable early estimation of evaporator operational parameters, using the Predict modeling program. Analyses were performed at the 222-S Laboratory as defined and specified in the TSAP and the Laboratory's Quality Assurance P1an, References 6 and 7. Any deviations from the instructions documented in the TSAP are discussed in this narrative and are supported with additional documentation

Properties of M1-M2-Si-Al-O-N glasses (M1 = La or Nd, M2 = Y or Er)

Energy Technology Data Exchange (ETDEWEB)

Pomeroy, M.J.; Nestor, E.; Hampshire, S. [Limerick Univ. (Ireland). Materials and Surface Science Inst.; Ramesh, R. [Littelfuse Ireland, Dundalk, Co. Louth (Ireland)

2002-07-01

Mixed lanthanide cation oxynitride glasses have been prepared in the M1 - M2 - Si-Al-O-N systems where M1 = La or Nd and M2 = Y or Er. The densities ({rho}), Young's moduli (E), microhardnesses (H{sub v}), glass transition temperatures (T{sub g}), dilatometric softening temperatures (T{sub dil}) and coefficients of thermal expansion (CTE) of 13 glasses were determined. The molar volume values (MV) calculated from density data, E, H{sub v}, T{sub g}, T{sub dil} and CTE values were all found to vary linearly with the effective cation field strength arising from the M1 and M2 modifier cations. Least squares intercept and slope values are presented which correlate each property to effective cation field strength together with error values which arise from glass and specimen preparation and measurement inconsistencies. These linear correlations clearly indicate that the overall glass structure remains the same for each of the thirteen glasses with only the modifier cation(s) having any influence. This influence appears to be a cross-linking effect, the strength of which increases as the effective cation field strength of the M1, M2 modifiers increases. (orig.)

HAT-P-49b: a 1.7 M {sub J} planet transiting a bright 1.5 M {sub ☉} F-star

Energy Technology Data Exchange (ETDEWEB)

Bieryla, A.; Latham, D. W.; Buchhave, L. A.; Béky, B.; Falco, E.; Torres, G.; Noyes, R. W.; Berlind, P.; Calkins, M. C.; Esquerdo, G. A. [Harvard-Smithsonian Center for Astrophysics, Cambridge, MA 02138 (United States); Hartman, J. D.; Bakos, G. Á.; Bhatti, W.; Csubry, Z.; Penev, K.; De Val-Borro, M. [Department of Astrophysical Sciences, Princeton University, Princeton, NJ 08544 (United States); Kovács, G. [Konkoly Observatory, Budapest 1121 (Hungary); Boisse, I. [Centro de Astrofísica, Universidade do Porto, Rua das Estrelas, 4150-762 Porto (Portugal); Lázár, J.; Papp, I., E-mail: abieryla@cfa.harvard.edu, E-mail: gbakos@astro.princeton.edu [Hungarian Astronomical Association (HAA), Budapest 1461 (Hungary); and others

2014-04-01

We report the discovery of the transiting extrasolar planet HAT-P-49b. The planet transits the bright (V = 10.3) slightly evolved F-star HD 340099 with a mass of 1.54 M {sub ☉} and a radius of 1.83 R {sub ☉}. HAT-P-49b is orbiting one of the 25 brightest stars to host a transiting planet which makes this a favorable candidate for detailed follow-up. This system is an especially strong target for Rossiter-McLaughlin follow-up due to the host star's fast rotation, 16 km s{sup –1}. The planetary companion has a period of 2.6915 days, mass of 1.73 M {sub J}, and radius of 1.41 R {sub J}. The planetary characteristics are consistent with that of a classical hot Jupiter but we note that this is the fourth most massive star to host a transiting planet with both M{sub p} and R{sub p} well determined.

Elastin-derived peptides promote abdominal aortic aneurysm formation by modulating M1/M2 macrophage polarization1

Science.gov (United States)

Dale, Matthew A; Xiong, Wanfen; Carson, Jeffrey S; Suh, Melissa K; Karpisek, Andrew D.; Meisinger, Trevor M.; Casale, George P.; Baxter, B. Timothy

2016-01-01

Abdominal aortic aneurysm (AAA) is a dynamic vascular disease characterized by inflammatory cell invasion and extracellular matrix (ECM) degradation. Damage to elastin in the ECM results in release of elastin-derived peptides (EDPs), which are chemotactic for inflammatory cells such as monocytes. Their effect on macrophage polarization is less well known. Pro-inflammatory M1 macrophages initially are recruited to sites of injury but, if their effects are prolonged, they can lead to chronic inflammation that prevents normal tissue repair. Conversely, anti-inflammatory M2 macrophages reduce inflammation and aid in wound healing. Thus, a proper M1/M2 ratio is vital for tissue homeostasis. AAA tissue reveals a high M1/M2 ratio where pro-inflammatory cells and their associated markers dominate. In the present study, in vitro treatment of bone marrow-derived macrophages with EDPs induced M1 macrophage polarization. By using C57Bl/6 mice, antibody-mediated neutralization of EDPs reduced aortic dilation, matrix metalloproteinase activity, and pro-inflammatory cytokine expression at early and late time points after aneurysm induction. Furthermore, direct manipulation of the M1/M2 balance altered aortic dilation. Injection of M2 polarized macrophages reduced aortic dilation after aneurysm induction. EDPs promoted a pro-inflammatory environment in aortic tissue by inducing M1 polarization and neutralization of EDPs attenuated aortic dilation. The M1/M2 imbalance is vital to aneurysm formation. PMID:27183603

Determination of mixing characterisitics in leaching tanks using ...

African Journals Online (AJOL)

The mixing characteristics in two gold leaching tanks each of volume 1.4 x 103 m3 were investigated with a pulse injection of 7.4 x 1010 Bq aqueous solution of 131I into the feed of the tanks to determine the flow model and mixing efficiency of the system. The flow patterns in the tanks connected in series were identical with ...

46 CFR 32.52-1 - Bilge pumps on tank vessels constructed or converted on or after November 19, 1952-TB/ALL.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Bilge pumps on tank vessels constructed or converted on... Bilge pumps on tank vessels constructed or converted on or after November 19, 1952—TB/ALL. The number and arrangement of bilge pumps on each tank vessel shall conform to the requirements of subchapter F...

Nucleolin Mediates MicroRNA-directed CSF-1 mRNA Deadenylation but Increases Translation of CSF-1 mRNA*

Science.gov (United States)

Woo, Ho-Hyung; Baker, Terri; Laszlo, Csaba; Chambers, Setsuko K.

2013-01-01

CSF-1 mRNA 3′UTR contains multiple unique motifs, including a common microRNA (miRNA) target in close proximity to a noncanonical G-quadruplex and AU-rich elements (AREs). Using a luciferase reporter system fused to CSF-1 mRNA 3′UTR, disruption of the miRNA target region, G-quadruplex, and AREs together dramatically increased reporter RNA levels, suggesting important roles for these cis-acting regulatory elements in the down-regulation of CSF-1 mRNA. We find that nucleolin, which binds both G-quadruplex and AREs, enhances deadenylation of CSF-1 mRNA, promoting CSF-1 mRNA decay, while having the capacity to increase translation of CSF-1 mRNA. Through interaction with the CSF-1 3′UTR miRNA common target, we find that miR-130a and miR-301a inhibit CSF-1 expression by enhancing mRNA decay. Silencing of nucleolin prevents the miRNA-directed mRNA decay, indicating a requirement for nucleolin in miRNA activity on CSF-1 mRNA. Downstream effects followed by miR-130a and miR-301a inhibition of directed cellular motility of ovarian cancer cells were found to be dependent on nucleolin. The paradoxical effects of nucleolin on miRNA-directed CSF-1 mRNA deadenylation and on translational activation were explored further. The nucleolin protein contains four acidic stretches, four RNA recognition motifs (RRMs), and nine RGG repeats. All three domains in nucleolin regulate CSF-1 mRNA and protein levels. RRMs increase CSF-1 mRNA, whereas the acidic and RGG domains decrease CSF-1 protein levels. This suggests that nucleolin has the capacity to differentially regulate both CSF-1 RNA and protein levels. Our finding that nucleolin interacts with Ago2 indirectly via RNA and with poly(A)-binding protein C (PABPC) directly suggests a nucleolin-Ago2-PABPC complex formation on mRNA. This complex is in keeping with our suggestion that nucleolin may work with PABPC as a double-edged sword on both mRNA deadenylation and translational activation. Our findings underscore the complexity of

Corrective action baseline report for underground storage tank 2331-U Building 9201-1

International Nuclear Information System (INIS)

1994-01-01

The purpose of this report is to provide baseline geochemical and hydrogeologic data relative to corrective action for underground storage tank (UST) 2331-U at the Building 9201-1 Site. Progress in support of the Building 9201-1 Site has included monitoring well installation and baseline groundwater sampling and analysis. This document represents the baseline report for corrective action at the Building 9201-1 site and is organized into three sections. Section 1 presents introductory information relative to the site, including the regulatory initiative, site description, and progress to date. Section 2 includes the summary of additional monitoring well installation activities and the results of baseline groundwater sampling. Section 3 presents the baseline hydrogeology and planned zone of influence for groundwater remediation

Building M7-0505 Treatment Tank (SWMU 039) Annual Performance Monitoring Report

Science.gov (United States)

2015-01-01

This Annual Performance Monitoring Report presents a summary of Interim Measure (IM) activities and an evaluation of data collected during the third year (June 2014 to September 2015) of operation, maintenance, and monitoring (OM&M) conducted at the Building M7-505 (M505) Treatment Tank area, Kennedy Space Center (KSC), Florida ("the Site"). Under KSC's Resource Conservation and Recovery Act Corrective Action Program, the M505 Treatment Tank area was designated Solid Waste Management Unit 039. Arcadis U.S., Inc. (Arcadis) began IM activities on January 10, 2012, after completion of construction of an in situ air sparge (IAS) system to remediate volatile organic compounds (VOCs) in groundwater at concentrations exceeding applicable Florida Department of Environmental Protection (FDEP) Chapter 62-777, Florida Administrative Code, Natural Attenuation Default Concentrations (NADCs). This report presents a summary of the third year of OM&M activities conducted between June 2014 and September 2015.

In-service inspection of ET-RR-1 reactor vessels and spent fuel storage tank

International Nuclear Information System (INIS)

Khattab, M.; Shafy, M.; Konoplev, K.; Samodurve, YU.; Orlov, S.; Didenko, V.; Jackorev, O.

1993-01-01

Technical survey included in-service inspection are needed in order to investigate the structural integrity and to insure safe operation of the ET-R R-1 reactor after thirty years aging. An intensive work for the inspection of the inspection of the central tank, shield tank, horizontal channels, primary coolant circuit and spent fuel storage tank have been carried out. The inspection procedures were visual method using video camera and magnification optical as well as thickness measurements using ultrasonic gauge meter and replica for determining defect depth. Water chemical analysis of the primary cooling circuit and spent fuel storage were helpful in results explanation. The results showed that the reactor vessels have good surface conditions. The observed pitting did not affect the structural integrity. The majority of the defects were pits having maximum surface area of about 50 mm. Their depth does not exceed 2 mm. The pits depth rate penetration is of the order of 0.5% per year. Thickness measurements showed insignificant variation. Water status and its chemical properties are very important in controlling corrosion rate. 18 figs., 14 tabs

MNK Controls mTORC1:Substrate Association through Regulation of TELO2 Binding with mTORC1

Directory of Open Access Journals (Sweden)

Michael C. Brown

2017-02-01

Full Text Available The mechanistic target of rapamycin (mTOR integrates numerous stimuli and coordinates the adaptive response of many cellular processes. To accomplish this, mTOR associates with distinct co-factors that determine its signaling output. While many of these co-factors are known, in many cases their function and regulation remain opaque. The MAPK-interacting kinase (MNK contributes to rapamycin resistance in cancer cells. Here, we demonstrate that MNK sustains mTORC1 activity following rapamycin treatment and contributes to mTORC1 signaling following T cell activation and growth stimuli in cancer cells. We determine that MNK engages with mTORC1, promotes mTORC1 association with the phosphatidyl inositol 3′ kinase-related kinase (PIKK stabilizer, TELO2, and facilitates mTORC1:substrate binding. Moreover, our data suggest that DEPTOR, the endogenous inhibitor of mTOR, opposes mTORC1:substrate association by preventing TELO2:mTORC1 binding. Thus, MNK orchestrates counterbalancing forces that regulate mTORC1 enzymatic activity.

Resveratrol regulates microglia M1/M2 polarization via PGC-1α in conditions of neuroinflammatory injury.

Science.gov (United States)

Yang, Xiaodong; Xu, Shaoqing; Qian, Yiwei; Xiao, Qin

2017-08-01

Microglia are the primary cells that exert immune function in the central nervous system (CNS), and accumulating evidence suggests that microglia act as key players in the initiation of neurodegenerative diseases. It is now well recognized that microglia have functional plasticity and dual phenotypes, proinflammatory M1 and anti-inflammatory M2 phenotypes. Inhibiting the M1 phenotype while stimulating the M2 phenotype has been suggested as a potential therapeutic approach for the treatment of neuroinflammation-related diseases. Resveratrol has been demonstrated to exert anti-inflammatory effects by suppressing M1 microglia activation. However, the role of resveratrol in regulating microglia polarization and the molecular mechanisms involved have not been fully clarified. In this study, we tested whether resveratrol could suppress microglia activation by promoting microglia polarization toward the M2 phenotype via PGC-1α by measuring M1 and M2 markers in vitro and in vivo. Our study demonstrated that resveratrol reduced inflammatory damage and promoted microglia polarization to the M2 phenotype in LPS-induced neuroinflammation. In addition, resveratrol ameliorated LPS-induced sickness behavior in mice. The promoting effects of resveratrol on M2 polarization were attenuated by knocking down PGC-1α. PGC-1α not only suppressed LPS-evoked M1 marker expression by inhibition of NF-κB activity but also increased M2 marker expression by coactivation of the STAT6 and STAT3 pathways. We propose that overexpression PGC-1α by resveratrol could be a potential therapeutic approach to suppress neuroinflammation by regulating microglia polarization. Copyright © 2017 Elsevier Inc. All rights reserved.

AX Tank Farm tank removal study

Energy Technology Data Exchange (ETDEWEB)

SKELLY, W.A.

1999-02-24

This report examines the feasibility of remediating ancillary equipment associated with the 241-AX Tank Farm at the Hanford Site. Ancillary equipment includes surface structures and equipment, process waste piping, ventilation components, wells, and pits, boxes, sumps, and tanks used to make waste transfers to/from the AX tanks and adjoining tank farms. Two remedial alternatives are considered: (1) excavation and removal of all ancillary equipment items, and (2) in-situ stabilization by grout filling, the 241-AX Tank Farm is being employed as a strawman in engineering studies evaluating clean and landfill closure options for Hanford single-shell tanks. This is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

Commissioning and cross-comparison of four scanning water tanks

Directory of Open Access Journals (Sweden)

Daniel Saenz

2016-03-01

Full Text Available Purpose: Water scanning systems are commonly used for data collection to characterize dosimetric properties of photon and electron beams, and the commissioning of such systems has been previously described. The aim in this study, however, was to investigate tank-specific dependencies as well as conduct a dosimetric comparison between four distinct water scanning systems.Methods: Four water scanning systems were studied including the PTW MP3-M Phantom Tank, the Standard Imaging DoseView 3D, the IBA Blue Phantom, and the Sun Nuclear 3D Scanner. Mechanical accuracy and reproducibility was investigated by driving the chamber holder to nominal positions relative to a zero point and using a leveled caliper with 30 cm range to measure the actual position. Dosimetric measurements were also performed not only to compare percent-depth-dose (PDD curves and profiles between tanks but also to assess dependencies such as directionality, scanning speed, and reproducibility for each tank individually. A PTW Semiflex 31010 ionization chamber with a sensitive volume of 0.125 cc was used at a Varian Clinac 2300 linear accelerator.Results: Mechanical precision was ensured to within 0.1 mm with the standard deviation (SD of reproducibility <0.1 mm for measurements made with calipers. Dependencies on scanning direction and speed are presented. 6 MV PDDs between tanks agreed to within 0.6% relative to an averaged PDD beyond dmax and within 2.5% in the build-up region. Specifically, the maximum difference was 1.0% between MP3-M and Blue Phantom at 6.1 cm depth. Lateral profiles agreed between tanks within 0.5% in the central 80% of the field. 6 MeV PDD maximum difference was 1.3% occurring at the steepest portion, where the R50 was nevertheless within 0.6 mm across tanks. Setup uncertainties estimated at ≤1 mm are presumed to have contributed some of the difference between water tank data.Conclusion: Modern water scanning systems have achieved high accuracy across

Rheology of Savannah River Site Tank 42 radioactive sludges. Revision 1

International Nuclear Information System (INIS)

Ha, B.C.; Bibler, N.E.

1995-01-01

Knowledge of the rheology of the radioactive sludge slurries at the Savannah River Site (SRS) is necessary in order to ensure that they can be retrieved from waste tanks and processed for final disposal. At Savannah River Site (SRS), Tank 42 sludge represents one of the first HLW radioactive sludges to be vitrified in the Defense Waste Processing Facility (DWPF). The rheological properties of unwashed Tank 42 sludge slurries at various solids concentrations were measured remotely in the Shielded Cells at the Savannah River Technology Center (SRTC) using a modified Haake Rotovisco viscometer. Rheological properties of Tank 42 radioactive sludge were measured as a function of weight percent total solids to ensure that the first DWPF radioactive sludge batch can be pumped and processed in the DWPF with the current design bases. The yield stress and consistency of the sludge slurries were determined by assuming a Bingham plastic fluid model

49 CFR 173.172 - Aircraft hydraulic power unit fuel tank.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Aircraft hydraulic power unit fuel tank. 173.172... Class 1 and Class 7 § 173.172 Aircraft hydraulic power unit fuel tank. Aircraft hydraulic power unit fuel tanks containing a mixture of anhydrous hydrazine and monomethyl hydrazine (M86 fuel) and designed...

Tank characterization report for single-shell tank 241-A-101

International Nuclear Information System (INIS)

Field, J.M.

1997-01-01

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-A-101. This tank has been listed on the Hydrogen Watch List. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10

A new series of oxycarbonate superconductors (Cu{sub 0.5}C{sub 0.5}){sub m}Ba{sub m+1}Ca{sub n-1}Cu{sub n}O{sub 2}({sub m+n})+1

Energy Technology Data Exchange (ETDEWEB)

Takayama-Muromachi, E.; Kawashima, T.; Matsui, Y. [National Institute for Research in Inorganic Materials, Ibaraki (Japan)

1994-12-31

We found a new series of oxycarbonate superconductors in the Ba-Ca-Cu-C-O system under high pressure of 5 GPa. Their ideal formula is (Cu{sub 0.5}C{sub 0.5}){sub m}Ba{sub m+1}Ca{sub n-1}Cu{sub n}O{sub 2}({sub m+n})+1 ((Cu,C)-m(m+1)(n-1)n). Thus far, n=3, 4 members of the m=1 series, (Cu,C)-1223 and (Cu,C)-1234, have been prepared in bulk while n=4, 5 members, (Cu,C)-2334 and (Cu,C)-2345, have been prepared for the m=2 series. (Cu,C)-1223 shows superconductivity below 67 K while T{sub c}`s of other compounds are above 110 K. In particular, (Cu,C)=1234 has the highest T{sub c} of 117 K.

Differential S1P Receptor Profiles on M1- and M2-Polarized Macrophages Affect Macrophage Cytokine Production and Migration.

Science.gov (United States)

Müller, Jan; von Bernstorff, Wolfram; Heidecke, Claus-Dieter; Schulze, Tobias

2017-01-01

Introduction . Macrophages are key players in complex biological processes. In response to environmental signals, macrophages undergo polarization towards a proinflammatory (M1) or anti-inflammatory (M2) phenotype. Sphingosine 1-phosphate (S1P) is a bioactive lysophospholipid that acts via 5 G-protein coupled receptors (S1P 1-5 ) in order to influence a broad spectrum of biological processes. This study assesses S1P receptor expression on macrophages before and after M1 and M2 polarization and performs a comparative analysis of S1P signalling in the two activational states of macrophages. Methods . Bone marrow derived macrophages (BMDM) from C57 BL/6 mice were cultured under either M1- or M2-polarizing conditions. S1P-receptor expression was determined by quantitative RT-PCR. Influence of S1P on macrophage activation, migration, phagocytosis, and cytokine secretion was assessed in vitro. Results . All 5 S1P receptor subclasses were expressed in macrophages. Culture under both M1- and M2-polarizing conditions led to significant downregulation of S1P 1 . In contrast, M1-polarized macrophages significantly downregulated S1P 4 . The expression of the remaining three S1P receptors did not change. S1P increased expression of iNOS under M2-polarizing conditions. Furthermore, S1P induced chemotaxis in M1 macrophages and changed cytokine production in M2 macrophages. Phagocytosis was not affected by S1P-signalling. Discussion . The expression of different specific S1P receptor profiles may provide a possibility to selectively influence M1- or M2-polarized macrophages.

Assessing the applicability of the 1D flux theory to full-scale secondary settling tank design with a 2D hydrodynamic model.

Science.gov (United States)

Ekama, G A; Marais, P

2004-02-01

The applicability of the one-dimensional idealized flux theory (1DFT) for the design of secondary settling tanks (SSTs) is evaluated by comparing its predicted maximum surface overflow (SOR) and solids loading (SLR) rates with that calculated with the two-dimensional computational fluid dynamics model SettlerCAD using as a basis 35 full-scale SST stress tests conducted on different SSTs with diameters from 30 to 45m and 2.25-4.1m side water depth (SWD), with and without Stamford baffles. From the simulations, a relatively consistent pattern appeared, i.e. that the 1DFT can be used for design but its predicted maximum SLR needs to be reduced by an appropriate flux rating, the magnitude of which depends mainly on SST depth and hydraulic loading rate (HLR). Simulations of the Watts et al. (Water Res. 30(9)(1996)2112) SST, with doubled SWDs and the Darvill new (4.1m) and old (2.5m) SSTs with interchanged depths, were run to confirm the sensitivity of the flux rating to depth and HLR. Simulations with and without a Stamford baffle were also performed. While the design of the internal features of the SST, such as baffling, has a marked influence on the effluent SS concentration while the SST is underloaded, these features appeared to have only a small influence on the flux rating, i.e. capacity, of the SST. Until more information is obtained, it would appear from the simulations that the flux rating of 0.80 of the 1DFT maximum SLR recommended by Ekama and Marais (Water Pollut. Control 85(1)(1986)101) remains a reasonable value to apply in the design of full-scale SSTs-for deep SSTs (4m SWD) the flux rating could be increased to 0.85 and for shallow SSTs (2.5m SWD) decreased to 0.75. It is recommended that (i) while the apparent interrelationship between SST flux rating and depth suggests some optimization of the volume of the SST, this be avoided and (ii) the depth of the SST be designed independently of the surface area as is usually the practice and once selected, the

Saturn V First Stage S-1C LOX Fuel Tanks

Science.gov (United States)

1960-01-01

This photograph shows the Saturn V assembled LOX (Liquid Oxygen) and fuel tanks ready for transport from the Manufacturing Engineering Laboratory at Marshall Space Flight Center in Huntsville, Alabama. The tanks were then shipped to the launch site at Kennedy Space Center for a flight. The towering 363-foot Saturn V was a multi-stage, multi-engine launch vehicle standing taller than the Statue of Liberty. Altogether, the Saturn V engines produced as much power as 85 Hoover Dams.

46 CFR 32.55-5 - Ventilation of tank vessels constructed between November 10, 1936, and July 1, 1951-TB/ALL.

Science.gov (United States)

2010-10-01

... actuated gas ejectors or blowers or ventilators fitted with heads for natural ventilation, will be approved... 46 Shipping 1 2010-10-01 2010-10-01 false Ventilation of tank vessels constructed between November... HOMELAND SECURITY TANK VESSELS SPECIAL EQUIPMENT, MACHINERY, AND HULL REQUIREMENTS Ventilation and Venting...

Tank characterization report for single-shell tank 241-S-104

International Nuclear Information System (INIS)

Jo, J.

1997-01-01

One of the major functions of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for single-shell tank 241-S-104. The objectives of this report are: (1) to use characterization data in response to technical issues associated with 241-S- 104 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendixes. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-05

Experimental Conditions: SE24_S1_M1_D1 [Metabolonote[Archive

Lifescience Database Archive (English)

Full Text Available rometry with 13C‑Labeling for Chemical Assignment of Sulfur-Containing Metabolites ...SE24_S1_M1_D1 SE24 Combination of Liquid Chromatography-Fourier Transform Ion Cyclotron Resonance-Mass Spect

Ire1 mediated mRNA splicing in a C-terminus deletion mutant of Drosophila Xbp1.

Directory of Open Access Journals (Sweden)

Dina S Coelho

Full Text Available The Unfolded Protein Response is a homeostatic mechanism that permits eukaryotic cells to cope with Endoplasmic Reticulum (ER stress caused by excessive accumulation of misfolded proteins in the ER lumen. The more conserved branch of the UPR relies on an ER transmembrane enzyme, Ire1, which, upon ER stress, promotes the unconventional splicing of a small intron from the mRNA encoding the transcription factor Xbp1. In mammals, two specific regions (the hydrophobic region 2--HR2--and the C-terminal translational pausing site present in the Xbp1unspliced protein mediate the recruitment of the Xbp1 mRNA-ribosome-nascent chain complex to the ER membrane, so that Xbp1 mRNA can be spliced by Ire1. Here, we generated a Drosophila Xbp1 deletion mutant (Excision101 lacking both HR2 and C-terminal region, but not the Ire1 splicing site. We show that Ire1-dependent splicing of Xbp1 mRNA is reduced, but not abolished in Excision101. Our results suggest the existence of additional mechanisms for ER membrane targeting of Xbp1 mRNA that are independent of the C-terminal domain of Drosophila Xbp1unspliced.

FoxM1 is a general target for proteasome inhibitors.

Directory of Open Access Journals (Sweden)

Uppoor G Bhat

2009-08-01

Full Text Available Proteasome inhibitors are currently in the clinic or in clinical trials, but the mechanism of their anticancer activity is not completely understood. The oncogenic transcription factor FoxM1 is one of the most overexpressed genes in human tumors, while its expression is usually halted in normal non-proliferating cells. Previously, we established that thiazole antibiotics Siomycin A and thiostrepton inhibit FoxM1 and induce apoptosis in human cancer cells. Here, we report that Siomycin A and thiostrepton stabilize the expression of a variety of proteins, such as p21, Mcl-1, p53 and hdm-2 and also act as proteasome inhibitors in vitro. More importantly, we also found that well-known proteasome inhibitors such as MG115, MG132 and bortezomib inhibit FoxM1 transcriptional activity and FoxM1 expression. In addition, overexpression of FoxM1 specifically protects against bortezomib-, but not doxorubicin-induced apoptosis. These data suggest that negative regulation of FoxM1 by proteasome inhibitors is a general feature of these drugs and it may contribute to their anticancer properties.

Tank waste remediation system characterization project quality policies. Revision 1

International Nuclear Information System (INIS)

Trimble, D.J.

1995-01-01

These Quality Policies (QPs) describe the Quality Management System of the Tank Waste Characterization Project (hereafter referred to as the Characterization Project), Tank Waste Remediation System (TWRS), Westinghouse Hanford Company (WHC). The Quality Policies and quality requirements described herein are binding on all Characterization Project organizations. To achieve quality, the Characterization Project management team shall implement this Characterization Project Quality Management System

mTORC1 Directly Phosphorylates and Regulates Human MAF1▿

Science.gov (United States)

Michels, Annemieke A.; Robitaille, Aaron M.; Buczynski-Ruchonnet, Diane; Hodroj, Wassim; Reina, Jaime H.; Hall, Michael N.; Hernandez, Nouria

2010-01-01

mTORC1 is a central regulator of growth in response to nutrient availability, but few direct targets have been identified. RNA polymerase (pol) III produces a number of essential RNA molecules involved in protein synthesis, RNA maturation, and other processes. Its activity is highly regulated, and deregulation can lead to cell transformation. The human phosphoprotein MAF1 becomes dephosphorylated and represses pol III transcription after various stresses, but neither the significance of the phosphorylations nor the kinase involved is known. We find that human MAF1 is absolutely required for pol III repression in response to serum starvation or TORC1 inhibition by rapamycin or Torin1. The protein is phosphorylated mainly on residues S60, S68, and S75, and this inhibits its pol III repression function. The responsible kinase is mTORC1, which phosphorylates MAF1 directly. Our results describe molecular mechanisms by which mTORC1 controls human MAF1, a key repressor of RNA polymerase III transcription, and add a new branch to the signal transduction cascade immediately downstream of TORC1. PMID:20516213

The September 2017 M=8.1 Chiapas and M=7.1 Puebla, Mexico, earthquakes: Chain reaction or coincidence?

Science.gov (United States)

Toda, S.; Stein, R. S.

2017-12-01

The M=8.1 and M=7.1 events struck 12 days and 600 km apart, both with an independent probability of occurrence of 0.5% per year, based on the GEAR model [Bird et al., 2015]. Are they related? First, we calculated the static stress imparted by the M=8.1 shock to the fault that ruptured in the M=7.1, and find a tiny push that would favor rupture. But the stress increase (0.2 kPa) is less than the fault would experience from the tidal stresses, and so it should be inconsequential. We next used the México Servicio Sismológico Nacional (UNAM) online catalog to look at the quakes in the month before the M=8.1 and in the 13 days since. We calculate the completeness to be M≥4.0. There are virtually no remote aftershocks from the Chiapas rupture that extend within 250 km of the M=7.1 shock during the first week after the M=8.1. So, if anything, the M=8.1 turned off for a week or more the region that ruptured in the M=7.1. Events started turning on about 2-3 days before the M=7.1, but none of those struck within 40 km of the future M=7.1 mainshock. The seismic surface waves unleashed by great earthquakes envelop the globe in just 160 minutes, and yet triggering of remote large aftershocks during these 2-3 hours is either very rare [Pollitz et al., Nature 2012] or in dispute [Fan & Shearer, 2016 vs. Yue et al., 2017]. So, the waves must trigger tiny shocks that cascade into larger shocks after some delay. Or, perhaps the stresses conveyed by the waves pump pockets of fluids that slowly diffuse into nearby fault zones, lubricating them to the point of failure [Parsons at al., 2017]. In the cases where great earthquakes are indisputably seen to trigger aftershocks at great distances or even globally, they to do so within several days, or a week at most. Since Puebla struck 12 days later, this seems to us too long a period to be explained by dynamic triggering. Even though neither quake on their own is rare, what's the chance of independent M=8.1 and M=7.1 events just 12

Depósito de agua 1.500 m3 en Getafe – España

Directory of Open Access Journals (Sweden)

del Pozo, Florencio

1970-02-01

Full Text Available Due to the redevelopment of the activities of the proprietor firm, and the consequent need to modify and extend the cooling water circuit of their plant, it has been necessary to construct an elevated water tank, with a minimum height of 30 m above the ground. This tank, whose description is given, is made of prestressed concrete, has no roofing surface, and its detailed characteristics as well as the method of construction are also briefly and clearly discussed in this article.Por exigencias y reestructuración de la empresa propietaria, que ha orientado en forma nueva la producción de sus talleres, ha sido necesario modificar y ampliar todo el circuito de agua de refrigeración, lo que ha obligado a construir un depósito de agua elevado, con cota mínima de + 30 m, de hormigón pretensado y sin cubierta, cuyas características, Ba cálculo y proceso constructivo se describen somera, pero claramente, en este artículo.

Data quality objectives for TWRS privatization Phase 1: Confirm tank T is an appropriate feed source for low-activity waste feed batch X

International Nuclear Information System (INIS)

Certa, P.J.

1998-01-01

This document is one of a series of problem-specific data quality objectives prepared to help identify information needs of tank waste disposal in support of the Phase 1 privatization of the Tank Waste Remediation System (TWRS)

Sea cucumbers reduce chromophoric dissolved organic matter in aquaculture tanks.

Science.gov (United States)

Sadeghi-Nassaj, Seyed Mohammad; Catalá, Teresa S; Álvarez, Pedro A; Reche, Isabel

2018-01-01

Mono-specific aquaculture effluents contain high concentrations of nutrients and organic matter, which affect negatively the water quality of the recipient ecosystems. A fundamental feature of water quality is its transparency. The fraction of dissolved organic matter that absorbs light is named chromophoric dissolved organic matter (CDOM). A sustainable alternative to mono-specific aquaculture is the multitrophic aquaculture that includes species trophically complementary named "extractive" species that uptake the waste byproducts. Sea cucumbers are recognized as efficient extractive species due to the consumption of particulate organic matter (POM). However, the effects of sea cucumbers on CDOM are still unknown. During more than one year, we monitored CDOM in two big-volume tanks with different trophic structure. One of the tanks (-holothurian) only contained around 810 individuals of Anemonia sulcata , whereas the other tank (+holothurian) also included 90 individuals of Holothuria tubulosa and Holothuria forskali . We routinely analyzed CDOM absorption spectra and determined quantitative (absorption coefficients at 325 nm) and qualitative (spectral slopes) optical parameters in the inlet waters, within the tanks, and in their corresponding effluents. To confirm the time-series results, we also performed three experiments. Each experiment consisted of two treatments: +holothurians (+H) and -holothurians (-H). We set up three +H tanks with 80 individuals of A. sulcata and 10 individuals of H. tubulosa in each tank and four -H tanks that contained only 80 individuals of A. sulcata . In the time-series, absorption coefficients at 325 nm ( a 325 ) and spectral slopes from 275 to 295 nm ( S 275-295 ) were significantly lower in the effluent of the +holothurian tank (average: 0.33 m -1 and 16 µm -1 , respectively) than in the effluent of the -holothurian tank (average: 0.69 m -1 and 34 µm -1 , respectively), the former being similar to those found in the inlet

E2F1 regulates cellular growth by mTORC1 signaling.

Directory of Open Access Journals (Sweden)

Sebastian Real

2011-01-01

Full Text Available During cell proliferation, growth must occur to maintain homeostatic cell size. Here we show that E2F1 is capable of inducing growth by regulating mTORC1 activity. The activation of cell growth and mTORC1 by E2F1 is dependent on both E2F1's ability to bind DNA and to regulate gene transcription, demonstrating that a gene induction expression program is required in this process. Unlike E2F1, E2F3 is unable to activate mTORC1, suggesting that growth activity could be restricted to individual E2F members. The effect of E2F1 on the activation of mTORC1 does not depend on Akt. Furthermore, over-expression of TSC2 does not interfere with the effect of E2F1, indicating that the E2F1-induced signal pathway can compensate for the inhibitory effect of TSC2 on Rheb. Immunolocalization studies demonstrate that E2F1 induces the translocation of mTORC1 to the late endosome vesicles, in a mechanism dependent of leucine. E2F1 and leucine, or insulin, together affect the activation of S6K stronger than alone suggesting that they are complementary in activating the signal pathway. From these studies, E2F1 emerges as a key protein that integrates cell division and growth, both of which are essential for cell proliferation.

Process control plan for 242-A Evaporator Campaign 95-1

Energy Technology Data Exchange (ETDEWEB)

Le, E.Q.; Guthrie, M.D.

1995-05-18

The wastes from tanks 106-AP, 107-AP, and 106-AW have been selected to be candidate feed wastes for Evaporator Campaign 95-1. The wastes in tank 106-AP and 107-AP are primarily from B-Plant strontium processing and PUREX neutralized cladding removal, respectively. The waste in tank 106-AW originated primarily from the partially concentrated product from 242-A Evaporator Campaign 94-2. Approximately 8.67 million liters of waste from these tanks will be transferred to tank 102-AW during the campaign. Tank 102-AW is the dedicated waste feed tank for the evaporator and currently contains 647,000 liters of processable waste. The purpose of the 242-A Evaporator Campaign 95-1 Process Control Plan (hereafter referred to as PCP) is to certify that the wastes in tanks 106-AP, 107-AP, 102-AW, and 106-AW are acceptable for processing through evaporator and provide a general description of process strategies and activities which will take place during Campaign 95-1. The PCP also summarizes and presents a comprehensive characterization of the wastes in these tanks.

Process control plan for 242-A Evaporator Campaign 95-1

International Nuclear Information System (INIS)

Le, E.Q.; Guthrie, M.D.

1995-01-01

The wastes from tanks 106-AP, 107-AP, and 106-AW have been selected to be candidate feed wastes for Evaporator Campaign 95-1. The wastes in tank 106-AP and 107-AP are primarily from B-Plant strontium processing and PUREX neutralized cladding removal, respectively. The waste in tank 106-AW originated primarily from the partially concentrated product from 242-A Evaporator Campaign 94-2. Approximately 8.67 million liters of waste from these tanks will be transferred to tank 102-AW during the campaign. Tank 102-AW is the dedicated waste feed tank for the evaporator and currently contains 647,000 liters of processable waste. The purpose of the 242-A Evaporator Campaign 95-1 Process Control Plan (hereafter referred to as PCP) is to certify that the wastes in tanks 106-AP, 107-AP, 102-AW, and 106-AW are acceptable for processing through evaporator and provide a general description of process strategies and activities which will take place during Campaign 95-1. The PCP also summarizes and presents a comprehensive characterization of the wastes in these tanks

Current status of the Thai Research Reactor (TRR-1/M1)

International Nuclear Information System (INIS)

Chueinta, Siripone; Julanan, Mongkol; Charncanchee, Decharchai

2006-01-01

The first Thai Research Reactor, TRR-1 went critical on 27 October 1962 at the maximum power of 1 MW. It was located at Office of Atoms for Peace (OAP) in Bangkok. Since then, TRR-1 was continuously operated and eventually shut down in 1975. Plate type, high-enriched uranium (HEU) and U 3 O 8 A1 cladding were used as the reactor fuel. Light water was used as moderator and coolant as well. In 1975, because of the problem from fuel supplier and also to supporting the Treaty of Non Proliferation of Nuclear Weapon or NPT, TRR-1 was shut down for modification. The reactor core and control system were disassembled and replaced by TRIGA Mark III. A new core was a hexagonal core shape designed by General Atomics (GA). Afterwards, TRR-1 was officially renamed to the Thai Research Reactor-1/Modification 1 (TRR-1/M1). TRR-1/M1 is a multipurpose swimming pool type reactor with nominal power of 2 MW. The TRR-1/M1 uses uranium enriched at 20% in U-235 (LEU) and ZrH alloy as fuel. Light water is also used as coolant and moderator. At present, the reactor is operating with core No.14. The reactor has been serving for various kinds of utilization namely, radioisotope production, neutron activation analysis, beam experiments and reactor physics experiments. (author)

Vapor space characterization of waste tank 241-C-101: Results from samples collected on 9/1/94

International Nuclear Information System (INIS)

Lucke, R.B.; Clauss, T.W.; Ligotke, M.W.

1995-11-01

This report describes results of the analyses of tank-headspace samples taken from the Hanford waste Tank 241-C-101 (referred to as Tank C-101) and the ambient air collected - 30 ft upwind near the tank and through the VSS near the tank. Pacific Northwest Laboratory (PNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and to analyze inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The sample job was designated S4056, and samples were collected by WHC on September 1, 1994, using the vapor sampling system (VSS). The samples were inspected upon delivery to the 326/23B laboratory and logged into PNL record book 55408 before implementation of PNL Technical Procedure PNL-TVP-07. Custody of the sorbent traps was transferred to PNL personnel performing the inorganic analysis and stored at refrigerated (≤ 10 degrees C) temperature until the time of analysis. The canisters were stored in the 326/23B laboratory at ambient (25 degrees C) temperature until the time of the analysis. Access to the 326/23B laboratory is limited to PNL personnel working on the waste-tank safety program. Analyses described in this report were performed at PNL in the 300 area of the Hanford Reservation. Analytical methods that were used are described in the text. In summary, sorbent traps for inorganic analyses containing sample materials were either weighed (for water analysis) or desorbed with the appropriate aqueous solutions (for NH 3 , NO 2 , and NO analyses). The aqueous extracts were analyzed either by selective electrode or by ion chromatography (IC). Organic analyses were performed using cryogenic preconcentration followed by gas chromatography/mass spectrometry (GC/MS)

Operational Evaluation Of Vectomax® WSP (Bacillus thuringiensis Subsp. israelensis+Bacillus sphaericus) Against Larval Culex pipiens in Septic Tanks (1).

Science.gov (United States)

Cetin, Huseyin; Oz, Emre; Yanikoglu, Atila; Cilek, James E

2015-06-01

The residual effectiveness of VectoMax® WSP (a water-soluble pouch formulation containing a combination of Bacillus thuringiensis subsp. israelensis strain AM65-52 and B. sphaericus strain ABTS 1743) when applied to septic tanks against 3rd- and 4th-stage larvae of Culex pipiens L. was evaluated in this study. This formulation was evaluated at operational application rates of 1 pouch (10 g) and 2 pouches (20 g) per septic tank. Both application rates resulted in >96% control of larvae for 24 days. Operationally, VectoMax WSP has proven to be a useful tool for the nonchemical control of Culex species in septic tank environments.

Analysis of glutathione S-transferase (M1, T1 and P1) gene ...

African Journals Online (AJOL)

Glutathione S-transferase enzymes are active in detoxifying a wide number of endogenous and exogenous chemical carcinogens and subsequently, are crucial in protecting the DNA. Several studies show some differences in association of glutathione S-transferase M1, T1 and P1 genetic polymorphisms with the risk of ...

Temporary septic holding tank at the 100-D remedial action support facility -- Engineering report. Revision 1

International Nuclear Information System (INIS)

Kelty, G.G.

1996-09-01

This document provides an engineering evaluation for the temporary septic holding tank that will be installed at the 100-D Remedial Action Support Facility at the 100-DR-1 Operable Unit in the Hanford Site. This support facility will be installed at the 100-DR-1 Operable Unit to provide office and work space for the workers involved in remediation activities of the various waste sites located at the Hanford Site

Main: 1M2Q [RPSD[Archive

Lifescience Database Archive (English)

Full Text Available 1M2Q トウモロコシ Corn Zea mays L. Casein Kinase Ii, Alpha Chain Name=Ack2; Zea Mays Mole...cule: Casein Kinase Ii, Alpha Chain; Chain: A; Fragment: Catlytic Subunit; Synonym: Ckii; Engineered: Yes Tr...ansferase 2.7.1.37 (Casein Kinase Ii, Alpha Chain) E.De Moliner, S.Sarno, S.Moro, G.Zagotto, G.Zanotti, L.A....=2-326.|PDB; 1M2Q; X-ray; A=2-328.|PDB; 1M2R; X-ray; A=2-328.|PDB; 1OM1; X-ray; A=1-332.|Mai

Estimation and Properties of a Time-Varying GQARCH(1,1-M Model

Directory of Open Access Journals (Sweden)

Sofia Anyfantaki

2011-01-01

analysis of these models computationally infeasible. This paper outlines the issues and suggests to employ a Markov chain Monte Carlo algorithm which allows the calculation of a classical estimator via the simulated EM algorithm or a simulated Bayesian solution in only ( computational operations, where is the sample size. Furthermore, the theoretical dynamic properties of a time-varying GQARCH(1,1-M are derived. We discuss them and apply the suggested Bayesian estimation to three major stock markets.

Flammable gas tank waste level reconcilliation tank 241-SX-102

International Nuclear Information System (INIS)

Brevick, C.H.; Gaddie, L.A.

1997-01-01

Fluoro Dynel Northwest (FDNW) was authorized to address flammable gas issues by reconciling the unexplained surface level increases in Tank 24 1-S-1 1 1 (S-I 1 1, typical). The trapped gas evaluation document (ref 1) states that Tank SX-102 exceeds the 25% of the lower flammable limit (FL) criterion (ref 2), based on a surface level rise evaluation. The Waste Storage Tank Status and Leak Detection Criteria document, commonly referred to as the ''Wallet Report'' is the basis for this letter report (ref 3). The Wallet Report is also a part of the trapped gas evaluation document criteria. The Wallet Report contains various tank information, including: physical information, status, levels, and dry wells, see Appendix A. The unexplained waste level rises were attributed to the production and retention of gas in the column of waste corresponding to the unacquainted for surface level rise. From 1973 through 1980, the Wallet Report tracked Tank S- 102 transfers and reported a net cumulative change of 19.95 in. This surface level increase is from an unknown source or is unacquainted for. Duke Engineering and Services Hanford (DASH) and Leached Martin Hanford Corporation (LMHC) are interested in determining the validity of the unexplained surface level changes reported in the 0611e Wallet Report based upon other corroborative sources of data. The purpose of this letter report is to assemble detailed surface level and waste addition data from daily tank records, logbooks, and other corroborative data that indicate surface levels, and to reconcile the cumulative unacquainted for surface level changes as shown in the Wallet Report from 1973 through 1980

“m=1” coatings

DEFF Research Database (Denmark)

Cooper-Jensen, C.; Klinkby, Esben Bryndt; Beaucour, J.

For neutrons the critical angle of Ni is defined as m=1. If one needs a coating with reflectivity above m=1, people have traditionally used Ni58 or Ni-based multilayers. The reason to use Ni is the high neutron scattering density and the fact that it is easy to coat Ni using magnetron sputtering....... For a neutron guide the cost of shielding around the guide is a substantial part of the total cost of the guide. We are therefore looking at other materials than Ni for m=1 coatings. Both Be and diamond have the same or higher neutron scattering density than Ni, and have a much smaller absorption cross section....... Because of the lower absorption cross section, and because of fewer emitted gamma ray photons when a neutron is absorbed, these coatings are producing much less gamma radiation and therefore reduce the shielding costs. Be is frequently used in a wide range of science and technology applications. The only...

Experimental critical parameters of enriched uranium solution in annular tank geometries

International Nuclear Information System (INIS)

Rothe, R.E.

1996-04-01

A total of 61 critical configurations are reported for experiments involving various combinations of annular tanks into which enriched uranium solution was pumped. These experiments were performed at two widely separated times in the 1980s under two programs at the Rocky Flats Plant's Critical Mass Laboratory. The uranyl nitrate solution contained about 370 g of uranium per liter, but this concentration varied a little over the duration of the studies. The uranium was enriched to about 93% [sup 235]U. All tanks were typical of sizes commonly found in nuclear production plants. They were about 2 m tall and ranged in diameter from 0.6 m to 1.5 m. Annular thicknesses and conditions of neutron reflection, moderation, and absorption were such that criticality would be achieved with these dimensions. Only 13 of the entire set of 74 experiments proved to be subcritical when tanks were completely filled with solution. Single tanks of several radial thicknesses were studied as well as small line arrays (1 x 2 and 1 x 3) of annular tanks. Many systems were reflected on four sides and the bottom by concrete, but none were reflected from above. Many experiments also contained materials within and outside the annular regions that contained strong neutron absorbers. One program had such a thick external moderator/absorber combination that no reflector was used at all

Experimental critical parameters of enriched uranium solution in annular tank geometries

Energy Technology Data Exchange (ETDEWEB)

Rothe, R.E.

1996-04-01

A total of 61 critical configurations are reported for experiments involving various combinations of annular tanks into which enriched uranium solution was pumped. These experiments were performed at two widely separated times in the 1980s under two programs at the Rocky Flats Plant`s Critical Mass Laboratory. The uranyl nitrate solution contained about 370 g of uranium per liter, but this concentration varied a little over the duration of the studies. The uranium was enriched to about 93% [sup 235]U. All tanks were typical of sizes commonly found in nuclear production plants. They were about 2 m tall and ranged in diameter from 0.6 m to 1.5 m. Annular thicknesses and conditions of neutron reflection, moderation, and absorption were such that criticality would be achieved with these dimensions. Only 13 of the entire set of 74 experiments proved to be subcritical when tanks were completely filled with solution. Single tanks of several radial thicknesses were studied as well as small line arrays (1 x 2 and 1 x 3) of annular tanks. Many systems were reflected on four sides and the bottom by concrete, but none were reflected from above. Many experiments also contained materials within and outside the annular regions that contained strong neutron absorbers. One program had such a thick external moderator/absorber combination that no reflector was used at all.

M1 and M2 macrophages derived from THP-1 cells differentially modulate the response of cancer cells to etoposide

International Nuclear Information System (INIS)

Genin, Marie; Clement, Francois; Fattaccioli, Antoine; Raes, Martine; Michiels, Carine

2015-01-01

Tumor associated macrophages (TAMs) are present in high density in solid tumors. TAMs share many characteristics with alternatively activated macrophages, also called M2. They have been shown to favor tumor development and a role in chemoresistance has also been suggested. Here, we investigated the effects of M2 in comparison to M1 macrophages on cancer cell sensitivity to etoposide. We set up a model of macrophage polarization, starting from THP-1 monocytes differentiated into macrophages using PMA (Phorbol 12-myristate 13-acetate). Once differentiated (M0 macrophages), they were incubated with IL-4 and IL-13 in order to obtain M2 polarized macrophages or with IFN-gamma and LPS for classical macrophage activation (M1). To mimic the communication between cancer cells and TAMs, M0, M1 or M2 macrophages and HepG2 or A549 cancer cells were co-cultured during respectively 16 (HepG2) or 24 (A549) hours, before etoposide exposure for 24 (HepG2) or 16 (A549) hours. After the incubation, the impact of etoposide on macrophage polarization was studied and cancer cell apoptosis was assessed by western-blot for cleaved caspase-3 and cleaved PARP-1 protein, caspase activity assay and FACS analysis of Annexin V and PI staining. mRNA and protein expression of M1 and M2 markers confirmed the polarization of THP-1-derived macrophages, which provide a new, easy and well-characterized model of polarized human macrophages. Etoposide-induced cancer cell apoptosis was markedly reduced in the presence of THP-1 M2 macrophages, while apoptosis was increased in cells co-cultured with M1 macrophages. On the other hand, etoposide did not influence M1 or M2 polarization. These results evidence for the first time a clear protective effect of M2 on the contrary to M1 macrophages on etoposide-induced cancer cell apoptosis

Management assessment of tank waste remediation system contractor readiness to proceed with phase 1B privatization

International Nuclear Information System (INIS)

Honeyman, J.O.

1998-01-01

This Management Assessment of Tank Waste Remediation System (TWRS) Contractor Readiness to Proceed With Phase 1B Privatization documents the processes used to determine readiness to proceed with tank waste treatment technologies from private industry, now known as TWRS privatization. An overall systems approach was applied to develop action plans to support the retrieval and disposal mission of the TWRS Project. The systems and infrastructure required to support the mission are known. Required systems are either in place or plans have been developed to ensure they exist when needed. Since October 1996 a robust system engineering approach to establishing integrated Technical Baselines, work breakdown structures, tank farms organizational structure and configurations, work scope, and costs has become part of the culture within the TWRS Project. An analysis of the programmatic, management, and technical activities necessary to declare readiness to proceed with execution of the mission demonstrates that the system, personnel, and hardware will be on-line and ready to support the private contractors. The systems approach included defining the retrieval and disposal mission requirements and evaluating the readiness of the Project Hanford Management Contract (PHMC) team to support initiation of waste processing by the private contractors in June 2002 and to receive immobilized waste shortly thereafter. The Phase 1 feed delivery requirements from the private contractor Requests for Proposal were reviewed. Transfer piping routes were mapped, existing systems were evaluated, and upgrade requirements were defined

Final characterization and safety screen report of double shell tank 241-AP-104 for 242-A evaporator, campaign 96-1

International Nuclear Information System (INIS)

Miller, G.L.

1996-01-01

This data package satisfies the requirement for a format IV, final report. It is a follow-up to the 45-day safety screen report for tank AP-104. Evaporator candidate feed from tank 241-AP-104 (hereafter referred to as AP-104) was characterized for physical, inorganic, organic and radiochemical parameters by the Westinghouse Hanford Company, 222-S Laboratory, and by the Battelle Pacific Northwest National Laboratory (PNNL), Analytical Chemistry Laboratory (ACL) as directed by the Tank Sample and Analysis Plan (TSAP), References 1 through 4. Preliminary data in the form of summary analytical tables were provided to the project in advance of this final report to enable early estimation of evaporator operational parameters, using the Predict modeling program. Laboratory analyses at ACL Laboratory was performed according to the TSAP. Analyses were performed at the 222-S Laboratory as defined and specified in the TSAP and the Laboratory's Quality Assurance Plan, References 5 and 6. Any deviations from the instructions documented in the TSAP are discussed in this narrative and are supported with additional documentation. SAMPLING The TSAP, section 2, provided sampling information for waste samples collected from tank AP-104. The bottle-on-a-string method was used to collect liquid grab samples from the tank. Each glass sample bottle was amber, precleaned, and contained approximately 100 milliliters. Each bottle was closed with a teflon seal cap (or teflon septum for volatile organic analysis samples). Field blank samples were prepared by placing deionized water into sampling bottles, lowering the unclosed bottles into the riser for a period of time, retrieving them from the riser, and then closing the bottles with the same types of caps used for the tank samples. None of the samples were preserved by acidification. Upon receipt, the sample bottles destined for organic analyses were placed in a refrigerator. No attempt was made during sampling to assure the complete

Mouse fetal antigen 1 (mFA1), the circulating gene product of mdlk, pref-1 and SCP-1: isolation, characterization and biology

DEFF Research Database (Denmark)

Bachmann, E; Krogh, T N; Højrup, P

1996-01-01

The mouse homologue to human fetal antigen 1 (hFA1) was purified from mouse amniotic fluid by cation exchange chromatography and immunospecific affinity chromatography. Mouse FA1 (mFA1) is a single chain glycoprotein with an M(r) of 42-50 kDa (SDS-PAGE). The N-terminal amino acid sequence (39...... residues) revealed 74% identity to hFA1 and 100% identity to the translated cDNAs referred to as mouse dlk, pref-1 and SCP-1. mFA1 is the secreted processed molecule encoded by the mRNA defined by these identical mouse cDNAs. Monospecific rabbit anti-mFA1 antibodies, purified by ammonium sulfate...... precipitation and immunospecific affinity chromatography, were used for immunohistochemical and quantitative ELISA techniques. The indirect immunoperoxidase technique demonstrated mFA1 within the endocrine structures of adult mouse pancreas, whereas the exocrine tissue remained unstained. FA1-positive staining...

Rheology of Savannah River site tank 42 and tank 51 HLW radioactive sludges

International Nuclear Information System (INIS)

Ha, B.C.; Bibler, N.E.

1996-01-01

Knowledge of the rheology of the radioactive sludge slurries at the Savannah River Site (SRS) is necessary in order to ensure that they can be retrieved from waste tanks and processed for final disposal. The high activity radioactive wastes stored as caustic slurries at SRS result from the neutralization of acid waste generated from production of nuclear defense materials. During storage, the wastes separate into a supernate layer and a sludge layer. In the Defense Waste Processing Facility (DWPF) at SRS, the radionuclides from the sludge and supernate will be immobilized into borosilicate glass for long term storage and eventual disposal. Before transferring the waste from a storage tank to the DWPF, a portion of the aluminum in the waste sludge will be dissolved and the sludge will be extensively washed to remove sodium. Tank 51 and Tank 42 radioactive sludges represent the first batch of HLW sludge to be processed in the DWPF. This paper presents results of rheology measurements of Tank 51 and Tank 42 at various solids concentrations. The rheologies of Tank 51 and Tank 42 radioactive slurries were measured remotely in the Shielded Cells Operations (SCO) at the Savannah River Technology Center (SRTC) using a modified Haake Rotovisco RV-12 with an M150 measuring drive unit and TI sensor system. Rheological properties of the Tank 51 and Tank 42 radioactive sludges were measured as a function of weight percent solids. The weight percent solids of Tank 42 sludge was 27, as received. Tank 51 sludge had already been washed. The weight percent solids were adjusted by dilution with water or by concentration through drying. At 12, 15, and 18 weight percent solids, the yield stresses of Tank 51 sludge were 5, 11, and 14 dynes/cm2, respectively. The apparent viscosities were 6, 10, and 12 centipoises at 300 sec-1 shear rate, respectively

Enhanced M1/M2 macrophage ratio promotes orthodontic root resorption.

Science.gov (United States)

He, D; Kou, X; Luo, Q; Yang, R; Liu, D; Wang, X; Song, Y; Cao, H; Zeng, M; Gan, Y; Zhou, Y

2015-01-01

Mechanical force-induced orthodontic root resorption is a major clinical challenge in orthodontic treatment. Macrophages play an important role in orthodontic root resorption, but the underlying mechanism remains unclear. In this study, we examined the mechanism by which the ratio of M1 to M2 macrophage polarization affects root resorption during orthodontic tooth movement. Root resorption occurred when nickel-titanium coil springs were applied on the upper first molars of rats for 3 to 14 d. Positively stained odontoclasts or osteoclasts with tartrate-resistant acid phosphatase were found in resorption areas. Meanwhile, M1-like macrophages positive for CD68 and inducible nitric oxide synthase (iNOS) persistently accumulated on the compression side of periodontal tissues. In addition, the expressions of the M1 activator interferon-γ and the M1-associated pro-inflammatory cytokine tumor necrosis factor (TNF)-α were upregulated on the compression side of periodontal tissues. When the coil springs were removed at the 14th day after orthodontic force application, root resorption was partially rescued. The number of CD68(+)CD163(+) M2-like macrophages gradually increased on the compression side of periodontal tissues. The levels of M2 activator interleukin (IL)-4 and the M2-associated anti-inflammatory cytokine IL-10 also increased. Systemic injection of the TNF-α inhibitor etanercept or IL-4 attenuated the severity of root resorption and decreased the ratio of M1 to M2 macrophages. These data imply that the balance between M1 and M2 macrophages affects orthodontic root resorption. Root resorption was aggravated by an enhanced M1/M2 ratio but was partially rescued by a reduced M1/M2 ratio. © International & American Associations for Dental Research 2014.

High-definition transcranial direct-current stimulation of the right M1 further facilitates left M1 excitability during crossed facilitation.

Science.gov (United States)

Cabibel, Vincent; Muthalib, Makii; Teo, Wei-Peng; Perrey, Stephane

2018-04-01

The crossed-facilitation (CF) effect refers to when motor-evoked potentials (MEPs) evoked in the relaxed muscles of one arm are facilitated by contraction of the opposite arm. The aim of this study was to determine whether high-definition transcranial direct-current stimulation (HD-tDCS) applied to the right primary motor cortex (M1) controlling the left contracting arm [50% maximum voluntary isometric contraction (MVIC)] would further facilitate CF toward the relaxed right arm. Seventeen healthy right-handed subjects participated in an anodal and cathodal or sham HD-tDCS session of the right M1 (2 mA for 20 min) separated by at least 48 h. Single-pulse transcranial magnetic stimulation (TMS) was used to elicit MEPs and cortical silent periods (CSPs) from the left M1 at baseline and 10 min into and after right M1 HD-tDCS. At baseline, compared with resting, CF (i.e., right arm resting, left arm 50% MVIC) increased left M1 MEP amplitudes (+97%) and decreased CSPs (-11%). The main novel finding was that right M1 HD-tDCS further increased left M1 excitability (+28.3%) and inhibition (+21%) from baseline levels during CF of the left M1, with no difference between anodal and cathodal HD-tDCS sessions. No modulation of CSP or MEP was observed during sham HD-tDCS sessions. Our findings suggest that CF of the left M1 combined with right M1 anodal or cathodal HD-tDCS further facilitated interhemispheric interactions during CF from the right M1 (contracting left arm) toward the left M1 (relaxed right arm), with effects on both excitatory and inhibitory processing. NEW & NOTEWORTHY This study shows modulation of the nonstimulated left M1 by right M1 HD-tDCS combined with crossed facilitation, which was probably achieved through modulation of interhemispheric interactions.

TANK-Binding Kinase 1 (TBK1 Isoforms Negatively Regulate Type I Interferon Induction by Inhibiting TBK1-IRF3 Interaction and IRF3 Phosphorylation

Directory of Open Access Journals (Sweden)

Yi Wei Hu

2018-01-01

Full Text Available TANK-binding kinase 1 (TBK1 is an important serine/threonine-protein kinase that mediates phosphorylation and nuclear translocation of IRF3, which contributes to induction of type I interferons (IFNs in the innate antiviral response. In mammals, TBK1 spliced isoform negatively regulates the virus-triggered IFN-β signaling pathway by disrupting the interaction between retinoic acid-inducible gene I (RIG-I and mitochondria antiviral-signaling protein (MAVS. However, it is still unclear whether alternative splicing patterns and the function of TBK1 isoform(s exist in teleost fish. In this study, we identify two alternatively spliced isoforms of TBK1 from zebrafish, termed TBK1_tv1 and TBK1_tv2. Both TBK1_tv1 and TBK1_tv2 contain an incomplete STKc_TBK1 domain. Moreover, the UBL_TBK1_like domain is also missing for TBK1_tv2. TBK1_tv1 and TBK1_tv2 are expressed in zebrafish larvae. Overexpression of TBK1_tv1 and TBK1_tv2 inhibits RIG-I-, MAVS-, TBK1-, and IRF3-mediated activation of IFN promoters in response to spring viremia of carp virus infection. Also, TBK1_tv1 and TBK1_tv2 inhibit expression of IFNs and IFN-stimulated genes induced by MAVS and TBK1. Mechanistically, TBK1_tv1 and TBK1_tv2 competitively associate with TBK1 and IRF3 to disrupt the formation of a functional TBK1-IRF3 complex, impeding the phosphorylation of IRF3 mediated by TBK1. Collectively, these results demonstrate that TBK1 spliced isoforms are dominant negative regulators in the RIG-I/MAVS/TBK1/IRF3 antiviral pathway by targeting the functional TBK1-IRF3 complex formation. Identification and functional characterization of piscine TBK1 spliced isoforms may contribute to understanding the role of TBK1 expression in innate antiviral response.

Sludge mobilization with submerged nozzles in horizontal cylindrical tanks

International Nuclear Information System (INIS)

Hylton, T.D.; Cummins, R.L.; Youngblood, E.L.; Perona, J.J.

1995-10-01

The Melton Valley Storage Tanks (MVSTs) and the evaporator service tanks at the Oak Ridge National Laboratory (ORNL) are used for the collection and storage of liquid low-level waste (LLLW). Wastes collected in these tanks are typically acidic when generated and are neutralized with sodium hydroxide to protect the tanks from corrosion; however, the high pH of the solution causes the formation of insoluble compounds that precipitate. These precipitates formed a sludge layer approximately 0.6 to 1.2 m (2 to 4 ft) deep in the bottom of the tanks. The sludge in the MVSTs and the evaporator service tanks will eventually need to be removed from the tanks and treated for final disposal or transferred to another storage facility. The primary options for removing the sludge include single-point sluicing, use of a floating pump, robotic sluicing, and submerged-nozzle sluicing. The objectives of this study were to (1) evaluate the feasibility of submerged-nozzle sluicing in horizontal cylindrical tanks and (2) obtain experimental data to validate the TEMPEST (time-dependent, energy, momentun, pressure, equation solution in three dimensions) computer code

Tank 241-AP-107, grab samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 analytical results for the final report

International Nuclear Information System (INIS)

Steen, F.H.

1997-01-01

This document is the final report for tank 241-AP-107 grab samples. Three grab samples were collected from riser 1 on September 11, 1997. Analyses were performed on samples 7AP-97-1, 7AP-97-2 and 7AP-97-3 in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) (Sasaki, 1997) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Rev. 1: Fowler, 1995; Rev. 2: Mulkey and Nuier, 1997). The analytical results are presented in the data summary report (Table 1). A notification was made to East Tank Farms Operations concerning low hydroxide in the tank and a hydroxide (caustic) demand analysis was requested. The request for sample analysis (RSA) (Attachment 2) received for AP-107 indicated that the samples were polychlorinated biphenyl (PCB) suspects. Therefore, prior to performing the requested analyses, aliquots were made to perform PCB analysis in accordance with the 222-S Laboratory administrative procedure, LAP-101-100. The results of this analysis indicated that no PCBs were present at 50 ppm and analysis proceeded as non-PCB samples. The results and raw data for the PCB analysis will be included in a revision to this document. The sample breakdown diagrams (Attachment 1) are provided as a cross-reference for relating the tank farm customer identification numbers with the 222-S Laboratory sample numbers and the portion of sample analyzed

High-level waste tank remediation technology integration summary. Revision 1

International Nuclear Information System (INIS)

DeLannoy, C.R.; Susiene, C.; Fowler, K.M.; Robson, W.M.; Cruse, J.M.

1994-07-01

The U.S. Department of Energy's Environmental Restoration and Waste Management and Technology Development Programs are engaged in a number of projects to develop, demonstrate, test, and evaluate new technologies to support the cleanup and site remediation of more than 300 underground storage tanks containing over 381,000 m 3 (100 million gal) of liquid radioactive mixed waste at the Hanford Reservation. Significant development is needed within primary functions and in determining an overall bounding strategy. This document is an update of continuing work to summarize the overall strategy and to provide data regarding technology development activities within the strategy. It is intended to serve as an information resource to support understanding, decision making, and integration of multiple program technology development activities. Recipients are encouraged to provide comments and input to the authors for incorporation in future revisions

Tank 241-BY-105 vapor sampling and analysis tank characterization report

International Nuclear Information System (INIS)

Huckaby, J.L.

1995-01-01

Tank BY-105 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-105 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-105 using the vapor sampling system (VSS) on July 7, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 26 C. Air from the Tank BY-105 headspace was withdrawn via a heated sampling probe mounted in riser 10A, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 65 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 46 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 10 trip blanks provided by the laboratories

Phase 1 RCRA Facility Investigation/Corrective Measures Study Work Plan for Single-Shell Tank (SST) Waste Management Areas

International Nuclear Information System (INIS)

MCCARTHY, M.M.

1999-01-01

This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly

Technical assessment of workplace air sampling requirements at tank farm facilities. Revision 1

International Nuclear Information System (INIS)

Olsen, P.A.

1994-01-01

WHC-CM-1-6 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). It was written to implement DOE N 5480.6 ''US Department of Energy Radiological Control Manual'' as it applies to programs at Hanford which are now overseen by WHC. As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. In addition to WHC-CM-1-6, there is HSRCM-1, the ''Hanford Site Radiological Control Manual'' and several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. This document also provides an evaluation of the compliance of Tank Farms' workplace air sampling program to the criteria, standards, and requirements and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance

Amino Acid Activation of mTORC1 by a PB1-Domain-Driven Kinase Complex Cascade.

Science.gov (United States)

Linares, Juan F; Duran, Angeles; Reina-Campos, Miguel; Aza-Blanc, Pedro; Campos, Alex; Moscat, Jorge; Diaz-Meco, Maria T

2015-08-25

The mTORC1 complex is central to the cellular response to changes in nutrient availability. The signaling adaptor p62 contributes to mTORC1 activation in response to amino acids and interacts with TRAF6, which is required for the translocation of mTORC1 to the lysosome and the subsequent K63 polyubiquitination and activation of mTOR. However, the signal initiating these p62-driven processes was previously unknown. Here, we show that p62 is phosphorylated via a cascade that includes MEK3/6 and p38δ and is driven by the PB1-containing kinase MEKK3. This phosphorylation results in the recruitment of TRAF6 to p62, the ubiquitination and activation of mTOR, and the regulation of autophagy and cell proliferation. Genetic inactivation of MEKK3 or p38δ mimics that of p62 in that it leads to inhibited growth of PTEN-deficient prostate organoids. Analysis of human prostate cancer samples showed upregulation of these three components of the pathway, which correlated with enhanced mTORC1 activation. Copyright © 2015 The Authors. Published by Elsevier Inc. All rights reserved.

Amino Acid Activation of mTORC1 by a PB1-Domain-Driven Kinase Complex Cascade

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Juan F. Linares

2015-08-01

Full Text Available The mTORC1 complex is central to the cellular response to changes in nutrient availability. The signaling adaptor p62 contributes to mTORC1 activation in response to amino acids and interacts with TRAF6, which is required for the translocation of mTORC1 to the lysosome and the subsequent K63 polyubiquitination and activation of mTOR. However, the signal initiating these p62-driven processes was previously unknown. Here, we show that p62 is phosphorylated via a cascade that includes MEK3/6 and p38δ and is driven by the PB1-containing kinase MEKK3. This phosphorylation results in the recruitment of TRAF6 to p62, the ubiquitination and activation of mTOR, and the regulation of autophagy and cell proliferation. Genetic inactivation of MEKK3 or p38δ mimics that of p62 in that it leads to inhibited growth of PTEN-deficient prostate organoids. Analysis of human prostate cancer samples showed upregulation of these three components of the pathway, which correlated with enhanced mTORC1 activation.

The MCNP Simulation of a PGNAA System at TRR-1/M1

Science.gov (United States)

Sangaroon, S.; Ratanatongchai, W.; Picha, R.; Khaweerat, S.; Channuie, J.

2017-06-01

The prompt-gamma neutron activation analysis system (PGNAA) has been installed at Thai Research Reactor-1/Modified 1 (TRR-1/M1) since 1999. The purpose of the system is for elemental and isotopic analyses. The system mainly consists of a series of the moderator and collimator, neutron and gamma-ray shielding and the HPGe detector. In this work, the condition of the system is carried out based on the Monte Carlo method using Monte Carlo N-Particle transport code and the experiment. The flux ratios (Φthermal/Φepithermal and Φthermal/Φfast) and thermal neutron flux have been obtained. The simulated prompt gamma rays of the Portland cement sample have been carried out. The simulation provides significant contribution in upgrading the PGNAA station to be available in various applications.

Uncleaved ApoM signal peptide is required for formation of large ApoM/sphingosine 1-phosphate (S1P)-enriched HDL particles.

Science.gov (United States)

Liu, Mingxia; Allegood, Jeremy; Zhu, Xuewei; Seo, Jeongmin; Gebre, Abraham K; Boudyguina, Elena; Cheng, Dongmei; Chuang, Chia-Chi; Shelness, Gregory S; Spiegel, Sarah; Parks, John S

2015-03-20

Apolipoprotein M (apoM), a plasma sphingosine 1-phosphate (S1P) carrier, associates with plasma HDL via its uncleaved signal peptide. Hepatocyte-specific apoM overexpression in mice stimulates formation of both larger nascent HDL in hepatocytes and larger mature apoM/S1P-enriched HDL particles in plasma by enhancing hepatic S1P synthesis and secretion. Mutagenesis of apoM glutamine 22 to alanine (apoM(Q22A)) introduces a functional signal peptidase cleavage site. Expression of apoM(Q22A) in ABCA1-expressing HEK293 cells resulted in the formation of smaller nascent HDL particles compared with wild type apoM (apoM(WT)). When apoM(Q22A) was expressed in vivo, using recombinant adenoviruses, smaller plasma HDL particles and decreased plasma S1P and apoM were observed relative to expression of apoM(WT). Hepatocytes isolated from both apoM(WT)- and apoM(Q22A)-expressing mice displayed an equivalent increase in cellular levels of S1P, relative to LacZ controls; however, relative to apoM(WT), apoM(Q22A) hepatocytes displayed more rapid apoM and S1P secretion but minimal apoM(Q22A) bound to nascent lipoproteins. Pharmacologic inhibition of ceramide synthesis increased cellular sphingosine and S1P but not medium S1P in both apoM(WT) and apoM(Q22A) hepatocytes. We conclude that apoM secretion is rate-limiting for hepatocyte S1P secretion and that its uncleaved signal peptide delays apoM trafficking out of the cell, promoting formation of larger nascent apoM- and S1P-enriched HDL particles that are probably precursors of larger apoM/S1P-enriched plasma HDL. © 2015 by The American Society for Biochemistry and Molecular Biology, Inc.

Revised final report for tank 241-AN-101, grab samples 1AN-95-1 through 1AN-95-7. Revision 1

International Nuclear Information System (INIS)

Esch, R.A.

1996-01-01

Six supernate grab samples and one field blank were taken from tank 241-AN-101. This report documents analyses performed in support of the Safety Screening program: differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), density by specific gravity (Sp.G.), and total alpha activity (AT)

Evaluation and monitoring plan for consolidation tanks: Gunite and Associated Tanks Operable Unit, Waste Area Grouping 1, Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1997-02-01

This report describes the results of an integrity evaluation of Tanks W-8 and W-9, part of the Gunite and Associated Tanks (GAAT), in the South Tank Farm at Oak Ridge National Laboratory (ORNL), together with a plan for monitoring those tanks for potential releases during the GAAT CERCLA treatability study and waste removal activities. This work was done in support of an ORNL plan to use W-8 and W-9 as consolidation tanks during remediation of the other tanks in the North and South Tank Farms. The analysis portion of the report draws upon both tank-internal measurements of liquid volume change and tank-external measurements of the change in electrical conductivity of the groundwater in the dry wells adjacent to each tank. The results of the analysis show that both W-8 and W-9 are liquid-tight and are suitable for use as consolidation tanks. The recommended monitoring plan will utilize the dry well conductivity monitoring method as the primary release detection tool during the CERCLA activities. This method is expected to be able to detect releases of less than 0.5 gal/h with a 95% probability of detection, most of the time. The results described here validate three prior independent efforts: a liquid integrity assessment made in 1995, a structural integrity assessment made in 1995 by experts in the field of gunite tanks, and a structural integrity assessment made in 1994 using a three-dimensional, finite-element computer model. This work, along with the three prior efforts, shows that Tanks W-8 and W-9 are structurally sound and liquid-tight. Based upon this work it is concluded that these tanks are suitable for use as consolidation tanks during the GAAT CERCLA treatability study and waste removal actions and it is recommended that the tanks be monitored for potential releases during this period using the methods described in this report

Multi-Function Waste Tank Facility Corrosion Test Report (Phase 1)

International Nuclear Information System (INIS)

Carlos, W. C.; Fritz, R. L.

1993-01-01

This report documents the results of the corrosion tests that were performed to aid in the selection of the construction materials for multi-function waste tanks to be built in the U.S. Department of Energy Hanford Site. Two alloys were tested: 304L and Alloy 20 austenitic stainless steel. The test media were aqueous solutions formulated to represent the extreme of the chemical compositions of waste to be stored in the tanks. The results summerized by alloy are as follows: For 304L the tests showed no stress-corrosion cracking in any of the nine test solutions. The tests showed pitting in on of the solutions. There were no indications of any weld heat-tint corrosion, nor any sign of preferential corrosion in the welded areas. For Alloy 20 the tests showed no general, pitting, or stress-corrosion cracking. One crevice corrosion coupon cracked at the web between a hole and the edge of the coupon in one of the solutions. Mechanical tests showed some possible crack extension in the same solution. Because of the failure of both alloys to meet test acceptance criteria, the tank waste chemistry will have to be restricted or an alternative alloy tested

Phosphorylation-induced changes in the energetic frustration in human Tank binding kinase 1.

Science.gov (United States)

Husain, Shahrukh; Kumar, Vijay; Hassan, Md Imtaiyaz

2018-07-14

Tank binding kinase 1 (TBK-1) plays an important role in immunity, inflammation, autophagy, cell growth and proliferation. Nevertheless, a key molecular and structural detail of TBK-1 phosphorylation and activation has been largely unknown. Here we investigated the energy landscape of phosphorylated (active) and unphosphorylated (inactive) forms of human TBK-1 to characterize the interplay between phosphorylation and local frustration. By employing the algorithm equipped with energy function and implemented in Frustratometer web-server (http://www.frustratometer.tk), we quantify the role of frustration in the activation of TBK-1. Accordingly, the conformational changes were observed in phosphoregulated active and inactive TBK-1. Substantial changes in frustration, flexibility and interatomic motions were observed among different forms of TBK-1. Structurally rigid kinase domain constitutes a minimally frustrated hub in the core of the catalytic domain, and highly frustrated clusters mainly at the C-lobe might enable the conformational transitions during activation. Also, a large network of highly frustrated interactions is found in the SDD domain of TBK-1 involved in protein-protein interactions and dimerization. The contact maps of the activation loop and α-C helix of kinase domain showed significant changes upon phosphorylation. Cross correlation analysis indicate that both intra and inter subunit correlated motions increases with phosphorylation of TBK-1. Phosphorylation thus introduces subtle changes in long-range contacts that might lead to significant conformational change of TBK-1. Copyright © 2018 Elsevier Ltd. All rights reserved.

Diversification of the vacAs1m1 and vacAs2m2 strains of Helicobacter pylori in Meriones unguiculatus

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Sandra Mendoza Elizalde

2016-11-01

Full Text Available The bacterium Helicobacter pylori exhibits great genetic diversity, and the pathogenic roles of its virulence factors have been widely studied. However, the evolutionary dynamics of H. pylori strains during stomach colonization are not well characterized. Here, we analyzed the microevolutionary dynamics of the toxigenic strain vacAs1m1, the non-toxigenic strain vacAs2m2, and a combination of both strains in an animal model over time. Meriones unguiculatus were inoculated with the following bacteria: group 1–toxigenic strain vacAs1m1/cagA+/cagE+/babA2+; ST181, group 2–non-toxigenic strain vacAs2m2/ cagA+/ cagE+/ babA2+; ST2901, and group 3–both strains. The gerbils were euthanized at different time points (3, 6, 12 and 18 months. In group 1, genetic alterations were observed at 6 and 12 months. With the combination of both strains, group 3 also exhibited genetic alterations at 3 and 18 months; moreover, a chimera, vacA m1-m2, was detected. Additionally, four new sequence types (STs were reported in the PubMLST database for H. pylori. Synonymous and non-synonymous mutations were analyzed and associated with alterations in amino acids. Microevolutionary analysis of the STs (PHYLOViZ identified in each group revealed many mutational changes in the toxigenic (vacAs1m1 and non-toxigenic (vacAs2m2 strains. Phylogenetic assessments (eBURST did not reveal clonal complexes. Our findings indicate that the toxigenic strain, vacAs1m1, and a combination of toxigenic and non-toxigenic strains acquired genetic material by recombination. The allelic combination, vacAs2m1, displayed the best adaptation in the animal model over time, and a chimera, m1-m2, was also identified, which confirmed previous reports.

[99mTc[TRODAT-1: a novel technetium-99m complex as a dopamine transporter imaging agent

International Nuclear Information System (INIS)

Kung Meiping; Stevenson, D.A.; Ploessl, K.; Meegalla, S.K.; Beckwith, A.; Essman, W.D.; Mu, M.; Lucki, I.; Kung, H.F.

1997-01-01

Technetium-99m is the most commonly used radionuclide in routine nuclear medicine imaging procedures. Development of 99m Tc-labeled receptor-specific imaging agents for studying the central nervous system is potentially useful for evaluation of brain function in normal and disease states. A novel 99m Tc-labeled tropane derivative, [ 99m Tc[TRODAT-1, which is useful as a potential CNS dopamine transporter imaging agent, was evaluated and characterized. After i.v. injection into rats, [ 99m Tc[TRODAT-1 displayed specific brain uptake in the rat striatal region (striatum-cerebellum/cerebellum ratio 1.8 at 60 min), where dopamine neurons are concentrated. The specific striatal uptake could be blocked by pretreating rats with a dose of competing dopamine transporter ligand, β-CIT (or RTI-55, i.v., 1 mg/kg). However, the specific striatal uptake of [ 99m Tc[TRODAT-1 was not affected by co-injection of excess free ligand (TRODAT-1, up to 200 μg per rat) or by pretreating the rats with haloperidol (i.v., 1 mg/kg). The specific uptake in striatal regions of rats that had prior 6-hydroxydopamine lesion in the substantia nigra area showed a dramatic reduction. The radioactive material recovered from the rat striatal homogenates at 60 min after i.v. injection of [ 99m Tc[TRODAT-1 showed primarily the original compound (>95%), a good indication of in vivo stability in brain tissue. Similar and comparable organ distribution patterns and brain regional uptakes of [ 99m Tc[TRODAT-1 were obtained for male and female rats. (orig./AJ). With 4 figs., 6 tabs

Akt inhibition promotes ABCA1-mediated cholesterol efflux to ApoA-I through suppressing mTORC1.

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Fumin Dong

Full Text Available ATP-binding cassette transporter A1 (ABCA1 plays an essential role in mediating cholesterol efflux to apolipoprotein A-I (apoA-I, a major housekeeping mechanism for cellular cholesterol homeostasis. After initial engagement with ABCA1, apoA-I directly interacts with the plasma membrane to acquire cholesterol. This apoA-I lipidation process is also known to require cellular signaling processes, presumably to support cholesterol trafficking to the plasma membrane. We report here that one of major signaling pathways in mammalian cells, Akt, is also involved. In several cell models that express ABCA1 including macrophages, pancreatic beta cells and hepatocytes, inhibition of Akt increases cholesterol efflux to apoA-I. Importantly, Akt inhibition has little effect on cells expressing non-functional mutant of ABCA1, implicating a specific role of Akt in ABCA1 function. Furthermore, we provide evidence that mTORC1, a major downstream target of Akt, is also a negative regulator of cholesterol efflux. In cells where mTORC1 is constitutively activated due to tuberous sclerosis complex 2 deletion, cholesterol efflux to apoA-I is no longer sensitive to Akt activity. This suggests that Akt suppresses cholesterol efflux through mTORC1 activation. Indeed, inhibition of mTORC1 by rapamycin or Torin-1 promotes cholesterol efflux. On the other hand, autophagy, one of the major pathways of cholesterol trafficking, is increased upon Akt inhibition. Furthermore, Akt inhibition disrupts lipid rafts, which is known to promote cholesterol efflux to apoA-I. We therefore conclude that Akt, through its downstream targets, mTORC1 and hence autophagy, negatively regulates cholesterol efflux to apoA-I.

Tank characterization report for Single-Shell Tank 241-BX-107

International Nuclear Information System (INIS)

Raphael, G.F.

1994-09-01

This study examined and assessed the status, safety issues, composition, and distribution of the wastes contained in the tank 241-BX-107. Historical and most recent information, ranging from engineering structural assessment experiments, process history, monitoring and remediation activities, to analytical core sample data, were compiled and interpreted in an effort to develop a realistic, contemporary profile for the tank BX-107 contents. The results of this is study revealed that tank BX-107, a 2,006,050 L (530,000 gal) cylindrical single-shell, dished-bottom carbon-steel tank in the 200 East Area of the Hanford Site, was classified as sound. It has been interim stabilized and thus contains less than 189,250 L (50,000 gal) of interstitial liquid, and less than 18,925 L (5,000 gal) of supernatant. It has also been partially interim isolated, whereby all inlets to the tank are sealed to prevent inadvertent addition of liquid. At a residual waste level of ∼3.07 m (120.7 ± 2 in. from sidewall bottom or ∼132.9 in. from center bottom), it is estimated that the tank BX-107 contents are equivalent to 1,305,825 L (345,000 gal). The vapor space pressure is at atmospheric. The latest temperature readings, which were taken in July 1994, show a moderate temperature value of 19 degrees C (66 degrees F). Two supernatant samples were collected in 1974 and 1990, prior to interim stabilization. Sludge core samples were obtained in 1979 and 1992

Production of Newcastle Disease Virus by Vero Cells Grown on Cytodex 1 Microcarriers in a 2-Litre Stirred Tank Bioreactor

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Mohd Azmir Arifin

2010-01-01

Full Text Available The aim of this study is to prepare a model for the production of Newcastle disease virus (NDV lentogenic F strain using cell culture in bioreactor for live attenuated vaccine preparation. In this study, firstly we investigated the growth of Vero cells in several culture media. The maximum cell number was yielded by culture of Vero cells in Dulbecco's Modified Eagle Medium (DMEM which was 1.93×106 cells/ml. Secondly Vero cells were grown in two-litre stirred tank bioreactor by using several commercial microcarriers. We achieved the maximum cell concentration about 7.95×105 cells/ml when using Cytodex 1. Later we produced Newcastle Disease virus in stirred tank bioreactor based on the design developed using Taguchi L4 method. Results reveal that higher multiplicity of infection (MOI and size of cell inoculums can yield higher virus titer. Finally, virus samples were purified using high-speed centrifugation based on 3∗∗(3-1 Fractional Factorial Design. Statistical analysis showed that the maximum virus titer can be achieved at virus sample concentration of 58.45% (v/v, centrifugation speed of 13729 rpm, and centrifugation time of 4 hours. As a conclusion, high yield of virus titer could be achieved through optimization of cell culture in bioreactor and separation by high-speed centrifugation.

Tank Space Options Report

International Nuclear Information System (INIS)

BOYLES, V.C.

2001-01-01

A risk-based priority for the retrieval of Hanford Site waste from the 149 single-shell tanks (SSTs) has been adopted as a result of changes to the Hanford Federal Facility Agreement and Consent Order (HFFACO) (Ecology et al. 1997) negotiated in 2000. Retrieval of the first three tanks in the retrieval sequence fills available capacity in the double-shell tanks (DSTs) by 2007. As a result, the HFFACO change established a milestone (M-45-12-TO1) requiring the determination of options that could increase waste storage capacity for single-shell tank waste retrieval. The information will be considered in future negotiations. This document fulfills the milestone requirement. This study presents options that were reviewed for the purpose of increasing waste storage capacity. Eight options are identified that have the potential for increasing capacity from 5 to 10 million gallons, thus allowing uninterrupted single-shell tank retrieval until the planned Waste Treatment Plant begins processing substantial volumes of waste from the double-shell tanks in 2009. The cost of implementing these options is estimated to range from less than $1 per gallon to more than $14 per gallon. Construction of new double-shell tanks is estimated to cost about $63 per gallon. Providing 5 to 10 million gallons of available double-shell tank space could enable early retrieval of 5 to 9 high-risk single-shell tanks beyond those identified for retrieval by 2007. These tanks are A-101, AX-101, AX-103, BY-102, C-107, S-105, S-106, S-108, and S-109 (Garfield et al. 2000). This represents a potential to retrieve approximately 14 million total curies, including 3,200 curies of long-lived mobile radionuclides. The results of the study reflect qualitative analyses conducted to identify promising options. The estimated costs are rough-order-of magnitude and, therefore, subject to change. Implementing some of the options would represent a departure from the current baseline and may adversely impact the

Theoretical descriptions of novel triplet germylenes M1-Ge-M2-M3 (M1 = H, Li, Na, K; M2 = Be, Mg, Ca; M3 = H, F, Cl, Br).

Science.gov (United States)

Kassaee, Mohamad Zaman; Ashenagar, Samaneh

2018-02-06

In a quest to identify new ground-state triplet germylenes, the stabilities (singlet-triplet energy differences, ΔE S-T ) of 96 singlet (s) and triplet (t) M 1 -Ge-M 2 -M 3 species were compared and contrasted at the B3LYP/6-311++G**, QCISD(T)/6-311++G**, and CCSD(T)/6-311++G** levels of theory (M 1  = H, Li, Na, K; M 2  = Be, Mg, Ca; M 3  = H, F, Cl, Br). Interestingly, F-substituent triplet germylenes (M 3  = F) appear to be more stable and linear than the corresponding Cl- or Br-substituent triplet germylenes (M 3  = Cl or Br). Triplets with M 1  = K (i.e., the K-Ge-M 2 -M 3 series) seem to be more stable than the corresponding triplets with M 1  = H, Li, or Na. This can be attributed to the higher electropositivity of potassium. Triplet species with M 3  = Cl behave similarly to those with M 3  = Br. Conversely, triplets with M 3  = H show similar stabilities and linearities to those with M 3  = F. Singlet species of formulae K-Ge-Ca-Cl and K-Ge-Ca-Br form unexpected cyclic structures. Finally, the triplet germylenes M 1 -Ge-M 2 -M 3 become more stable as the electropositivities of the α-substituents (M 1 and M 2 ) and the electronegativity of the β-substituent (M 3 ) increase.

Phase 1 RCRA Facility Investigation & Corrective Measures Study Work Plan for Single Shell Tank (SST) Waste Management Areas

Energy Technology Data Exchange (ETDEWEB)

MCCARTHY, M.M.

1999-08-01

This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly.

A Shift in ApoM/S1P Between HDL-Particles in Women With Type 1 Diabetes Mellitus Is Associated With Impaired Anti-Inflammatory Effects of the ApoM/S1P Complex.

Science.gov (United States)

Frej, Cecilia; Mendez, Armando J; Ruiz, Mario; Castillo, Melanie; Hughes, Thomas A; Dahlbäck, Björn; Goldberg, Ronald B

2017-06-01

Type 1 diabetes mellitus (T1D) patients have an increased risk of cardiovascular disease despite high levels of high-density lipoproteins (HDL). Apolipoprotein M (apoM) and its ligand sphingosine 1-phospate (S1P) exert many of the anti-inflammatory effects of HDL. We investigated whether apoM and S1P are altered in T1D and whether apoM and S1P are important for HDL functionality in T1D. ApoM and S1P were quantified in plasma from 42 healthy controls and 89 T1D patients. HDL was isolated from plasma and separated into dense, medium-dense, and light HDL by ultracentrifugation. Primary human aortic endothelial cells were challenged with tumor necrosis factor-α in the presence or absence of isolated HDL. Proinflammatory adhesion molecules E-selectin and vascular cellular adhesion molecule-1 were quantified by flow cytometry. Activation of the S1P 1 - receptor was evaluated by analyzing downstream signaling targets and receptor internalization. There were no differences in plasma levels of apoM and S1P between controls and T1D patients, but the apoM/S1P complexes were shifted from dense to light HDL particles in T1D. ApoM/S1P in light HDL particles from women were less efficient in inhibiting expression of vascular cellular adhesion molecule-1 than apoM/S1P in denser particles. The light HDL particles were unable to activate Akt, whereas all HDL subfractions were equally efficient in activating Erk and receptor internalization. ApoM/S1P in light HDL particles were inefficient in inhibiting tumor necrosis factor-α-induced vascular cellular adhesion molecule-1 expression in contrast to apoM/S1P in denser HDL particles. T1D patients have a higher proportion of light particles and hence more dysfunctional HDL, which could contribute to the increased cardiovascular disease risk associated with T1D. © 2017 American Heart Association, Inc.

Minutes of the Tank Waste Science Panel meeting July 9--1, 1991

International Nuclear Information System (INIS)

Strachan, D.M.

1992-04-01

The fifth meeting of the Tank Waste Science Panel was held July 9--11, 1991, in Atlanta, Georgia. The subject areas included the generation, retention, and release of gases from Tank 241-SY-101 and the chemistry of ferrocyanide wastes

CRITICAL ASSUMPTIONS IN THE F-TANK FARM CLOSURE OPERATIONAL DOCUMENTATION REGARDING WASTE TANK INTERNAL CONFIGURATIONS

Energy Technology Data Exchange (ETDEWEB)

Hommel, S.; Fountain, D.

2012-03-28

The intent of this document is to provide clarification of critical assumptions regarding the internal configurations of liquid waste tanks at operational closure, with respect to F-Tank Farm (FTF) closure documentation. For the purposes of this document, FTF closure documentation includes: (1) Performance Assessment for the F-Tank Farm at the Savannah River Site (hereafter referred to as the FTF PA) (SRS-REG-2007-00002), (2) Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site (DOE/SRS-WD-2012-001), (3) Tier 1 Closure Plan for the F-Area Waste Tank Systems at the Savannah River Site (SRR-CWDA-2010-00147), (4) F-Tank Farm Tanks 18 and 19 DOE Manual 435.1-1 Tier 2 Closure Plan Savannah River Site (SRR-CWDA-2011-00015), (5) Industrial Wastewater Closure Module for the Liquid Waste Tanks 18 and 19 (SRRCWDA-2010-00003), and (6) Tank 18/Tank 19 Special Analysis for the Performance Assessment for the F-Tank Farm at the Savannah River Site (hereafter referred to as the Tank 18/Tank 19 Special Analysis) (SRR-CWDA-2010-00124). Note that the first three FTF closure documents listed apply to the entire FTF, whereas the last three FTF closure documents listed are specific to Tanks 18 and 19. These two waste tanks are expected to be the first two tanks to be grouted and operationally closed under the current suite of FTF closure documents and many of the assumptions and approaches that apply to these two tanks are also applicable to the other FTF waste tanks and operational closure processes.

Organic tanks safety program, FY97 waste aging studies. Revision 1

International Nuclear Information System (INIS)

Camaioni, D.M.; Samuels, W.D.; Linehan, J.C.; Sharma, A.K.; Hogan, M.O.; Lilga, M.A.; Clauss, S.A.; Wahl, K.L.; Campbell, J.A.

1998-02-01

To model tank waste aging and interpret tank waste speciation results, the authors began measuring the reactivity of organic complexants and related compounds towards radiation-induced oxidation reactions. Because of the high efficiency of scavenging of the primary radicals of water radiolysis by nitrate and nitrite ion, the major radiolytically-generated radicals in these solutions, and in Hanford tank wastes, are NO 2 , NO and O - . Prior to this effort, little quantitative information existed for the reactions of these radicals with organic compounds such as those that were used in Hanford processes. Therefore, modeling of actual waste aging, or even simulated waste aging, was not feasible without measuring reactivities and determining reaction paths. The authors have made the first rate measurements of complexant aging and determined some of their degradation products

Power Projection: The Current and Future Relevance of the M1A1Tank to Marine Corps Capabilities

Science.gov (United States)

2002-01-01

Kenneth W. Estes, Marines under Armor : The Marine Corps and the Armored Fighting Vehicle, 1916-2000 (Annapolis, MD: Naval institute Press, 2000), 183...is the M2 heavy barrel machine gun that has been in the U.S. inventory for decades. It can be fired from under armor and has a range of 1800 meters...Accessed 9 January 2002. Estes, Kenneth W. Marines under Armor : The Marine Corps and the Armored Fighting Vehicle, 1916-2000. Annapolis, MD

Overexpression of the polycystin-1 (PC-1) C-tail enhances sensitivity of M-1 cells to ouabain

Science.gov (United States)

Jansson, Kyle; Magenheimer, Brenda S.; Maser, Robin L.; Calvet, James P.; Blanco, Gustavo

2014-01-01

Cells derived from renal cysts of patients with autosomal dominant polycystic kidney disease (ADPKD) are abnormally sensitive to ouabain, responding to physiological ouabain concentrations with enhanced proliferation and increased forskolin-induced transepithelial fluid secretion. This requires activation of the epidermal growth factor receptor (EGFR), Src kinase, and the extracellular regulated kinases MEK and ERK. Here, we have determined if the ADPKD phenotype obtained in mouse cortical collecting duct cells by stable overexpression of the C-terminal domain of polycystin-1 (PC-1 C-tail) also elicits the ADPKD-like response to ouabain in the cells. M-1 C20 cells expressing the PC-1 C-tail, and M-1 C17 cells, lacking expression of this construct, were treated with physiological concentrations of ouabain, and cell proliferation, activation of the EGFR-Src-MEK-ERK pathway, forskolin-induced transepithelial Cl− secretion, and the sensitivity of the Na,K-ATPase to ouabain were explored. M-1 C20 cells responded to ouabain with increased cell proliferation and ERK phosphorylation. Ouabain also augmented forskolin-induced and cystic fibrosis transmembrane conductance regulator (CFTR)-mediated apical secretion of Cl− in M-1 C20 cells. These effects required activation of EGFR, Src and MEK. In contrast, ouabain had no significant effects on M-1 C17 cells. Interestingly, approximately 20 % of the Na,K-ATPase from M-1 C20 cells presented an abnormally increased sensitivity to ouabain. Overexpression of PC-1 C-tail in M-1 C20 cells is associated with a ouabain sensitive phenotype and an increased ability of the cells to proliferate and secrete anions upon ouabain stimulation. This phenotype mimics the ouabain sensitivity of ADPKD cells and may help promote their cystogenic potential. PMID:23784065

Tank Closure Progress at the Department of Energy's Idaho National Engineering Laboratory Tank Farm Facility

International Nuclear Information System (INIS)

Butterworth, St.W.; Shaw, M.R.

2009-01-01

Significant progress continued at the U.S. Department of Energy (DOE) Idaho National Laboratory (INL) with the completion of the closure process to empty, clean and close radioactive liquid waste storage tanks at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF). The TFF includes eleven 1,135.6-kL (300,000-gal) underground stainless steel storage tanks and four smaller, 113.5-kL (30,000-gal) stainless steel tanks, along with tank vaults, interconnecting piping, and ancillary equipment. The TFF tanks had historically been used to store a variety of radioactive liquid waste, including wastes associated with past spent nuclear fuel reprocessing. Four of the large storage tanks remain in use for waste storage while the other seven 1,135.6-kL (300,000-gal) tanks and the four 113.5-kL (30,000-gal) tanks have been emptied of waste, cleaned and filled with grout. Recent issuance of an Amended Record of Decision (ROD) in accordance with the National Environmental Policy Act, and a Waste Determination complying with Section 3116 of the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, allowed commencement of grouting activities on the cleaned tanks. The first three 113.5-kL (30,000-gal) tanks were grouted in the Fall of 2006 and the fourth tank and the seven 1,135.6-kL (300,000-gal) tanks were filled with grout in 2007 to provide long-term stability. During 2008 over seven miles of underground process piping along with associated tank valve boxes and secondary containment systems was stabilized with grout. Lessons learned were compiled and implemented during the closure process and will be utilized on the remaining four 1,135.6-kL (300,000-gal) underground stainless steel storage tanks. Significant progress has been made to clean and close emptied tanks at the INTEC TFF. Between 2002 and 2005, seven of the eleven 1,135.6-kL (300,000-gal) tanks and all four 113.5-kL (30,000-gal) tanks were cleaned and prepared

hnRNP A2/B1 interacts with influenza A viral protein NS1 and inhibits virus replication potentially through suppressing NS1 RNA/protein levels and NS1 mRNA nuclear export

Energy Technology Data Exchange (ETDEWEB)

Wang, Yimeng; Zhou, Jianhong; Du, Yuchun, E-mail: ydu@uark.edu

2014-01-20

The NS1 protein of influenza viruses is a major virulence factor and exerts its function through interacting with viral/cellular RNAs and proteins. In this study, we identified heterogeneous nuclear ribonucleoprotein A2/B1 (hnRNP A2/B1) as an interacting partner of NS1 proteins by a proteomic method. Knockdown of hnRNP A2/B1 by small interfering RNA (siRNA) resulted in higher levels of NS vRNA, NS1 mRNA, and NS1 protein in the virus-infected cells. In addition, we demonstrated that hnRNP A2/B1 proteins are associated with NS1 and NS2 mRNAs and that knockdown of hnRNP A2/B1 promotes transport of NS1 mRNA from the nucleus to the cytoplasm in the infected cells. Lastly, we showed that knockdown of hnRNP A2/B1 leads to enhanced virus replication. Our results suggest that hnRNP A2/B1 plays an inhibitory role in the replication of influenza A virus in host cells potentially through suppressing NS1 RNA/protein levels and NS1 mRNA nucleocytoplasmic translocation. - Highlights: • Cellular protein hnRNP A2/B1 interacts with influenza viral protein NS1. • hnRNP A2/B1 suppresses the levels of NS1 protein, vRNA and mRNA in infected cells. • hnRNP A2/B1 protein is associated with NS1 and NS2 mRNAs. • hnRNP A2/B1 inhibits the nuclear export of NS1 mRNAs. • hnRNP A2/B1 inhibits influenza virus replication.

Tank Farms Technical Safety Requirements. Volume 1 and 2

International Nuclear Information System (INIS)

CASH, R.J.

2000-01-01

The Technical Safety Requirements (TSRs) define the acceptable conditions, safe boundaries, basis thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR)

Tank Farms Technical Safety Requirements [VOL 1 and 2

Energy Technology Data Exchange (ETDEWEB)

CASH, R.J.

2000-12-28

The Technical Safety Requirements (TSRs) define the acceptable conditions, safe boundaries, basis thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR).

GST M1-T1 null allele frequency patterns in geographically assorted human populations: a phylogenetic approach.

Directory of Open Access Journals (Sweden)

Senthilkumar Pitchalu Kasthurinaidu

Full Text Available Genetic diversity in drug metabolism and disposition is mainly considered as the outcome of the inter-individual genetic variation in polymorphism of drug-xenobiotic metabolizing enzyme (XME. Among the XMEs, glutathione-S-transferases (GST gene loci are an important candidate for the investigation of diversity in allele frequency, as the deletion mutations in GST M1 and T1 genotypes are associated with various cancers and genetic disorders of all major Population Affiliations (PAs. Therefore, the present population based phylogenetic study was focused to uncover the frequency distribution pattern in GST M1 and T1 null genotypes among 45 Geographically Assorted Human Populations (GAHPs. The frequency distribution pattern for GST M1 and T1 null alleles have been detected in this study using the data derived from literatures representing 44 populations affiliated to Africa, Asia, Europe, South America and the genome of PA from Gujarat, a region in western India. Allele frequency counting for Gujarat PA and scattered plot analysis for geographical distribution among the PAs were performed in SPSS-21. The GST M1 and GST T1 null allele frequencies patterns of the PAs were computed in Seqboot, Gendist program of Phylip software package (3.69 versions and Unweighted Pair Group method with Arithmetic Mean in Mega-6 software. Allele frequencies from South African Xhosa tribe, East African Zimbabwe, East African Ethiopia, North African Egypt, Caucasian, South Asian Afghanistan and South Indian Andhra Pradesh have been identified as the probable seven patterns among the 45 GAHPs investigated in this study for GST M1-T1 null genotypes. The patternized null allele frequencies demonstrated in this study for the first time addresses the missing link in GST M1-T1 null allele frequencies among GAHPs.

INVESTIGATING SUSPENSION OF MST SLURRIES IN A PILOT-SCALE WASTE TANK

Energy Technology Data Exchange (ETDEWEB)

Poirier, M.; Restivo, M.; Steeper, T.; Williams, M.; Qureshi, Z.

2011-01-24

The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for suspending monosodium titanate (MST), crystalline silicotitanate (CST), and simulated sludge. The purpose of this pilot scale testing is for the pumps to suspend the MST particles so that MST can be removed from the tank. The pilot-scale tank is a 1/10.85 linear scaled model of Tank 41H. The tank diameter, tank liquid level, pump nozzle diameter, pump elevation, and cooling coil diameter are all 1/10.85 of their dimensions in Tank 41H. The pump locations correspond to the proposed locations in Tank 41H by the SCIX program (Risers B5 and B2 for two pump configurations and Risers B5, B3, and B1 for three pump configurations).

Remote inspection of underground storage tanks

International Nuclear Information System (INIS)

Griebenow, B.L.; Martinson, L.M.

1992-01-01

Westinghouse Idaho Nuclear Company, Inc. (WINCO) operates the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy. The ICPP's mission is to process government-owned spent nuclear fuel. The process involves dissolving the fuel, extracting off uranium, and calcining the waste to a solid form for storage, Prior to calcining, WINCO temporarily stores the liquid waste from this process in eleven 1,135,600-l(300,000-gal), 15,2-m (50-ft)-diam, high-level liquid waste tanks. Each of these stainless steel tanks is contained within an underground concrete vault. The only access to the interior of the tanks is through risers that extend from ground level to the dome of the tanks. WINCO is replacing these tanks because of their age and the fact that they do not meet all of the current design requirements. The tanks will be replaced in two phases. WINCO is now in the Title I design stage for four new tank and vault systems to replace five of the existing systems. The integrity of the six remaining tanks must be verified to continue their use until they can be replaced in the second phase. To perform any integrity analysis, the inner surface of the tanks must be inspected. The remote tank inspection (RTI) robotic system, designed by RedZone Robotics of Pittsburgh, Pennsylvania, was developed to access the interior of the tanks and position various end effectors required to perform tank wall inspections

Interaction between NBS1 and the mTOR/Rictor/SIN1 complex through specific domains.

Directory of Open Access Journals (Sweden)

Jian-Qiu Wang

Full Text Available Nijmegen breakage syndrome (NBS is a chromosomal-instability syndrome. The NBS gene product, NBS1 (p95 or nibrin, is a part of the Mre11-Rad50-NBS1 complex. SIN1 is a component of the mTOR/Rictor/SIN1 complex mediating the activation of Akt. Here we show that NBS1 interacted with mTOR, Rictor, and SIN1. The specific domains of mTOR, Rictor, or SIN1 interacted with the internal domain (a.a. 221-402 of NBS1. Sucrose density gradient showed that NBS1 was located in the same fractions as the mTOR/Rictor/SIN1 complex. Knockdown of NBS1 decreased the levels of phosphorylated Akt and its downstream targets. Ionizing radiation (IR increased the NBS1 levels and activated Akt activity. These results demonstrate that NBS1 interacts with the mTOR/Rictor/SIN1 complex through the a.a. 221-402 domain and contributes to the activation of Akt activity.

Development of a hot water tank simulation program with improved prediction of thermal stratification in the tank

DEFF Research Database (Denmark)

Fan, Jianhua; Furbo, Simon; Yue, Hongqiang

2015-01-01

A simulation program SpiralSol was developed in previous investigations to calculate thermal performance of a solar domestic hot water (SDHW) system with a hot water tank with a built-in heat exchanger spiral [1]. The simulation program is improved in the paper in term of prediction of thermal...... stratification in the tank. The transient fluid flow and heat transfer in the hot water tank during cooling caused by standby heat loss are investigated by validated computational fluid dynamics (CFD) calculations. Detailed CFD investigations are carried out to determine the influence of thickness and material...... property of the tank wall on thermal stratification in the tank. It is elucidated how thermal stratification in the tank is influenced by the natural convection and how the heat loss from the tank sides will be distributed at different levels of the tank at different thermal conditions. The existing...

26 CFR 1.401(m)-2 - ACP test.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 5 2010-04-01 2010-04-01 false ACP test. 1.401(m)-2 Section 1.401(m)-2 Internal... TAXES Pension, Profit-Sharing, Stock Bonus Plans, Etc. § 1.401(m)-2 ACP test. (a) Actual contribution percentage (ACP) test—(1) In general—(i) ACP test formula. A plan satisfies the ACP test for a plan year only...

Tank 244A tank characterization plan

International Nuclear Information System (INIS)

Schreiber, R.D.

1994-01-01

The Double-Shell Tank (DST) System currently receives waste from the Single-Shell Tank (SST) System in support of SST stabilization efforts or from other on-site facilities which generate or store waste. Waste is also transferred between individual DSTs. The mixing or commingling of potentially incompatible waste types at the Hanford Site must be addressed prior to any waste transfers into the DSTs. The primary goal of the Waste Compatibility Program is to prevent the formation of an Unreviewed Safety Question (USQ) as a result of improper waste management. Tank 244A is a Double Contained Receiver Tank (DCRT) which serves as any overflow tank for the East Area Farms. Waste material is able to flow freely between the underground storage tanks and tank 244A. Therefore, it is necessary to test the waste in tank 244A for compatibility purposes. Two issues related to the overall problem of waste compatibility must be evaluated: Assurance of continued operability during waste transfer and waste concentration and Assurance that safety problems are not created as a result of commingling wastes under interim storage. The results of the grab sampling activity prescribed by this Tank Characterization Plan shall help determine the potential for four kinds of safety problems: criticality, flammable gas accumulation, energetics, and corrosion and leakage

Assessment of TRAC-PF1/MOD3 Mark-22 assembly model using SRL ''A'' tank single-assembly flow experiments

International Nuclear Information System (INIS)

Fischer, S.R.; Lam, K.; Lin, J.C.

1991-01-01

This paper summarizes the results of an assessment of our TRAC-PF1/MOD3 Mark-22 prototype fuel assembly model against single-assembly data obtained from the ''A'' Tank single-assembly tests that were performed at the Savannah River Laboratory. We felt the data characterize prototypic assembly behavior over a range of air-water flow conditions of interest for loss-of-coolant accident (LOCA) calculations. This study was part of a benchmarking effort performed to evaluate and validate a multiple-assembly, full-plant model that is being developed by Los Alamos National Laboratory to study various aspects of the Savannah River plant operating conditions, including LOCA transients, using TRAC-PF1/MOD3 Version 1.10. The results of this benchmarking effort demonstrate that TRAC-PF1/MOD3 is capable pf calculating plenum conditions and assembly flows during conditions thought to be typical of the Emergency Cooling System (ECS) phase of a LOCA. 10 refs., 12 fig

49 CFR 231.8 - Tank cars without side sills and tank cars with short side sills and end platforms.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Tank cars without side sills and tank cars with... APPLIANCE STANDARDS § 231.8 Tank cars without side sills and tank cars with short side sills and end platforms. (a) Hand brakes—(1) Number. Same as specified for “Box and other house cars” (see § 231.1(a)(1...

The modulation of enzyme indoleamine 2,3-dioxygenase from dendritic cells for the treatment of type 1 diabetes mellitus

OpenAIRE

Abram, D?bora Moitinho; Fernandes, Luis Gustavo Romani; Ramos Filho, Ant?nio Celso Saragossa; Simioni, Patr?cia Ucelli

2017-01-01

Débora Moitinho Abram,1 Luis Gustavo Romani Fernandes,1,2 Antônio Celso Saragossa Ramos Filho,2 Patrícia Ucelli Simioni2–4 1Department of Internal Medicine, Faculty of Medical Sciences, University of Campinas, Cidade Universitária Zeferino Vaz, Campinas, SP, Brazil; 2Department of Biomedical Science, Faculty of Americana, Americana, SP, Brazil; 3Department of Genetics, Evolution and Bioagents, Institute of Biology, University of Campinas (...

Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 1: Procedural overview

International Nuclear Information System (INIS)

2007-01-01

Accurate determinations of volume are a fundamental component of any measurement-based system of control and accountability in a facility that processes or stores nuclear materials in liquid form. Volume determinations are typically made with the aid of a calibration or volume measurement equation that relates the response of the tank's measurement system to some independent measure of tank volume. The ultimate purpose of the calibration exercise is to estimate the tank's volume measurement equation (the inverse of the calibration equation), which relates tank volume to measurement system response. The steps carried out to acquire data for estimating the tank's calibration or volume measurement equation are collectively described as the process of tank calibration. This part of ISO 18213 describes procedures for tank calibration and volume determination for nuclear process tanks equipped with pressure-measurement systems for determining liquid content. Specifically, overall guidance is provided for planning a calibration exercise undertaken to obtain the data required for the measurement equation to estimate a tank's volume. The key steps in the procedure are also presented for subsequently using the estimated volume-measurement equation to determine tank liquid volumes. The procedures presented apply specifically to tanks equipped with bubbler probe systems for measuring liquid content. Moreover, these procedures produce reliable results only for clear (i.e. without suspended solids), homogeneous liquids that are at both thermal and static equilibrium. The paper elaborates on scope, physical principles involved, the calibration model, equipment required, a typical tank calibration procedure, calibration planning and pre-calibration activities, and volume determination. A bibliography is provided

Development Of A Numerical Tow Tank With Wave Generation To Supplement Experimental Efforts

Science.gov (United States)

2017-12-01

meters (24 inches), a maximum thrust of 1779.3 newtons ( 400 pounds), and a maximum linear speed of 0.4064 m/s (16.0 in/s). 17 3.3 Data Collection...has a small tow tank built in the 1970s. This 10.97 meter (36 foot) long facility is short by academic standards and has lacked wave generation...PAGE INTENTIONALLY LEFT BLANK 14 CHAPTER 3: Experimental Setup 3.1 Description of Experimental Facility The experimental tow tank is 10.97 meters (36.0

Tank 4 Characterization, Settling, And Washing Studies

International Nuclear Information System (INIS)

Bannochie, C.; Pareizs, J.; Click, D.; Zamecnik, J.

2009-01-01

A sample of PUREX sludge from Tank 4 was characterized, and subsequently combined with a Tank 51 sample (Tank 51-E1) received following Al dissolution, but prior to a supernate decant by the Tank Farm, to perform a settling and washing study to support Sludge Batch 6 preparation. The sludge source for the majority of the Tank 51-E1 sample is Tank 12 HM sludge. The Tank 51-E1 sample was decanted by SRNL prior to use in the settling and washing study. The Tank 4 sample was analyzed for chemical composition including noble metals. The characterization of the Tank 51-E1 sample, used here in combination with the Tank 4 sample, was reported previously. SRNL analyses on Tank 4 were requested by Liquid Waste Engineering (LWE) via Technical Task Request (TTR) HLE-TTR-2009-103. The sample preparation work is governed by Task Technical and Quality Assurance Plan (TTQAP), and analyses were controlled by an Analytical Study Plan and modifications received via customer communications. Additional scope included a request for a settling study of decanted Tank 51-E1 and a blend of decanted Tank 51-E1 and Tank 4, as well as a washing study to look into the fate of undissolved sulfur observed during the Tank 4 characterization. The chemistry of the Tank 4 sample was modeled with OLI Systems, Inc. StreamAnalyzer to determine the likelihood that sulfate could exist in this sample as insoluble Burkeite (2Na 2 SO 4 · Na 2 CO 3 ). The OLI model was also used to predict the composition of the blended tank materials for the washing study. The following conclusions were drawn from the Tank 4 analytical results reported here: (1) Any projected blend of Tank 4 and the current Tank 51 contents will produce a SB6 composition that is lower in Ca and U than the current SB5 composition being processed by DWPF. (2) Unwashed Tank 4 has a relatively large initial S concentration of 3.68 wt% on a total solids basis, and approximately 10% of the total S is present as an insoluble or undissolved form

Energy consumption of agitators in activated sludge tanks - actual state and optimization potential.

Science.gov (United States)

Füreder, K; Svardal, K; Frey, W; Kroiss, H; Krampe, J

2018-02-01

Depending on design capacity, agitators consume about 5 to 20% of the total energy consumption of a wastewater treatment plant. Based on inhabitant-specific energy consumption (kWh PE 120 -1 a -1 ; PE 120 is population equivalent, assuming 120 g chemical oxygen demand per PE per day), power density (W m -3 ) and volume-specific energy consumption (Wh m -3 d -1 ) as evaluation indicators, this paper provides a sound contribution to understanding energy consumption and energy optimization potentials of agitators. Basically, there are two ways to optimize agitator operation: the reduction of the power density and the reduction of the daily operating time. Energy saving options range from continuous mixing with low power densities of 1 W m -3 to mixing by means of short, intense energy pulses (impulse aeration, impulse stirring). However, the following correlation applies: the shorter the duration of energy input, the higher the power density on the respective volume-specific energy consumption isoline. Under favourable conditions with respect to tank volume, tank geometry, aeration and agitator position, mixing energy can be reduced to 24 Wh m -3 d -1 and below. Additionally, it could be verified that power density of agitators stands in inverse relation to tank volume.

Efficacy of magnetoacustoradiation treatment of experimental M-1, PC-1 tumors

International Nuclear Information System (INIS)

Chizh, D.V.; Krutilina, N.I.

2011-01-01

The urgency of the struggle against malignant tumors is determined by a stable growth of cancer incidence, high level of disability and morbidity, the cost and difficulty of treatment. The influence of low-frequency ultrasound and alternating magnetic field on transplanted tumors of sarcoma M-1 and alveolar liver cancer PC-1 together with radiation therapy at a SFD of 5 Gy and 20 Gy was investigated in the experiments on animals. It was established that the influence of the above physical factors inhibited sarcoma M-1 and alveolar liver cancer PC-1 growth, prolonged the life and survival of the animals of the investigated groups when compared to the intact controls, which definitely expanded the ideas about the capabilities of ultrasound and magnetic fields in cancer treatment.

M1 transitions in the (sdg) boson model

Energy Technology Data Exchange (ETDEWEB)

Kuyucak, S.; Morrison, I.

1988-03-03

Using the 1/N expansion technique we derive expressions for ..beta.. -> g, ..gamma.. -> g and ..gamma.. -> ..gamma.. M1 transitions in a general boson model. The M1 matrix elements in the sdg-boson model are similar in form to those in the neutron-proton IBM. Comparisons are made to some selected M1 data exhibiting collective character.

Dynamin-dependent amino acid endocytosis activates mechanistic target of rapamycin complex 1 (mTORC1).

Science.gov (United States)

Shibutani, Shusaku; Okazaki, Hana; Iwata, Hiroyuki

2017-11-03

The mechanistic target of rapamycin complex 1 (mTORC1) is a master regulator of protein synthesis and potential target for modifying cellular metabolism in various conditions, including cancer and aging. mTORC1 activity is tightly regulated by the availability of extracellular amino acids, and previous studies have revealed that amino acids in the extracellular fluid are transported to the lysosomal lumen. There, amino acids induce recruitment of cytoplasmic mTORC1 to the lysosome by the Rag GTPases, followed by mTORC1 activation by the small GTPase Ras homolog enriched in brain (Rheb). However, how the extracellular amino acids reach the lysosomal lumen and activate mTORC1 remains unclear. Here, we show that amino acid uptake by dynamin-dependent endocytosis plays a critical role in mTORC1 activation. We found that mTORC1 is inactivated when endocytosis is inhibited by overexpression of a dominant-negative form of dynamin 2 or by pharmacological inhibition of dynamin or clathrin. Consistently, the recruitment of mTORC1 to the lysosome was suppressed by the dynamin inhibition. The activity and lysosomal recruitment of mTORC1 were rescued by increasing intracellular amino acids via cycloheximide exposure or by Rag overexpression, indicating that amino acid deprivation is the main cause of mTORC1 inactivation via the dynamin inhibition. We further show that endocytosis inhibition does not induce autophagy even though mTORC1 inactivation is known to strongly induce autophagy. These findings open new perspectives for the use of endocytosis inhibitors as potential agents that can effectively inhibit nutrient utilization and shut down the upstream signals that activate mTORC1. © 2017 by The American Society for Biochemistry and Molecular Biology, Inc.

Stabilization of in-tank residual wastes and external-tank soil contamination for the tank focus area, Hanford Tank Initiative: Applications to the AX tank farm

International Nuclear Information System (INIS)

Becker, D.L.

1997-01-01

This report investigates five technical areas for stabilization of decommissioned waste tanks and contaminated soils at the Hanford Site AX Farm. The investigations are part of a preliminary evacuation of end-state options for closure of the AX Tanks. The five technical areas investigated are: (1) emplacement of cementations grouts and/or other materials; (2) injection of chemicals into contaminated soils surrounding tanks (soil mixing); (3) emplacement of grout barriers under and around the tanks; (4) the explicit recognition that natural attenuation processes do occur; and (5) combined geochemical and hydrological modeling. Research topics are identified in support of key areas of technical uncertainty, in each of the five areas. Detailed cost-benefit analyses of the technologies are not provided. This investigation was conducted by Sandia National Laboratories, Albuquerque, New Mexico, during FY 1997 by tank Focus Area (EM-50) funding

[{sup 99m}Tc]TRODAT-1: a novel technetium-99m complex as a dopamine transporter imaging agent

Energy Technology Data Exchange (ETDEWEB)

Meiping, Kung [Department of Radiology, University of Pennsylvania, Philadelphia (United States); Stevenson, D A [Department of Radiology, University of Pennsylvania, Philadelphia (United States); Ploessl, K [Department of Radiology, University of Pennsylvania, Philadelphia (United States); Meegalla, S K [Department of Radiology, University of Pennsylvania, Philadelphia (United States); Beckwith, A [Department of Radiology, University of Pennsylvania, Philadelphia (United States); Essman, W D [Department of Psychiatry, University of Pennsylvania, Philadelphia (United States); Mu, M [Department of Radiology, University of Pennsylvania, Philadelphia (United States); Lucki, I [Department of Psychiatry, University of Pennsylvania, Philadelphia (United States); [Department of Pharmacology, University of Pennsylvania, Philadelphia (United States); Kung, H F [Department of Radiology, University of Pennsylvania, Philadelphia (United States); [Department of Pharmacology, University of Pennsylvania, Philadelphia (United States)

1997-04-01

Technetium-99m is the most commonly used radionuclide in routine nuclear medicine imaging procedures. Development of {sup 99m}Tc-labeled receptor-specific imaging agents for studying the central nervous system is potentially useful for evaluation of brain function in normal and disease states. A novel {sup 99m}Tc-labeled tropane derivative, [{sup 99m}Tc]TRODAT-1, which is useful as a potential CNS dopamine transporter imaging agent, was evaluated and characterized. After i.v. injection into rats, [{sup 99m}Tc]TRODAT-1 displayed specific brain uptake in the rat striatal region (striatum-cerebellum/cerebellum ratio 1.8 at 60 min), where dopamine neurons are concentrated. The specific striatal uptake could be blocked by pretreating rats with a dose of competing dopamine transporter ligand, {beta}-CIT (or RTI-55, i.v., 1 mg/kg). However, the specific striatal uptake of [{sup 99m}Tc]TRODAT-1 was not affected by co-injection of excess free ligand (TRODAT-1, up to 200 {mu}g per rat) or by pretreating the rats with haloperidol (i.v., 1 mg/kg). The specific uptake in striatal regions of rats that had prior 6-hydroxydopamine lesion in the substantia nigra area showed a dramatic reduction. The radioactive material recovered from the rat striatal homogenates at 60 min after i.v. injection of [{sup 99m}Tc]TRODAT-1 showed primarily the original compound (>95%), a good indication of in vivo stability in brain tissue. Similar and comparable organ distribution patterns and brain regional uptakes of [{sup 99m}Tc]TRODAT-1 were obtained for male and female rats. (orig./AJ). With 4 figs., 6 tabs.

China Dimensions Data Collection: Fundamental GIS: Digital Chart of China, 1:1M, Version 1

Data.gov (United States)

National Aeronautics and Space Administration — Fundamental GIS: Digital Chart of China, 1:1M, Version 1 consists of vector maps of China and surrounding areas. The maps include roads, railroads, drainage systems,...

SU-E-T-118: Analysis of Variability and Stability Between Two Water Tank Phantoms Utilizing Water Tank Commissioning Procedures

International Nuclear Information System (INIS)

Roring, J; Saenz, D; Cruz, W; Papanikolaou, N; Stathakis, S

2015-01-01

Purpose: The commissioning criteria of water tank phantoms are essential for proper accuracy and reproducibility in a clinical setting. This study outlines the results of mechanical and dosimetric testing between PTW MP3-M water tank system and the Standard Imaging Doseview 3D water tank system. Methods: Measurements were taken of each axis of movement on the tank using 30 cm calipers at 1, 5, 10, 50, 100, and 200 mm for accuracy and reproducibility of tank movement. Dosimetric quantities such as percent depth dose and dose profiles were compared between tanks using a 6 MV beam from a Varian 23EX LINAC. Properties such as scanning speed effects, central axis depth dose agreement with static measurements, reproducibility of measurements, symmetry and flatness, and scan time between tanks were also investigated. Results: Results showed high geometric accuracy within 0.2 mm. Central axis PDD and in-field profiles agreed within 0.75% between the tanks. These outcomes test many possible discrepancies in dose measurements across the two tanks and form a basis for comparison on a broader range of tanks in the future. Conclusion: Both 3D water scanning phantoms possess a high degree of spatial accuracy, allowing for equivalence in measurements regardless of the phantom used. A commissioning procedure when changing water tanks or upon receipt of a new tank is nevertheless critical to ensure consistent operation before and after the arrival of new hardware

Tank characterization report for single-shell tank 241-BY-112

International Nuclear Information System (INIS)

Baldwin, J.H.

1997-01-01

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BY-112. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10. (This tank has been designated a Ferrocyanide Watch List tank.)

M1 transitions in the (sdg) boson model

Science.gov (United States)

Kuyucak, S.; Morrison, I.

1988-03-01

Using the {1}/{N} expansion technique we derive expressions for β→g, γ→g and γ→γ M1 transitions in a general boson model. The M1 matrix elements in the sdg-boson model are similar in form to those in the neutron-proton IBM. Comparisons are made to some selected M1 data exhibiting collective character.

M1 transitions in the (sdg) boson model

International Nuclear Information System (INIS)

Kuyucak, S.; Tuebingen Univ.; Morrison, I.

1988-01-01

Using the 1/N expansion technique we derive expressions for β → g, γ → g and γ → γ M1 transitions in a general boson model. The M1 matrix elements in the sdg-boson model are similar in form to those in the neutron-proton IBM. Comparisons are made to some selected M1 data exhibiting collective character. (orig.)

1/12-Scale mixing interface visualization and buoyant particle release tests in support of Tank 241-SY-101 hydrogen mitigation

Energy Technology Data Exchange (ETDEWEB)

Eschbach, E.J.; Enderlin, C.W.

1993-10-01

In support of tank waste safety programs, visualization tests were performed in the 1/12-scale tank facility, using a low-viscosity simulant. The primary objective of the tests was to obtain video records of the transient jet-sludge interaction. The intent is that these videos will provide useful qualitative data for comparison with model predictions. Two tests were initially planned: mixing interface visualization (MIV) and buoyant particle release (BPR). Completion of the buoyant particle release test was set aside in order to complete additional MIV tests. Rheological measurements were made on simulant samples before testing, and the simulant was found to exhibit thixotropic behavior. Shear vane measurements were also made on an in-situ analog of the 1/12-scale tank simulant. Simulant shear strength has been observed to be time dependent. The primary objective of obtaining video records of jet-sludge interaction was satisfied, and the records yielded jet location information which may be of use in completing model comparisons. The modeling effort is not part of this task, but this report also discusses test specific instrumentation, visualization techniques, and shear vane instrumentation which would enable improved characterization of jet-sludge interaction and simulant characteristics.

1/12-Scale mixing interface visualization and buoyant particle release tests in support of Tank 241-SY-101 hydrogen mitigation

International Nuclear Information System (INIS)

Eschbach, E.J.; Enderlin, C.W.

1993-10-01

In support of tank waste safety programs, visualization tests were performed in the 1/12-scale tank facility, using a low-viscosity simulant. The primary objective of the tests was to obtain video records of the transient jet-sludge interaction. The intent is that these videos will provide useful qualitative data for comparison with model predictions. Two tests were initially planned: mixing interface visualization (MIV) and buoyant particle release (BPR). Completion of the buoyant particle release test was set aside in order to complete additional MIV tests. Rheological measurements were made on simulant samples before testing, and the simulant was found to exhibit thixotropic behavior. Shear vane measurements were also made on an in-situ analog of the 1/12-scale tank simulant. Simulant shear strength has been observed to be time dependent. The primary objective of obtaining video records of jet-sludge interaction was satisfied, and the records yielded jet location information which may be of use in completing model comparisons. The modeling effort is not part of this task, but this report also discusses test specific instrumentation, visualization techniques, and shear vane instrumentation which would enable improved characterization of jet-sludge interaction and simulant characteristics

In-Tank Elutriation Test Report And Independent Assessment

International Nuclear Information System (INIS)

Burns, H. H.; Adamson, D. J.; Qureshi, Z. H.; Steeper, T. J.

2011-01-01

The Department of Energy (DOE) Office of Environmental Management (EM) funded Technology Development and Deployment (TDD) to solve technical problems associated with waste tank closure for sites such as Hanford Site and Savannah River Site (SRS). One of the tasks supported by this funding at Savannah River National Laboratory (SRNL) and Pacific Northwest Laboratory (PNNL) was In-Tank Elutriation. Elutriation is the process whereby physical separation occurs based on particle size and density. This report satisfies the first phase of Task WP 1 .3.1.1 In-Tank Elutriation, which is to assess the feasibility of this method of separation in waste tanks at Hanford Site and SRS. This report includes an analysis of scoping tests performed in the Engineering Development Laboratory of SRNL, analysis of Hanford's inadvertent elutriation, the viability of separation methods such as elutriation and hydrocyclones and recommendations for a path forward. This report will demonstrate that the retrieval of Hanford salt waste tank S-112 very successfully decreased the tank's inventories of radionuclides. Analyses of samples collected from the tank showed that concentrations of the major radionuclides Cs-136 and Sr-90 were decreased by factors of 250 and 6 and their total curie tank inventories decreased by factors of 60,000 and 2000. The total tank curie loading decreased from 300,000 Ci to 55 Ci. The remaining heel was nearly all innocuous gibbsite, Al(OH) 3 . However, in the process of tank retrieval approximately 85% of the tank gibbsite was also removed. Significant amounts of money and processing time could be saved if more gibbsite could be left in tanks while still removing nearly all of the radionuclides. There were factors which helped to make the elutriation of Tank S-112 successful which would not necessarily be present in all salt tanks. 1. The gibbsite particles in the tank were surprisingly large, as much as 200 o)m. The gibbsite crystals had probably grown in size over

Storage Tanks - Selection Of Type, Design Code And Tank Sizing

International Nuclear Information System (INIS)

Shatla, M.N; El Hady, M.

2004-01-01

The present work gives an insight into the proper selection of type, design code and sizing of storage tanks used in the Petroleum and Process industries. In this work, storage tanks are classified based on their design conditions. Suitable design codes and their limitations are discussed for each tank type. The option of storage under high pressure and ambient temperature, in spherical and cigar tanks, is compared to the option of storage under low temperature and slight pressure (close to ambient) in low temperature and cryogenic tanks. The discussion is extended to the types of low temperature and cryogenic tanks and recommendations are given to select their types. A study of pressurized tanks designed according to ASME code, conducted in the present work, reveals that tanks designed according to ASME Section VIII DIV 2 provides cost savings over tanks designed according to ASME Section VIII DlV 1. The present work is extended to discuss the parameters that affect sizing of flat bottom cylindrical tanks. The analysis shows the effect of height-to-diameter ratio on tank instability and foundation loads